ML19341A017

LER 80-109/03L-0:on 801230,steam Generator Water Level low-low Reactor Trip Setpoint Found at 15% Narrow Range Instrument Span on All Generators Rather than 18% Level. Caused by Oversight by Administrative Personnel

ML19341A017
Person / Time
Site:	North Anna
Issue date:	01/15/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19341A016	List: ML19341A015 ML19341A017
References
LER-80-109-03L, LER-80-109-3L, NUDOCS 8101210446
Download: ML19341A017 (2)

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j U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[0/1/ /V/A/N/A/S/1/ (2) /0/0/-/0/0/0/0/0/-/0/0/ (3) /4/1/1/1/1/ (4) / / / (5)

LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT E /L/ (6) /0/5/0/0/0/3/3/8/

DOCKET NUMBER (7) ' /1/2/3/0/8/0/

EVENT DATE (8) / o f 3/ 3/gj (9)

REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

/0/2/ / On December 30, 1980 during Mode 5 operation, it was discovered that the /

/0/3/ / Steam Generator Water Level Low-Low Reactor trip setpoint was at 15% narrow /

/0/4/ / range instrument span on all three steam generator rather than at 18% level /

/0/5/ / as required by T.S. 3.2.2.1 (13). This event is reportable pursuant to T.S. /

/0/6/ / 6.9.1.9.c. /

/0/7/ / /

/0/8/ / /

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

/0/9/ /I/B/ (11) g/ (12) /B/ (13) /I/N/S/T/R/U/ (14) g/ (15) LZ/ (16)

SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO. CODE TYPE NO.

(17) REPORT NUMBER /8/0/ /-/ /1/Of_ [1/ /0/3/ g/ /-/ /0/

ACTION FUTUP.E EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

/_E/ (18) /_X/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) /Y/ (23) /N/ (24) [N/ (25) /W/1/2/0/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/ / This event was caused by an oversight by administrative personnel. The Low- /

/1/1/ /j aw Level comparator will be recalibrated to the 18% setpoint prior to entering /

/1/2/ / Moje_ 4. Procedurg change requests have been submitted for the periodic cali- /

/1/3/ / bration procedure. /

/1/4/ / /

FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DESCRIPTION (32)

/1/5/ /G/ (28) /0/0/0/ (29) / NA / (30) DISCOVERY

/A/ (31) / OPERATOR OBSERVATION /

ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35) LOCATION OF RELEASE (36)

/1/6/ /Z/ (33) /Z/ (34) / NA / / NA /

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (171 /Z/ (38) / NA /

PERSONNEL INJURIES NUMBER DESCRIPTION (41) -

/1/8/ /0/0/0/ (40) / NA .l / _

LOSS TYFr. OF OR DAMAGE TO FACILITY (43)

DESCRIPTION

/1/9/ /Z/ ( M / NA /

PUBLICITY ISSUED DESCRIPTION (45) NRC USE ONLY

/2/0/ [N[ (44) / NA /////////////

NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 8103 210h[p

O Virginia Electric and Power Company North Anna Power Station, Unit #1

Attachment:

Page 1 of 1 Docket No. 50-338 Report No. LER 80-109/03L-0 Description of Event On December 30, 1980, it was discovered that the reactor trip from Low-Low Steam Generator Level was at 15% narrow range span rather than 18% as required by T.S. 3.2.2.1.

Probable Consequences of Occurrence Because of this administrative error, the setpoint change was not implemented for approximately 5 months af ter the Technical Specification Change (#13) was implemented. The reactor trip, during this time, would have occurred at 15% steam generator level rather than at 18%. Since the reactor trip from a Low-Low steam generator level was originally established at 15%, and the setpoint change to 18% represents a refinement in the model for a high energy line break within the containment, the effect on the health and safety of the public are negligible.

Cause of Event This event was caused by all administrative error. The instrument maintenance personnel are not on the distribution list for Technical Specification Changes. Therefore, the implementation of the chenge was not performed. The change became effective on August 5, 1980 wite change #13 to the North Anna Unit 1 Technical Specification.

Immediate Corrective Action Since the unit was in mode 5, no immediate corrective action was required.

Scheduled Corrective Action Prior to entering mode 4, the periodic calibration procedure will be revised and the channel Low-Low Level comparator will be recalibrated to the new setpoint.

Actions Taken to Prevent Recurrence The routing list for proposed and approved Technical Specification changes will be reviewed and the Instrument Maintenance shop added as a revision.

Generic Implications There are no generic implications of this event.

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