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| issue date = 06/06/1980
| issue date = 06/06/1980
| title = LER 80-003/03L-0:on 800514,w/unit in Cold Shutdown, MOV-CW-2008 Failed to Close on Safeguard Signal.Caused by Electrical Malfunction Due to Repairs in Progress.Redundant Inlet Valve Shut.Valve Will Be Repaired & Tested
| title = LER 80-003/03L-0:on 800514,w/unit in Cold Shutdown, MOV-CW-2008 Failed to Close on Safeguard Signal.Caused by Electrical Malfunction Due to Repairs in Progress.Redundant Inlet Valve Shut.Valve Will Be Repaired & Tested
| author name = WILSON J L
| author name = Wilson J
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:NRC FORM 366 -U.S. NUCLEAR REGULATORY COMMISSION (7-77) ..,. .LICENSEE EVENT REPORT e CONTROL BLOCK: I I r.j'\ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
{{#Wiki_filter:NRC FORM 366               -                                                                                                                       U.S. NUCLEAR REGULATORY COMMISSION (7-77)
L---'--....._-'-'----'---'----'6  
                                                                              .LICENSEE EVENT REPORT                                                       e CONTROL BLOCK:                                         I ~ I\V L---'--....._-'-'----'---'----'6 r.j'\               (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
\V CTA I s Ip Is I 2 101 ° I O I -1 ° I O I O I O [ 0 I -[ 0 I O 10[ 4 [1 [ 1 [ 1 [1 181 I I© 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [IT]] 7 8 L:'...J© I o I s Io I o I o I 21 s I 1 101 o I s I 1 I 4 I s I o 101 o I 6 I o .I 6 I s Io I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ . I With the unit at cold shutdown, MOV-CW-200B was found inoperable.
  ~
The failure of the [£JI] I MOV to close on a safeguards signal is non-conservative with respect to Technical I Specification 3.14.A.l.
7        8 CTA I s Ip Is I 2 101 °I OI -1 °I O I O I O [ 0 I - [ 0 I O 10[ 4 [1 [ 1 9          LICENSEE CODE                14      15                        LICENSE NUMBER                        25            26              LICENSE TYPE
This event is reportable per Technical Specification 6.6.2.b.2.
[1        [1 181 30 I I© 57 CAT 58 CON'T
1 [§I§] I The health and safety of the general public was not affected because the safety related [QJI] I function of the redundant valve was operable.  
[IT))                  :~~~~~' L:'...J© I             oI s Io I oI oI                  21     s I 1 101 o I s I 1 I 4 I s I o 101 o I 6 I o .I 6 I s Io IG) 7        8                          60           61             DOCKET NUMBER                     68   69     EVENT DATE                           74           75                   REPORT DATE             80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .
[ITD []]]] 7 8 9 80 [ITIJ 7 8 SYSTEM CODE 1w !A I@ 9 10 Q LER!RO LVENTYEAR
I With         the unit at cold shutdown, MOV-CW-200B was found inoperable.                                                                                             The failure of the
\!..Y REPORT I 8 10 I NUMBER 21 22 CAUSE CAUSE CODE SUBCODE COMPONENT CODE ~@ L!.J@ Iv [ Aj 11 v1 Ej xi@ 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO. CODE I . I I o I o I 3 I I/[ I o I 3 I 23 24 26 2 7 28 29 COMP. VALVE SUBCODE SUBCODE ~ w@ 19 20 REPORT TYPE l.1J l.=J 30 31 ACTION FUTURE EFFECT SHUTDOWN Q., ATTACHMENT NPRD-4 PRIME COMP. SUPPLIER REVISION NO. l_QJ 32 COMPONENT MANUFACTURER TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. ~@~@ ~@ ~ 101010101 L!J@ ~@) 33 34 35 36 37 40 41 42 l_aj@ I PI 3 1 4 I O I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 43 44 I The valve was under mechanical repair and will be repaired and tested for operability.  
[£JI] I MOV               to close on a safeguards signal is non-conservative with respect to Technical
[[OJ I The corrective action taken was to shut the redundant inlet valve. [I]I} 7 8 9 FACILITY STATUS % POWER OTHER STATUS METHOD OF A 47 80 0 ! 0 I O !@)IL-_..:;!:NA:.=__
  ~            I Specification 3.14.A.l.                                 This event is reportable per Technical Specification 6.6.2.b.2.
___ .,-l 10 12 1'3 o=ITJ W@ DISCOVERY DISCOVERY DESCRIPTION
1
'23; W@L.l -~o~p~e=.=r...:.a""'t=..)o.._r"---'o,...b""""'s_,.e.,.r-"v_..a  
[§I§] I The health and safety of the general public was not affected because the safety related
.... t .... i.,,o,...n,__
[QJI] I function of the redundant valve was operable.
________ ---,1 8 9 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~  
[ITD
[£JI] W@ LIJ@I NA 7 8 9 10 11 PERSONNEL EXPOSURES r::;:;,_ 44 44 45 46 .. LOCATION OF RELEASE @ 80 NA 45 80 NUMBER Q. TYPE DESCRIPTION~  
[))))
[2I?] 1 o, o , 0J0w'---~NA:::.:__
7       8   9                                                                                                                                                                                                               80 SYSTEM               CAUSE              CAUSE                                                                      COMP.                            VALVE CODE                 CODE            SUBCODE                  COMPONENT CODE                                SUBCODE                            SUBCODE
_____________________ 7 8 9 11 12 13 PERSONNEL INJURIES Q 80 NUMBER DESCRIPTION6 i O j O I O l@'-----.....:N=A:..._
[ITIJ                                  1w !A I@ ~@ L!.J@ Iv [ Aj 11                                                   v1   Ej xi@                           ~ w@
_____________________
7        8                          9          10            11                12                13                                 18                   19                                20 SEQUENTIAL                         OCCURRENCE                           REPORT                                          REVISION Q        LER!RO LVENTYEAR                                            REPORT NO.                             CODE                                 TYPE                                          NO.
__. 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4J' TYPE DESCRIPTIO*, uJ@)L-._ ______ ~NA::.!--'-
                \!..Y    REPORT NUMBER I   8  10    I         I23 . I           I o I o I 326I            I/[          I28 oI 329I                            l.1J                            l.=J           l_QJ 21          22                            24                        27                                                  30                               31           32 ACTION         FUTURE               EFFECT           SHUTDOWN                                 Q.,   ATTACHMENT                   NPRD-4                   PRIME COMP.                           COMPONENT TAKEN         ACTION             ON PLANT             METHOD                         HOURS ~        SUBMITTED               FORM SUB.                         SUPPLIER                        MANUFACTURER
