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{{#Wiki_filter:. a. ew LtAH Ht~ULA OHY COMMISSION 17-77)LICENSEE EVENT REPORT
{{#Wiki_filter:. a. ew       LtAH Ht~ULA OHY COMMISSION 17-77)
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LICENSEE EVENT REPORT CONTROL BLOCK:                   l    l    l    l    l      l                    (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1                                 6 l 0 l8i 9l lN LICENSEE
llllll(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6l 0 l i l lN lY lJ lA lF l 1 l@l0 l0l-l0l0 0 l 0 l - l 0 l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l l@?8 9 LICENSEE LODE 14 15 LICENSE Nuv8EH 25 26 LICENSE TYPE JO 57 CAT 58 CON'T 3E l L l@l 0 S l 01010131313 l@l 01910171719 l@ll 10 l0141719 l@
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[Z_j @ lZl@l NAlNA i ol7 8 9 10 11 44 45 PERSONNEL EXPOSURES 80 NUMBE H TYPE DESCRIPTION l i l 7 l l 0 l 0 l 0 l@l Z l@l l'" *PERSONNEL INJUF IES , .NUVBER DESCRIP TION 6 i (li ja l l 0l 0 0l@l NA"i.''l'~-7 8 9 ,, ,2 LO;d OF OH DAVAGE TO FACILITY Q j(),.).60 TYPE DESCRIPTION
75       REPORT D ATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o     2 l                                    Please See Attachment                                                                                                                         l 10i311                                                                                                                                                                                -
%.'7910 0.-- *li191IZl@L NAl7 8 9 10 80 12 l a l LN @ DESCRIPTION ISSUE*lNAl[jllllllllll;7 d 9 l'68 69 80 &W. Verne Childs 315-342-3840 o NAVE OF PREPAPER PHONE:$  
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'POWER AUTHORITY OF THE STATE OF NEW YORK
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, JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 iTTACHMENT TO LER 79-066/03L-0 Page 1 of I During normal operation while conducting Operationn Surveillance Test F-ST-5Q titled " Flow Bias Functional Test" to satisfy the requirenents of Technical Speci-fications Appendix A, Table 3.1-1, Average Power Range Monitor (APRM) channels A, D, and F tripped at a value of 120.5 compared to a Technical Specification require-ment of equal to or less than 120% of rated power.
l O    6         l l
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o   8        l 7          8 9                                                                                                                                                                           80 OE             CODE       SU8C E                     COYPONE NT CODE                 SLB                 SU 7
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_                                          SEQUENTI AL                           OCCUR R E N CE       REPORT                           REVISION LER RO       EVENT YEAR                               R EPORT NO.                             CODE                 TYPE                             N .
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Jg        l 0 lYACTURER 44               47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i   O        l                              Please See Attachment                                                                                                                       l
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PERSONNEL EXPOSURES                                                                                                                                               80 NUMBE H             TYPE         DESCRIPTION l i l 7" l *l 0 l 0 l 0 l@l Z l@l l
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NUVBER             DESCRIP TION                                                                                                     6 i           (
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W. Verne Childs                                                                 315-342-3840                               o NAVE OF PREPAPER                                                                                       PHONE:                                                         $
 
