05000333/LER-1980-036-01, /01X-1:on 800417,during Normal Operation,Average Power Range Monitor F Found Operating W/One Level C Low Power Range Monitor Input.Caused by Failure to Declare Monitor F Inoperable After Low Power Monitor 800409 Calibr

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/01X-1:on 800417,during Normal Operation,Average Power Range Monitor F Found Operating W/One Level C Low Power Range Monitor Input.Caused by Failure to Declare Monitor F Inoperable After Low Power Monitor 800409 Calibr
ML19338G089
Person / Time
Site: FitzPatrick 
Issue date: 10/22/1980
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19338G081 List:
References
LER-80-036-01X, LER-80-36-1X, NUDOCS 8010280429
Download: ML19338G089 (2)


LER-1980-036, /01X-1:on 800417,during Normal Operation,Average Power Range Monitor F Found Operating W/One Level C Low Power Range Monitor Input.Caused by Failure to Declare Monitor F Inoperable After Low Power Monitor 800409 Calibr
Event date:
Report date:
3331980036R01 - NRC Website

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8 60 61 DOCKET NUMB sH 68 69 EV ENT OATE I4 75 REPORT C ATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o Io Ial l During normal operation personnel noted APMI F was operating with only one (1) l

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[ Level C LPM 1 input which is contrary to TS Table 3.1-1 Note 10.

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36 37 40 41 42 43 44 47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h lilo l [ LPB1 was bypassed' making APMI F inoperable.

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See attachment for details.

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JAMES A. FITZPATRICK NUCLEAR POWER PI).NT i

DOCKET No.50-333 ATTACHMENT TO LER 80- 036/01X-1 Page 1

of 1

During normal operations, personnel noted that Average Power Range Monitor (APRM) Channel F was operating with only one (1) "C" level Local Power Range Monitor (LPRM) input. Technical Specifications Table 3.1-1, j

Note 10, requires that a minimum of two (2) LPRM inputs from each level must be present for the APRM to be considered operable.

The other APRM channels in the same safety system (Channels "B" and "D") were fully operable with at least eleven (11) LPRM inputs and at least two (2) LPRM l

Inputs for each level.

l A review of plant operating records reveals that APRM "F" should have been declared inoperable on April 9,1980 at the completion of a LPRM calibration. At that time APRM ChTnnels "B" and "D" were operable.

Between April 9, 1980 and April 17, 1980 when the problem was discovered, any time period in which either APRM "B" or "D" was inoperable or bypassed, i

l only one (1) APRM would have been available, which is contrary to the i

requirements of Technical Specifications Table 3.1-1.

A review of the operating records indicates that either APRM Channel "B" or "D" was j-bypassed on seven (7) occasions for a total of approximately seventy-one (71) minutes during the April 9 to April 17, 1980 time period.

In i

addition, operation with only one (1) APRM in the B. safety system operable (that is, with APRM F inoperable and APRM B or D bypassed or inoperable) i is an' example of operation in a degraded mode that is less conservative than the least conservative aspect of the LCO established by Table 3.1-1 2

and is a reportable occurrence as defined by Paragraph 6.9. A.4.1.b.

As soon as the problem was discovered, APRM "F" was bypassed and the switch tagged to inform the operator that the switch must remain in the "APRM F Bypass" position unless other action to satisfy Technical j

Specifications is taken. This action, due to the design of the bypass j

switch, physically prevented the bypassing of APRM "B" or "D" thus assuring that the requirements of Table 3.1-1 were met.

Since the root cause of the problem was the failure of personnel to recogni;e or communicate

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the status of APRM,i'F", the bypassing of APRM "B" or "D" was not recogni:ed as causing operation in conflict with the Technical Sp.cifications.

Accordingly, to preclude recurrence,. administrative controls which i

specifically require a determination of the status of an APRM Channel whenever a LPRM is bypassed, have.been developed and were implemented prior to startup following the 1980 refueliag outage.

No additional action is required.

The event-did not represent a significant hazard to

.the public health and safety.

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Revision 1Lis submitted to. correct or revise Items 10, 17,-19,-27 and the attachment.

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