--------------------------'
                ~@~@
7 8 9 10 80 PU!lLICITY  
33              34
(:;;'\ NRC USE ONLY ISSUEDt:;":;;,/ESCRIPTION * "' [ITIJ LNJ~.__~*~~~~-NA~~-~~-~~~-~-~~-J I I I I I I I I I I I I I~ 7 8 9 10 68 69 80 0* ~,AME OF ?RE PARER------------------
                                                  ~@
8 0061 2 033'l S J. L. Wilson PHONE: _(_8_04_)_3_5_7_-_3_1_8_4
35
___ _ 0 [!. " 
                                                                      ~
, ~ATTACHMENT (PAGE 1 OF 1) SURRY POWER STATION, UNIT DOCKET NO: 50-281 REPORT NO: 80-005/0lT-Q EVENT DATE: 3-6-80.
36 101010101 37                    40 L!J@
* TITLE OF EVENT: RECIRCULATION SPRAY HEAT EXCHANGER  
41
: 1. DESCRIPTION OF EVENT: During preparation for Type "A 11 testing, leakage was identified through Recirculation Spray Heat Exchanger diaphragm plate seal weld cracks. The components affected were 2-RS-E-lB, C, and D. The event is reportable per Tech. Specs. 6.6.2.a.9.  
                                                                                                                                                  ~@)
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: The affected reactor unit was at cold shutdown and the leakage was discovered during testing, therefore, there were no consequences as a result of the event, and the health and safety of the public were not affected-.  
42 l_aj@
: 3. CAUSE: The leaking seal weld cracks are attributed to lack of fusion and slag inclusion in the weld areas from previous maintenance work. 4. IMMEDIATE CORRECTIVE ACTION: The immediate corrective action was to have the Architect~Engineer perform a detailed stress analysis on the heat exchangers to determine if a design error had been committed.
43 I PI 3 14 I O I 44              47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                   @
Simultaneously, discussions were held with maintenance personnel and all maintenance histories were searched to determine the exact repairs that had been made to the affected components.  
I The       valve was under mechanical repair and will be repaired and tested for operability.
: 5. SUBSEQUENT CORRECTIVE ACTIONS: All defects found to date have been in the diaphragm plate seal weld area. All welds will be liquid penetrant inspected and all defects will be repaired.
((OJ I The                 corrective action taken was to shut the redundant inlet valve.
Stress analysis proved the design of the heat exchangers to be conservative; however, a modification is being made to incorporate a gasket between the diaphragm plate and heat exchanger cover to reduce stress on the diaphragm plate seal weld from external pressure forces. 6. FUTURE CORRECTIVE ACTION: No further corrective action is anticipated.  
[I]I}
7       8   9                                                                                                                                                                                                             80 FACILITY                                                                                   METHOD OF                                                                                            A STATUS                 % POWER                         OTHER STATUS                     DISCOVERY                                        DISCOVERY DESCRIPTION                              '23; o=ITJ W@                              0 ! 0 I O!@)IL-_..:;!:NA:.=___ _ _                        .,-l     W@L.l-~o~p~e=.=r...:.a""'t=..)o.._r"---'o,...b""""'s_,.e.,.r-"v_..a....t....i.,,o,...n,__________                ---,1 8   9                   10              12      1'3                                  44      45        46                                                                                                      80 ACTIVITY           CONTENT                                                     ~
RELEASED         OF RELEASE                     AMOUNT OF ACTIVITY~                                                                   ..LOCATION OF RELEASE                                @
[£JI] W@ LIJ@I                                                       NA                                                  NA 7       8     9                 10           11                                                 44          45                                                                                                            80 PERSONNEL EXPOSURES                               r::;:;,_
NUMBER         Q. TYPE             DESCRIPTION~
[2I?]         1 o,       o,     0J0w'---~NA:::.:___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
7       8   9                   11     12           13                                                                                                                                                                 80 PERSONNEL INJURIES                   Q NUMBER               DESCRIPTION6
~            i O j O I O l@'-----.....:N=A:...__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.
8   9                   11       12                                                                                                                                                                               80 LOSS OF OR DAMAGE TO FACILITY                   '4J' TYPE           DESCRIPTIO*,                     ~
~
7        8 9 uJ@)L-._       10
______~NA::.!--'-- - - - - - - - - - - - - - - - - - - - - - - - - - '                                                                                                                   80 PU!lLICITY               (:;;'\                                                                                                                                                 NRC USE ONLY ISSUEDt:;":;;,/ESCRIPTION ~                                                                                                                                                                  *                     "'
[ITIJ 7        8 LNJ~.__~*~~~~-NA~~-~~-~~~-~-~~-J 9              10                                                                                                                                              68            69 I I I I I I I I I I       I I 80 I~
0*
J. L. Wilson                                                                PHONE: _(_8_04_)_3_5_7_-_3_1_8_4_ _ __                                          0
                              ~,AME OF ?RE P A R E R - - - - - - - - - - - - - - - - - -                                                                                                                                         [!.
8 0061 2 033'l                               S                                                                                                                                                                               "
 
