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{{#Wiki_filter:consumers Power company . t=-1i..t-c.;P-f General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
{{#Wiki_filter:e*ov1~
* Area Code 517 788-0550 March 2, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -BR-78-005  
                                                                                          . t=-1i..t- c.;P-f consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
-STEAM .GENERATOR LEVEL INSTRUMENTATION The reverse side describes a reportable occurrence under Technical Specification 6.1.2.b(l) for the Palisades Plant. David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement 1978
* Area Code 517 788-0550 March 2, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - BR-78-005 - STEAM
** Palisades NRC FORM 366 (7*77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I I G) !PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
.GENERATOR LEVEL INSTRUMENTATION The reverse side describes a reportable occurrence under Technical Specification 6.1.2.b(l) for the Palisades Plant.
1 6 [IE] 7 8 IMIIIPIAILl1l@lolololololololo lob lo 101411111111101 I 10 9 LICENSEE COOE 14 LICENSE NUMBER 26 TYPE 30 57 CAT 58 CON'T [ill] 7 8 I 51 01bIo12 I 51 5*101 o I 21o12 17 I 8 IG)I o 13 10 12 17 1B10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@
David P Hoffman Assistant Nuclear Licensing Administrator CC:   Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement 1978
f During calibration of steam generator level instruments which provide []]1J I trip signals to the RPS. LT-0751C was found to have a setpoint of 40 inches. This setpoint is outside the limit of TS 2.3 (Table 2.3.1). The other three 'A' steam generator level instruments providing RPS trip signals were within specifications; as a result, the steam generator low I level trip was operable.
 
