ML17309A114: Difference between revisions

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{{#Wiki_filter:4 U.S.NUCLEAR REGULATORY COMMISSION 80-010/03L-0 LICENSEE EVENT REPORT (CAR 1275)QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 Qs.4 1 1 1 1 QE~QE LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 NRC FC 366I7.77)system.This constitutes a degradation of a system designed to contain radioactive
{{#Wiki_filter:4 NRC FC          366                                                                                                                U. S. NUCLEAR REGULATORY COMMISSION I7.77)                                                                                80-010/03L-0 LICENSEE EVENT REPORT (CAR 1275)
~O3 material.(T~S~6.9.2.b (4))Residual heat removal operation was continued through 6 a lternate discharge to RCS, and at lea st one steam generator wa s available CONTROL BLOCK: I[os)N Y R E G 1 Q2 0 8 9 LICENSEE CODE 14 15 CON'T~57"""~LQO 0 5 0 0 0 2 4 4QT 1 1 2 5 8 0 5 1 2 2 3 8 0 Qs 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO~o2 During a unit'hutdown a pinhole leak tva s found in the weld of a thermowell on the RHR~O6~O7~OB 7 8 9 80 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE F QTT 8 Q>>~CQTE P 1 P E X X QE~AQEE Z QEE 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPoRT~80+~01 0 Q>~03 QL Q 0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS+22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
CONTROL BLOCK:                                                    QI               (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~SQTE~ZQER~CQ25~ZQET O O 0 Z~WQ22~@@4~WQ25 X O S S Q 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 5 The initial weld was of poor quality and is believed to be the reason for the leak.The weld was repaired to current standards.
I                                  6
3 4 80 80 80 45 80 80 80 NRC USE ONLY 68 69 80 Ts o N E 3 1 5-5 2 4-4 4 4 6, ex t~2 1 4 S.M.Spector NAME OF PREPARER 7 8 9 FACILITY~30 METHOD OF STATUS%POWER OTHERSTATUS
[os)            N Y        R      E      G      1 Q2 0
~DISCOVERY DISCOVERY DESCRIPTION Q32~75 X Q25~00 0 Q25 Crevice cleaninp~AQOT Durinq operational tour 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q 6~Z Q33~ZQ34 NA NA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39~00 0 QET Qss NA 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION
LICENSE NUMBER                        25 Qs 26
~ZQ42 NA 7 8 9 10 I g 0}}
                                                                                                                                    .4     1     1 LICENSE TYPE 1     1 30 QE~QE 57 CAT 58 8   9         LICENSEE CODE               14       15 CON'T
~57                 """         ~LQO             0     5     0   0   0     2   4   4QT         1     1     2     5     8     0 74 5
75 1     2     2   3 REPORT DATE 8     0 Qs 80 7       8                       60           61               DOCKET NUMBER             68     69       EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO
~o2             During a unit'hutdown a pinhole leak tva s found in the weld of a thermowell on the RHR
~O3            system. This constitutes a degradation of a system designed to contain radioactive material          .    (T ~ S  ~  6 . 9 . 2 . b (4) )    Residual heat removal operation was continued through 6
a lternate          discharge to RCS, and at lea st one steam generator wa s available
~O6
~O7
~OB                                                                                                                                                                                       80 7       8   9 SYSTEM               CAUSE       CAUSE                                                           COMP.           VALVE CODE                 CODE       SUBCODE                 COMPONENT CODE                         SUBCODE           SUBCODE F     QTT         8   Q>>   ~CQTE             P   1     P     E   X X         QE       ~AQEE               Z   QEE 8                        9           10           11           12             13                                 18           19               20 7                                                                                                                                                                        REVISION SEQUENTIAL                           OCCURRENCE               REPORT Q17 LERIRO REPoRT ACTION FUTURE EVENT YEAR
                                      ~80 21        22 EFFECT
                                                              +23 SHUTDOWN
                                                                          ~01 24 REPORT NO.
0 26 Q>
27
                                                                                                                    ~03 28 ATTACHMENT CODE 29 NPRDQ TYPE QL 30 PRIME COMP.
Q 31 NO.
32 0
COMPONENT TAKEN ACTION                   ON PLANT             METHOD                 HOURS +22         SUBMITTED           FORM SUB.         SUPPLIER             MANUFACTURER
              ~SQTE ~ZQER                     ~CQ25               ~ZQET           O     O   0   Z           ~WQ22             ~@@4               ~WQ25             X     O     S   S Q
33           34                 35                 36           37                   40     41                 42                 43               44                 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                             Q27 5       The     initial weld               was of poor quality and is believed to be the reason for the leak.                                                               The weld was repaired to current standards.
3 4
80 7
~75 8   9 FACILITY STATUS X   Q25     ~00
                                    % POWER 0   Q25 OTHERSTATUS Crevice cleaninp
                                                                                    ~
                                                                                    ~30      METHOD OF DISCOVERY
                                                                                              ~AQOT           Durinq operational tour DISCOVERY DESCRIPTION Q32 7       8   9               10               12       13                           44     45           46                                                                             80 6
ACTIVITY CONTENT RELEASED OF RELEASE
              ~Z      Q33    ~ZQ34 AMOUNT OF ACTIVITY NA
                                                                                  ~                                                 NA LOCATION OF RELEASE         Q 7       8   9               10                                                       44           45                                                                                  80 PERSONNEL EXPOSURES NUMBER                 TYPE         DESCRIPTION Q39 7        8
              ~00 9
0 11 QET 12 Qss 13 NA 80 PERSONNEL INJURIES 7       8   9                 11       12                                                                                                                                               80 LOSS OF OR DAMAGE TO FACILITY TYPE         DESCRIPTION                     Q43
              ~ZQ42                                               NA 80 NRC USE ONLY 7           9           10                                                                                                                       68    69                              80  Ts 8
S. M. Spector                                                    oNE 3 1 5 5 2 4 4 4 4 6,        ex t  ~  2 14 NAME OF PREPARER
 