, ~ATTACHMENT (PAGE 1 OF 1)
SURRY POWER STATION, UNIT DOCKET NO:
REPORT NO:
50-281 80-005/0lT-Q EVENT DATE: 3-6-80.
TITLE OF EVENT:   RECIRCULATION SPRAY HEAT EXCHANGER
: 1. DESCRIPTION OF EVENT:
During preparation for Type "A 11 testing, leakage was identified through Recirculation Spray Heat Exchanger diaphragm plate seal weld cracks. The components affected were 2-RS-E-lB, C, and D. The event is reportable per Tech. Specs. 6.6.2.a.9.
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
The affected reactor unit was at cold shutdown and the leakage was discovered during testing, therefore, there were no consequences as a result of the event, and the health and safety of the public were not affected-.
: 3. CAUSE:
The leaking seal weld cracks are attributed to lack of fusion and slag inclusion in the weld areas from previous maintenance work.
: 4. IMMEDIATE CORRECTIVE ACTION:
The immediate corrective action was to have the Architect~Engineer perform a detailed stress analysis on the heat exchangers to determine if a design error had been committed. Simultaneously, discussions were held with maintenance personnel and all maintenance histories were searched to determine the exact repairs that had been made to the affected components.
: 5. SUBSEQUENT CORRECTIVE ACTIONS:
All defects found to date have been in the diaphragm plate seal weld area.
All welds will be liquid penetrant inspected and all defects will be repaired.
Stress analysis proved the design of the heat exchangers to be conservative; however, a modification is being made to incorporate a gasket between the diaphragm plate and heat exchanger cover to reduce stress on the diaphragm plate seal weld from external pressure forces.
: 6. FUTURE CORRECTIVE ACTION:
No further corrective action is anticipated.
: 7. GENERIC IMPLICATIONS:
: 7. GENERIC IMPLICATIONS:
Two of four RSHX's in Unit 1 have been subjected to maintenance by the turer's (YUBA) personnel.
Two of four RSHX's in Unit 1 have been subjected to maintenance by the manufac-turer's (YUBA) personnel. The welds on all four heat exchangers will be examined by Non-destructive methods during the next scheduled unit shutdown of sufficient duration. A gasket will be installed in Unit l's RSHX's between diaphragm plate and heat exchanger cover at that time.}}
The welds on all four heat exchangers will be examined by Non-destructive methods during the next scheduled unit shutdown of sufficient duration.
A gasket will be installed in Unit l's RSHX's between diaphragm plate and heat exchanger cover at that time.}}

