ML19350C770

LER 81-028/03L-0:on 810302,daily Periodic Test Procedure Which Calibrs Nuclear Power Range Channels Not Performed within Required Interval.Caused by Unstable Plant Conditions During Surveillance Interval

ML19350C770
Person / Time
Site:	North Anna
Issue date:	04/01/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19350C761	List: ML19350C760 ML19350C770
References
LER-81-028-03L-02, LER-81-28-3L-2, NUDOCS 8104060678
Download: ML19350C770 (2)

Text

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3  : U.S. NUCLEAR REGULATORY CO.T!ISSION j LICENSEE EVEhT REPORT l C0hTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE ALL REQUIRED IhTORMATION)

Oe>< eve ^/se^es/2/ <2) /oeoe-tozoeolozo/-<oeo/ <>) e4/te><><>< (4) / / / <s)

LICENSEE CODE LICENSE NUMBER LICENSE IYPE CAT E g/ (6) /0/5/0/0/0/3/3/9/ (7) /0/3/0/2/8/1/ (8) /c /4 /c /i /a /_t/ (9)

DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND DROBABLE CONSEQUENCES (10)

/0/2/

/ On March 2, 1981, during Mode 1 operation, the daily periodic test procedure /

/0/3/ / which calibrates the Nuclear Power Range Channels against a heat balance /

/0/4/ / standard (2-PT-24) was not performed within its required surveillance /

/0/5/ ./ interval. Because performance of the calorinetric was late by only 3 aours /

/0/6/- , and 43 minutes and results shcwed reactor heat output to be well below the /

/0/f,f / core design limit of 2775 MWth, the health and safety of the general public /

/0/8/ / were not affected. This event is report able pursuant to T.S. 6.9.1.9.b. /

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUB00DE SUBCODE

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

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

(17) REPORT NUMBER /8/1/ /-/ /0/2/8/ g/ /0/3/ /L/ /-/ /0/

ACTION ' FLTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMP 0hTh7 <

TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER ,

. /E/ (18) g/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) g/ (23) /_N/ (24) M/ (25) /W/1/2/0/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/ / 2-PT-24 was not performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> +25% of the last calibration because /

/1/1/ / power transients necessitated by decreasing condenser vacuum during locating /

/1/2/ / and repair of a tube leak resulted in unstable plant conditions throughout the /

/1/3/ / required surveillance interval. The calorimetric was performed when plant /

/1/4/ / conditions permitted and the Nuclear Instrumemtation was adjusted as required. /

FACILITY METHOD OF STATUS  % POWER OTHER STATUS C M RY DISCOERY DESCR M M (32)

/1/5/ g/ (28) /0/8/7/ (29) / NA / (30) /B/ (31) / OPERATOR OBSERVATION /

ACTIVITY CONTEhT-RELEASED OF RELEASE . AMOUNT OF ACTIVITY (35) LOCATION OF RELEASE (36)

/1/6/ /2/ (33) /Z/ (34) / NA / / NA /

PERSONNEL EXPOSURES.

NUMBER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (37) /Z/ (38) / NA /-

PERSONNEL INJURIES 51HBER DESCRIPTION (41)-

/1/8/ /0/0/0/-(40) /

NA /

p LOSS TYPE OF -DESCRIPTION OR DAMAGE TO FACILITY (43) d/9/ /Z/ (42) / NA /

PUBLICITY ISSUED DESCRIPTION (45) NRC USE ONLY

/2/0/' '/N/ (44) / NA /__/ / / / / / / / / / / /

NAME OF PREPARER W. R. CARTVRIGHT PHONE (703) 894-5151 D04060[78 _. - - ._

() Virginia Electric and Power Company North Anna Power Station, Unit #2

Attachment:

Page 1 of 1 Docket No. 50-339 Report No. LER 81-028/03L-0 Description of Event On March 2, 1981, during Mode 1 operation, the periodic test to daily calibrate the Nuclear Power Range Channels against a heat balance standard as required by T.S. 4.3.1.1.1 was not performed within its required surveillance interval. This event is reportable pursuant to T.S. 6.9.1.9.b.

Probable Consequences of Occurrence The consequences of this event were limited by the fact that 2-PT-24

, was performed that evening only 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 43 minutes later than required i

and the results showed reactor heat output as being only 2470 MW which is,well below the core design limit of 2775 MW at 100% power. tNs a result, the health and safety of the general public werethnot affected.

Cause of Event The daily calibration of.the Nuclear' Instrumentation Channels was not performed within the required 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> +25% surveillance interval because power reductions necessitated by decreasing condenser vacuum during inspection and repair of a condenser tube rupture resulted in unstable plant conditions

.(- ,

, during tne period required for the test to be run.

Immediate Corrective Action The calorimetric required by 2-PT-24 was performed as soon as plant

, conditions permitted and the Nuclear Power Range Channels were adjusted

, accordingly.

Scheduled Corre etive Action No scheduled corrective action is required.

Actions T ken to Prevent Recurrence No further actions are required. .

E Generic Implications There are no generic implications associated with this event.

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