[ill] 1 .0 9 80 SYSTEM CAUSE CAUSE COMP. VALVE filII CODE CODE SUBCODE COMPONENT CODE SUBCOOE SUBCODE I II Al@ Lm@ I IIN Is I Tl I1 u1e L.!J 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION*
                                                                                                                  **                             Palisades NRC FORM 366                                                                                                               U.S. NUCLEAR REGULATORY COMMISSION (7*77)
c:;... LE RIRO Cy' 7ENT Y8EAR ROEPOORT N50. OC003E J.,YPEI !:>(0. \;.:) REPORT I I I I I I I I I/ I I I I r::......J I I L'.::.J NUMBER 21 22 23 24 26 27 28 29 30 31 32 TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUS. SUPPLIER MANUFAq"\JRER ACTION FUTURE EFFECT SHUTDOWN @> ATTACHMENT NPRD-4 PRIME COMP. COMPONENT l!J@) I q 010 I I L!J@ l:J@) EJ@ 1F 10 10 I@ 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORREC'rlVE ACTIONS @ I The occurrence is attributed to setpoint drift. During the recalibration  
LICENSEE EVENT REPORT CONTROL BLOCK:           I                               I G)                   !PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
!JJII Lprocesco, no transmitter mol f1mcti ons were detected.
1                               6
and the transmitter o::m OJI! was easily returned to specifications.
[IE]       IMIIIPIAILl1l@lolololololololo                                                           lob       lo 101411111111101                                       I 10 7      8    9         LICENSEE COOE             14     ~5                    LICENSE NUMBER                       ~5    26     LICENS~ TYPE 30             57 CAT 58 CON'T
No further action is contemplated.I o:::m 7 8 9 FACILITY STATUS % POWER DJI1 L!U@ 10 I o I 01@1 OTHER STATUS @ N;A I 80 METHOD OF r.:;:::-.
[ill]               ~~~~~ ~10                    I 51 01bIo12 I 51 5*101                         oI                                    o 21o12 17 I 8 IG)I 13 10 12 17 1B10 7      8                      60         61             DOCKET NUMBER               68     69       EVENT DATE           74       75         REPORT DATE                 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@
DISCOVERY
f During calibration of steam generator level instruments which provide
* DJSCOYE.8.Y DESC,RJPTION  
[]]1J I         trip signals to the RPS. LT-0751C was found to have a setpoint of 40 inches.             This setpoint is outside the limit of TS 2.3 (Table 2.3.1).
'8J
The other three 'A' steam generator level instruments providing RPS trip signals were within specifications; as a result, the steam generator low
___
~          I level trip was operable.
___
[ill]
____________
1     .0   9                                                                                                                                                                           80 SYSTEM           CAUSE         CAUSE                                                     COMP.             VALVE CODE               CODE       SUBCODE                   COMPONENT CODE                 SUBCOOE           SUBCODE filII 7      8 I
.....i 7 8 9 10 12 13 ACTIVITY CONTENT t.;;;\ REL1ifSED OF RELEASE I AMOUNT OF ACTIVITY [ill]
9 II Al@ Lm@ ~@)
_____ ___. 7 8 9 10 11 45 -40 80 N/A LOCATION OF RELEASE @ 44 45 80 PERSONNEL EXPOSURES NUMBER r:;:;.. TYPE DESCRIPTION
10          11          12 I IIN Is I Tl I1 u1e 13                              18 L.!J 19
[ill] I 01 010
                                                                                                                                                  ~@
_____________________
20 SEQUENTIAL                           OCCURRENCE         REPORT                         REVISION*
--J 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER
c:;... LE RIRO   Cy' 7ENT Y8EAR                         ROEPOORT N50.                           OC003E             J.,YPEI                               !:>(0.
[LlTI I 0 I 01 0
            \;.:) REPORT NUMBER 21 I I 22 I I 23 I I I I 24              26 I /I 27 I I 28      29 I       r::......J 30 I I 31 L'32.::.J ACTION FUTURE TAKEN ACTION EFFECT ON PLANT SHUTDOWN METHOD                   HOURS
________________________
                                                                                                @>    ATTACHMENT SUBMITTED NPRD-4 FORM SUS.
__J 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY G TYPE DESfflfA_JON I2:III
PRIME COMP.
______________________________
SUPPLIER COMPONENT MANUFAq"\JRER l!J@~@
____J 7 8 9 10 80 PUBLICITY Q r:;-r,::i 2 O NRC USE ONLY I I I I I I I I I I I I I 7 8 9 10 68 69 80}}
33          34
                                            ~@
35 l!J@)
36 I
37 q 010       I I L!J@
40    41 l:J@)
42 EJ@
43 1F ~ 10 10 44                        47 I@
CAUSE DESCRIPTION AND CORREC'rlVE ACTIONS                       @
I   The occurrence is attributed to setpoint drift.                                                           During the recalibration
!JJII       Lprocesco, no transmitter mol f1mcti ons were detected. and the transmitter o::m             was easily returned to specifications.                                                 No further action is contemplated.I OJI!
o:::m 7     8   9                                                                                                                                                                         80 FACILITY                                                                     METHOD OF                                                           r.:;:::-.
STATUS              %  POWER                      OTHER STATUS @            DISCOVERY
* DJSCOYE.8.Y DESC,RJPTION '8J DJI1        L!U@ 10 I o I 01@1 N;A                                                                      ___
I ~QD.l c_a_1_1_b_r~at~1_o_n___                      ~e_s_u_.~_~_s____________.....i 7     8 9                 10             12     13                                     45 -      40                                                                              80 ACTIVITY CONTENT                                                 t.;;;\
REL1ifSED OF RELEASE                   I AMOUNT OF ACTIVITY                                   N/A LOCATION OF RELEASE @
[ill] ~@) ~@l.__N_A_ _ _ _ ____.
7     8   9             10         11                                         44             45                                                                                   80 PERSONNEL EXPOSURES                           ~
NUMBER r:;:;.. TYPE             DESCRIPTION
[ill] I         01 010 k~~@~N:..../A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- - J 7       8   9               11     12         13                                                                                                                                   80 PERSONNEL INJURIES                 ~
NUMBER             DESCRJPTION~
[LlTI I         0 I 01 0 l@~N_;A              _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ J 7       8   9               11     12                                                                                                                                               80 LOSS OF OR DAMAGE TO FACILITY G I2:III       TYPE        DESfflfA_JON                ~
            ~@).___1_,__________________________________J 7       8   9           10                                                                                                                                                           80 PUBLICITY             Q O
r:;-r,::i 1rirrr'44\DES1fJ'_A10N~                                                                                                                      NRC   USE         ONLY
~7 2
8    9
                    -v~------------------------------l 10                                                                                                                68    I 69  I I I I I I I I           I I I 80I}}