Latest revision as of 12:49, 17 March 2020

LER 80-003/03L-0:on 800514,w/unit in Cold Shutdown, MOV-CW-2008 Failed to Close on Safeguard Signal.Caused by Electrical Malfunction Due to Repairs in Progress.Redundant Inlet Valve Shut.Valve Will Be Repaired & Tested
ML18139A307
Person / Time
Site: Surry Dominion icon.png
Issue date: 06/06/1980
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A306 List:
References
LER-80-003-03L-02, LER-80-3-3L-2, NUDOCS 8006120339
Download: ML18139A307 (2)
v • d • e


Text

NRC FORM 366 - U.S. NUCLEAR REGULATORY COMMISSION (7-77)

.LICENSEE EVENT REPORT e CONTROL BLOCK: I ~ I\V L---'--....._-'-'----'---'----'6 r.j'\ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~

7 8 CTA I s Ip Is I 2 101 °I OI -1 °I O I O I O [ 0 I - [ 0 I O 10[ 4 [1 [ 1 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE

[1 [1 181 30 I I© 57 CAT 58 CON'T

[IT))  :~~~~~' L:'...J© I oI s Io I oI oI 21 s I 1 101 o I s I 1 I 4 I s I o 101 o I 6 I o .I 6 I s Io IG) 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .

I With the unit at cold shutdown, MOV-CW-200B was found inoperable. The failure of the

[£JI] I MOV to close on a safeguards signal is non-conservative with respect to Technical

~ I Specification 3.14.A.l. This event is reportable per Technical Specification 6.6.2.b.2.

1

[§I§] I The health and safety of the general public was not affected because the safety related

[QJI] I function of the redundant valve was operable.

[ITD

[))))

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

[ITIJ 1w !A I@ ~@ L!.J@ Iv [ Aj 11 v1 Ej xi@ ~ w@

7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q LER!RO LVENTYEAR REPORT NO. CODE TYPE NO.