,                        POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 iTTACHMENT TO LER 79-066/03L-0                     Page 1     of   I During normal operation while conducting Operationn Surveillance Test F-ST-5Q titled " Flow Bias Functional Test" to satisfy the requirenents of Technical Speci-fications Appendix A, Table 3.1-1, Average Power Range Monitor (APRM) channels A, D, and F tripped at a value of 120.5 compared to a Technical Specification require-ment of equal to or less than 120% of rated power.
Operations personnel bypassed channel ' A' and inserted a hal f scram into the
Operations personnel bypassed channel ' A' and inserted a hal f scram into the
'B'side of the RPS System to meet the requi rements of Technical Specifications.
    'B' side of the RPS System to meet the requi rements of Technical Specifications.
Plant operation continued in this manner until Instrumentation and Control Tech-nicians investigated the problem on the following day.
Plant operation continued in this manner until Instrumentation and Control Tech-nicians investigated the problem on the following day.       This investigation could not reproduce the out of tolerance trip values noted earlier and retest of the instruments utilizing F-ST-5Q revealed that the trip points were within the limits of Technical Speci fications therefore, the event did not represent any significant hazard to the public health and safety.       In view of these findings, the hal f scram was removed from the   'B'   side of the Reactor Protection System and the APRM System was restored to normal.
This investigation could not reproduce the out of tolerance trip values noted earlier and retest of the instruments utilizing F-ST-5Q revealed that the trip points were within the limits of Technical Speci fications therefore, the event did not represent any significant hazard to the public health and safety.
                              .}}
In view of these findings, the hal f scram was removed from the
'B'side of the Reactor Protection System and the APRM System was restored to normal.
.}}

Latest revision as of 05:27, 2 February 2020

LER 79-066/03L-0:on 790907,average Power Range Monitor Channels A,D & F Tripped at Value of 120.5% Compared to Tech Spec Requirements of 120%.Half Scram Removed & Channel Returned to Svc
ML19209B650
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/04/1979
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209B647 List:
References
LER-79-066-03L, LER-79-66-3L, NUDOCS 7910100273
Download: ML19209B650 (2)


Text

. a. ew LtAH Ht~ULA OHY COMMISSION 17-77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l 0 l8i 9l lN LICENSEE

?

lY lJ LODE lA lF l 1 l@l0 l0l-l0l0 14 15 0 l 0 l - l 0 l 0 l 025l@l 4 l 1 l 1 l 1 l 1 l@l LICENSE Nuv8EH 26 l

LICENSE TYPE JO 57 CAT 58 CON'T 7

O 1 8

3E l L60 l@l 0 S lDOCKET 61 01010131313 NUVB ER 6d l@l 63 01910171719 EVENT DATE 74 l@ll 10 l014171980l@

75 REPORT D ATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l Please See Attachment l 10i311 -

l o 4 l l

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l O 6 l l

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o 8 l 7 8 9 80 OE CODE SU8C E COYPONE NT CODE SLB SU 7

o 9 8

ll [E l @ [A [@ l Al@ ll [ N l S l r l R lU [g l fDElg l blEg 9 10 11 12 13 18 19 20

_ SEQUENTI AL OCCUR R E N CE REPORT REVISION LER RO EVENT YEAR R EPORT NO. CODE TYPE N .

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Jg l 0 lYACTURER 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i O l Please See Attachment l

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NUVBER DESCRIP TION 6 i (

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  • 12 l a l LN @ l DESCRIPTION NA l [jllll llllll; 7 d 9 l' 68 69 80 &

W. Verne Childs 315-342-3840 o NAVE OF PREPAPER PHONE: $

, POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 iTTACHMENT TO LER 79-066/03L-0 Page 1 of I During normal operation while conducting Operationn Surveillance Test F-ST-5Q titled " Flow Bias Functional Test" to satisfy the requirenents of Technical Speci-fications Appendix A, Table 3.1-1, Average Power Range Monitor (APRM) channels A, D, and F tripped at a value of 120.5 compared to a Technical Specification require-ment of equal to or less than 120% of rated power.

Operations personnel bypassed channel ' A' and inserted a hal f scram into the

'B' side of the RPS System to meet the requi rements of Technical Specifications.

Plant operation continued in this manner until Instrumentation and Control Tech-nicians investigated the problem on the following day. This investigation could not reproduce the out of tolerance trip values noted earlier and retest of the instruments utilizing F-ST-5Q revealed that the trip points were within the limits of Technical Speci fications therefore, the event did not represent any significant hazard to the public health and safety. In view of these findings, the hal f scram was removed from the 'B' side of the Reactor Protection System and the APRM System was restored to normal.

.