Revision as of 10:03, 20 October 2019

License Event Report 1978-005-00 Re Steam Generator Level Instrumentation
ML18347B185
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/02/1978
From: Hoffman D
Consumer Energy Co
To: James Keppler
NRC/RGN-III
References
LER 1978-005-00
Download: ML18347B185 (2)
v • d • e


Text

e*ov1~

. t=-1i..t- c.;P-f consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 March 2, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - BR-78-005 - STEAM

.GENERATOR LEVEL INSTRUMENTATION The reverse side describes a reportable occurrence under Technical Specification 6.1.2.b(l) for the Palisades Plant.

David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement 1978

    • Palisades NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7*77)

LICENSEE EVENT REPORT CONTROL BLOCK: I I G) !PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!

1 6

[IE] IMIIIPIAILl1l@lolololololololo lob lo 101411111111101 I 10 7 8 9 LICENSEE COOE 14 ~5 LICENSE NUMBER ~5 26 LICENS~ TYPE 30 57 CAT 58 CON'T

[ill] ~~~~~ ~10 I 51 01bIo12 I 51 5*101 oI o 21o12 17 I 8 IG)I 13 10 12 17 1B10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@

f During calibration of steam generator level instruments which provide

[]]1J I trip signals to the RPS. LT-0751C was found to have a setpoint of 40 inches. This setpoint is outside the limit of TS 2.3 (Table 2.3.1).

The other three 'A' steam generator level instruments providing RPS trip signals were within specifications; as a result, the steam generator low

~ I level trip was operable.

[ill]

1 .0 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCOOE SUBCODE filII 7 8 I

9 II Al@ Lm@ ~@)

10 11 12 I IIN Is I Tl I1 u1e 13 18 L.!J 19

~@

20 SEQUENTIAL OCCURRENCE REPORT REVISION*

c:;... LE RIRO Cy' 7ENT Y8EAR ROEPOORT N50. OC003E J.,YPEI  !:>(0.

\;.:) REPORT NUMBER 21 I I 22 I I 23 I I I I 24 26 I /I 27 I I 28 29 I r::......J 30 I I 31 L'32.::.J ACTION FUTURE TAKEN ACTION EFFECT ON PLANT SHUTDOWN METHOD HOURS

@> ATTACHMENT SUBMITTED NPRD-4 FORM SUS.

PRIME COMP.

SUPPLIER COMPONENT MANUFAq"\JRER l!J@~@

33 34

~@

35 l!J@)

36 I

37 q 010 I I L!J@

40 41 l:J@)

42 EJ@

43 1F ~ 10 10 44 47 I@

CAUSE DESCRIPTION AND CORREC'rlVE ACTIONS @

I The occurrence is attributed to setpoint drift. During the recalibration

!JJII Lprocesco, no transmitter mol f1mcti ons were detected. and the transmitter o::m was easily returned to specifications. No further action is contemplated.I OJI!

o:::m 7 8 9 80 FACILITY METHOD OF r.:;:::-.

STATUS  % POWER OTHER STATUS @ DISCOVERY

  • DJSCOYE.8.Y DESC,RJPTION '8J DJI1 L!U@ 10 I o I 01@1 N;A ___

I ~QD.l c_a_1_1_b_r~at~1_o_n___ ~e_s_u_.~_~_s____________.....i 7 8 9 10 12 13 45 - 40 80 ACTIVITY CONTENT t.;;;\

REL1ifSED OF RELEASE I AMOUNT OF ACTIVITY N/A LOCATION OF RELEASE @

[ill] ~@) ~@l.__N_A_ _ _ _ ____.

7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER r:;:;.. TYPE DESCRIPTION

[ill] I 01 010 k~~@~N:..../A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- - J 7 8 9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRJPTION~

[LlTI I 0 I 01 0 l@~N_;A _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ J 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY G I2:III TYPE DESfflfA_JON ~

~@).___1_,__________________________________J 7 8 9 10 80 PUBLICITY Q O

r:;-r,::i 1rirrr'44\DES1fJ'_A10N~ NRC USE ONLY

~7 2

8 9

-v~------------------------------l 10 68 I 69 I I I I I I I I I I I 80I

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