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Latest revision as of 09:55, 29 October 2019

LER 80-010/03L-0:on 801125,pinhole Leak Found in Weld on RHR Thermowell.Caused by Poor Quality Weld.Weld Repaired
ML17309A114
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/23/1980
From: Spector S
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17250A837 List:
References
LER-80-010-03L, LER-80-10-3L, NUDOCS 8012300525
Download: ML17309A114 (2)


Text

4 NRC FC 366 U. S. NUCLEAR REGULATORY COMMISSION I7.77) 80-010/03L-0 LICENSEE EVENT REPORT (CAR 1275)

CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

[os) N Y R E G 1 Q2 0

LICENSE NUMBER 25 Qs 26

.4 1 1 LICENSE TYPE 1 1 30 QE~QE 57 CAT 58 8 9 LICENSEE CODE 14 15 CON'T

~57 """ ~LQO 0 5 0 0 0 2 4 4QT 1 1 2 5 8 0 74 5

75 1 2 2 3 REPORT DATE 8 0 Qs 80 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~o2 During a unit'hutdown a pinhole leak tva s found in the weld of a thermowell on the RHR

~O3 system. This constitutes a degradation of a system designed to contain radioactive material . (T ~ S ~ 6 . 9 . 2 . b (4) ) Residual heat removal operation was continued through 6

a lternate discharge to RCS, and at lea st one steam generator wa s available

~O6

~O7

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE F QTT 8 Q>> ~CQTE P 1 P E X X QE ~AQEE Z QEE 8 9 10 11 12 13 18 19 20 7 REVISION SEQUENTIAL OCCURRENCE REPORT Q17 LERIRO REPoRT ACTION FUTURE EVENT YEAR

~80 21 22 EFFECT

+23 SHUTDOWN

~01 24 REPORT NO.

0 26 Q>

27

~03 28 ATTACHMENT CODE 29 NPRDQ TYPE QL 30 PRIME COMP.

Q 31 NO.

32 0

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~SQTE ~ZQER ~CQ25 ~ZQET O O 0 Z ~WQ22 ~@@4 ~WQ25 X O S S Q

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 5 The initial weld was of poor quality and is believed to be the reason for the leak. The weld was repaired to current standards.

3 4

80 7

~75 8 9 FACILITY STATUS X Q25 ~00

% POWER 0 Q25 OTHERSTATUS Crevice cleaninp

~

~30 METHOD OF DISCOVERY

~AQOT Durinq operational tour DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 6

ACTIVITY CONTENT RELEASED OF RELEASE

~Z Q33 ~ZQ34 AMOUNT OF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

0 11 QET 12 Qss 13 NA 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43

~ZQ42 NA 80 NRC USE ONLY 7 9 10 68 69 80 Ts 8

S. M. Spector oNE 3 1 5 5 2 4 4 4 4 6, ex t ~ 2 14 NAME OF PREPARER

I g 0