ML20064G377: Difference between revisions

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| number = ML20064G377
| number = ML20064G377
| issue date = 12/04/1978
| issue date = 12/04/1978
| title = LER#78-083/03L-0 on 781102:noted That FNP-1-STP-41.2 Specified IR Neutron Flux High Level Trip Setpoint Limits Were Less Conservative than Tech Spec Limits.Caused by Failure to Revise FNP-1-STP-41.2 to Reflect New Setpoint
| title = /03L-0 on 781102:noted That FNP-1-STP-41.2 Specified IR Neutron Flux High Level Trip Setpoint Limits Were Less Conservative than Tech Spec Limits.Caused by Failure to Revise FNP-1-STP-41.2 to Reflect New Setpoint
| author name = Hairston W
| author name = Hairston W
| author affiliation = ALABAMA POWER CO.
| author affiliation = ALABAMA POWER CO.

Latest revision as of 22:37, 31 May 2023

/03L-0 on 781102:noted That FNP-1-STP-41.2 Specified IR Neutron Flux High Level Trip Setpoint Limits Were Less Conservative than Tech Spec Limits.Caused by Failure to Revise FNP-1-STP-41.2 to Reflect New Setpoint
ML20064G377
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 12/04/1978
From: Hairston W
ALABAMA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20064G368 List:
References
LER-78-083-03L, LER-78-83-3L, NUDOCS 7812110138
Download: ML20064G377 (4)


Text

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HC F ORM *.6.5 U. S NUCLEAR REGULATORY cOWISStoN

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. LICENSEE EVENT REPORT (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATIONI

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bJ 61 EVENT DESCRIPTION AND PROD A8LE CONSEQUENCES h 10121 lon 9/14/78 it was determined that FNP-1-STP-41.2 specified IR neutron flux high level [

lo!3I l trip setpoint limits which were less conservative than the limits specified in T/S l lo1.ilITable 2.2-1. FNP-1-STP-228.3.-228.4 and FNP-1-STP-41.2 were revised on 9/18/78 to l i o i s 1 Icorrect the discrepancy. A subsequent review of all completed FNP-1-STP-41.2 procedures; lulal idetermined that no T/S limits had been exceeded. The health / safety of the public were l

[~ -] I not af fected. This incident was determined to be reportable per T/S 6.9.1.9.c on l l

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$YSTEM CAUSE CAUSE CODE CODE SUS 0002 COMPONENT COOE SUSCODE SuaCOOE lOlst 11 l A l@ (D_j@ l Zl@ I Z i Z l Z i z I Z l18Z l@19LZ J@23(z lg 7 8 9 to 11 12 13 SEOuf NTf AL OCCURRENCE REPOR T REVISION ggp no EVENT YE AR REPORT NO. COOE TYPE NO.

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._21 2J 23 24 26 27 26 29 30 31 32 A P ACT ON ON PLANT T d Houas 22 #58 5 YIN [ FoRYSIUS. SU 'l E MAN A TURER Ic l@l zl@ l zl@ l36ZI@ l 01 ol o f I lNlg 46 lN]g lZlg lZl9l9l9(g 33 34 3a 37 40 42 43 44 47 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS 27 Iii] IIFNP-1-STP-41.2 uas not revised to reflect new IR neutron flux high level trip setpoint l FNP-1-STP-228.3, 4228.4 Li4y Ilinits established per FNP-1-STP-228.3, -228.4 on 4/29/78. i i i: l lwere revised to recuire I$C personnel to record setpoint values 11 a Surveillance Teott lil3l l Data Book (located in control room). FMP-1-STP-41.2 was revised to require operations; 1iisl 1 personnel to obtain correct setpoint values from the Surveillance Test Data Book. [

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ALABAMA POWER COMPAhT JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO. 50-348 ATTACHMENT TO LER 78-083/03L-0

_- Facility: Joseph M. Farley Unit 1

-f, * . . Report Date: December 4,1978

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Event Date: 9/14/78 (Event was determined to be' reportable on 11/2/78.)