\!..Y REPORT NUMBER I 8 10 I I23 . I I o I o I 326I I/[ I28 oI 329I l.1J l.=J l_QJ 21 22 24 27 30 31 32 ACTION FUTURE EFFECT SHUTDOWN Q., ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~@~@

33 34

~@

35

~

36 101010101 37 40 L!J@

41

~@)

42 l_aj@

43 I PI 3 14 I O I 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I The valve was under mechanical repair and will be repaired and tested for operability.

((OJ I The corrective action taken was to shut the redundant inlet valve.

[I]I}

7 8 9 80 FACILITY METHOD OF A STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION '23; o=ITJ W@ 0 ! 0 I O!@)IL-_..:;!:NA:.=___ _ _ .,-l W@L.l-~o~p~e=.=r...:.a""'t=..)o.._r"---'o,...b""""'s_,.e.,.r-"v_..a....t....i.,,o,...n,__________ ---,1 8 9 10 12 1'3 44 45 46 80 ACTIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ ..LOCATION OF RELEASE @

[£JI] W@ LIJ@I NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES r::;:;,_

NUMBER Q. TYPE DESCRIPTION~

[2I?] 1 o, o, 0J0w'---~NA:::.:___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

7 8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION6

~ i O j O I O l@'-----.....:N=A:...__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.

8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4J' TYPE DESCRIPTIO*, ~

~

7 8 9 uJ@)L-._ 10

______~NA::.!--'-- - - - - - - - - - - - - - - - - - - - - - - - - - ' 80 PU!lLICITY (:;;'\ NRC USE ONLY ISSUEDt:;":;;,/ESCRIPTION ~ * "'

[ITIJ 7 8 LNJ~.__~*~~~~-NA~~-~~-~~~-~-~~-J 9 10 68 69 I I I I I I I I I I I I 80 I~

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J. L. Wilson PHONE: _(_8_04_)_3_5_7_-_3_1_8_4_ _ __ 0

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SURRY POWER STATION, UNIT DOCKET NO:

REPORT NO:

50-281 80-005/0lT-Q EVENT DATE: 3-6-80.

TITLE OF EVENT: RECIRCULATION SPRAY HEAT EXCHANGER

1. DESCRIPTION OF EVENT:

During preparation for Type "A 11 testing, leakage was identified through Recirculation Spray Heat Exchanger diaphragm plate seal weld cracks. The components affected were 2-RS-E-lB, C, and D. The event is reportable per Tech. Specs. 6.6.2.a.9.

2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:

The affected reactor unit was at cold shutdown and the leakage was discovered during testing, therefore, there were no consequences as a result of the event, and the health and safety of the public were not affected-.

3. CAUSE:

The leaking seal weld cracks are attributed to lack of fusion and slag inclusion in the weld areas from previous maintenance work.

4. IMMEDIATE CORRECTIVE ACTION:

The immediate corrective action was to have the Architect~Engineer perform a detailed stress analysis on the heat exchangers to determine if a design error had been committed. Simultaneously, discussions were held with maintenance personnel and all maintenance histories were searched to determine the exact repairs that had been made to the affected components.

5. SUBSEQUENT CORRECTIVE ACTIONS:

All defects found to date have been in the diaphragm plate seal weld area.

All welds will be liquid penetrant inspected and all defects will be repaired.

Stress analysis proved the design of the heat exchangers to be conservative; however, a modification is being made to incorporate a gasket between the diaphragm plate and heat exchanger cover to reduce stress on the diaphragm plate seal weld from external pressure forces.

6. FUTURE CORRECTIVE ACTION:

No further corrective action is anticipated.

7. GENERIC IMPLICATIONS:

Two of four RSHX's in Unit 1 have been subjected to maintenance by the manufac-turer's (YUBA) personnel. The welds on all four heat exchangers will be examined by Non-destructive methods during the next scheduled unit shutdown of sufficient duration. A gasket will be installed in Unit l's RSHX's between diaphragm plate and heat exchanger cover at that time.

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