1 Identification of Event 1

During the period from 4/29/78 to 9/14/78 the intermediate range neutron flux high level trip setpoint limits specified in Surveillance Test Procedure FNP-1-STP-41.2 were less conservative than required by Technical Specification Table 2.2-1 (s , Table I).

Conditions Prior to Event i The Unit was in Mode 1 operating at 100% steady state power.

Description of Event On 4/29/78, new intermediate range neutron flux high level trip

setpoints for Channels N35 and N36 were etablished per FNP-1-STP-228.3 and FNP-1-STP-228.4, Nuclear Instrumentation System Intermediate Range N35 (N36) Calibration and Function Check. At that time, FNP-1-STP-41.2, Intermediate Range Function Check N35 (N36), should have been revised to reflect the new setpoint limits. Through an oversight, this was not done. On 9/14/78 it was recognized that the limits specified in FNP-1-STP-41.2 were not the correct limits.

On 9/18/78 procedure revisions to FNP-1-STP-41.2, FNP-1-STP-228.3 and FNP-1-STP-228.4, were issued to correct the discrepancy and prevent recurrence of the incident.

Subsequent to revising the affected procedures, a review was made of all completed FNP-1-STP-41.2 procedures to determine if any Technical Specification limits had been exceeded. The review indicated that no limits were exceeded.

On 11/2/78 it was determined that this incident should be reported per Technical Specification 6.9.1.9.c. Using the incorrect limits in FNP-1-STP-41.2, it would have been possible to exceed the limiting safety system setting of Technical Specification Table 2.2-1, and '

the proper action required by Technical Specification 2.2.1 would not have been initiated.

r Designation of Apparent Cause FNP-1-STP-41.2 was not revised to reflect new intermediate range neutron flux high level trip setpoint limits when those limits were i

established per FNP-1-STP-228.3 and FNP-1-STP-228.4 on 4/29/78. ,

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. .s 78-083/01L-0 Analysis of Event A review of the FNP-1-STP-41.2 data for the period 4/29/78 to 9/14/78 indicated that the Technical Specification Table 7.2-1 intermediate range neutron flux high level trip setpoint limits were not exceeded. This occurrence had no effect on the health and srfety of the general public.

Effect on Plant This occurrence had no significant effect on plant operation.

Corrective Action -

FNP-1-STP-228.3 and FNP-1-STP-228.4 were revised to require I & C personnel to record setpoint values in a Surveillance Test Data Book which is located in the Control Room. FNP-1-STP-41.2 was revised to require Operations personnel to obtain the correct setpoint values from the Surveillance Test Data Book when the surveillance test is performed.

Failure Data None I

, l ... I 78-083/03L-0 TABII I

, Intermediate range neutron flux high level trip setpoint limits in FNP-1-STP-41.2 during period 4/29/78 to 9/14/78:

Trip Setpoint T/S Allowable Value N-35 4 amps ~4 amps 5 3.4 X 10 5 4.1 X 10 N-36 ~4 amps ~4 aps 1 4.1 X 10 5 4.9 X 10 The following are the limits established per FNP-1-STP-228.3 and FNP-1-STP-228.4 on 4/29/78:

Trip Setpoint T/S Allowable Value N-35 ~4 amps 4

, 1 2.3 X 10 1 2.8 X 10 amps N-36 4 4 1 3.8 X 10 amps 5 4.6 X 10 amps i The following are the actual trip values for the period 4/29/78 to

} 9/14/78:

Date N-35 N-36 l 4/29/78 2.1 X 104 amps 3.5 X 10~4 amps i 5/9/78 2.1 X 104 amps 3.3 X 10~4 amps 5/24/78 2.1 X 104 amps 3.3 X 104 amps 6/7/78 2.1 X 104 amps 3.1 X 104 amps 6/20/78 2.1 X 104 amps 3.5 X 104 amps

7/16/78 2.05 X 10~4 amps 3.7 X 104 amps 8/13/78 2.3 X 104 amps 3.8 X 104 amps 8/22/78 2.1 X 104 amps 3.5 X 10 4 amps i

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