ML20040B570

LER 81-033/01T-0:on 811228,error in Tech Spec Heatup & Cooldown Curves Found to Be Not Reported to Nrc.Caused by Administrative Reporting Failure & Errors in Calculation. Info Will Be Reported as Tech Spec Change by 820131

ML20040B570
Person / Time
Site:	Robinson
Issue date:	01/11/1982
From:	Gilman F CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20040B559	List: ML20040B558 ML20040B570
References
LER-81-033-01T, LER-81-33-1T, NUDOCS 8201260200
Download: ML20040B570 (2)

Text

NRC FORM D6 U.S. NurLEAR REGULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT CONT'HOL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 lo W8 9ls lCLICENSEE ln In CODE lR 12 l@l0 l0 l- l0 loLICENSE 14 l0 l0NUMBEHl0 l- l 010 l@l 25 4 26l 1 lLICENSE 1 l 1TYPE l 1JOl@l$1 CAT l 58 Ig i lb CON"T IOI1l $n] lL60@ l061l5 l0 l0DOCKE l0 Tl2NUMBER l6 l1 @l tal1 l 632 l 2 EVENT l 8 lDATE8 l 1 l@l 0 l 1 lREPORT F4 15 1 l 1DATE l 8 l 280l@

i 8 EVENT DESCRIPTION AND PRO 8ABLE CONSEQUENCES h j o l 2 l lOn December 28, 1981, it wa s de termined tha t an error in the Technical Specification l o 3 lhea tup and cooldown curves which had not been reported to the NRC was reportable l

[ o [ 4 l l pursuant to Technical Specifica tion 6.9.2.a.9. This error was made in 197 7 and , due tol l o (3_j jan administrative error, wa s not reported to the NRC. While this error does result in l j o ls l la non-conserva tive shift in the curves near their end of applicability (20 EFPY of l l o l 7 ] [ vessel exposure), the error does not represent non-conserva tive opera tion for the l current exposure (7.4 EFPY); therefore the re is no threa t to public health and I o Ia I lsafe ty from this event. l 7 8 9 80 SYSTE M CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CoOE SUSGoDE SUBCODE 7

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i j o l lThe hea tup and cooldown curves were in error due to calculational mistakes and were notl i i l revised due to an adminis tra tive error. 'Ih e correc ted curves and ca lcula tions will be l

[,l,i l submitted to the NRC as a Technical Specifica tion change by January 31, 1982. The l l , l 3 l l administrative error is considered a unique and isola ted event. A similar event l should be precluded by changes made to our administrative practices since 19 7 7, changes i lil4l lwhich have increased our awareness of the sta tus of projects being coordina ted. l )

? 8 9 80 i S  % POWE R OTH E R ST A TUS ISCO HY DISCOVERY DESCHiPTION t 5 L Ejh l 0l 8 l 0 l@l NA l W @l Review of Reactor Vessel History l .

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SUPPLEMENTAL INFORMATION FOR j LICENSEE EVENT REPORT 81-27

1. Cause Description and Analysis

On December 28, 1981, it was determined that an error in the Technical j Specification heatup and cooldown curves was reportable pursuant to l Technical Specifica tion 6.9.2.a.9.

l A recent review of informa tion rela ted to the Reactor Vessel Ma terial l Surveillance Program for H. B. Robinson Unit No. 2 revealed a

! calculational error in analyses used to update heatup and cooldown i curves pursuant to Specifica tion 3.1.2.4. This informa tion wa s i reported to Carolina Power and Light Company in April,1977, by the

) contractor who performed the analyses. Howeve r , through an administrative error, the revised informa tion was never reported nor i incorporated in Technical Specifications as required by Specification 3.1.2.4.a and b.

The error results in a slight shift (5*F) to the l right in Technical Specification figures 3.1-1 and 3.1-2. The current i

figures therefore could have resulted in operation above the revised curves as plant lifetime approached 20 ef fective full power years (EFPY), the period for which the figures are applicable. Ibwever, it has been verified tha t due to the current accumulated exposure l

j (approxima tely 7.4 EFPY) the curves now existing in Technical Specifications remain very conservative. There fo re , this event does

! not constitute a threat to public health and safety, i

2. Co rrec t ive Ac t ion I A verification was made to insure tha t the existing curves, although

slightly in error, would not result in non-conserva tive opera tion.

A Technical Specification change containing the revised curves and revised reactor vessel ma terial surveillance cilculations will be I submitted by Janua ry 31, 1982, to the NRC. The Technical Specification revision will be implemented upon issuance by the NRC.

3. Corrective Action to Prevent Recurrence This event occurred several years ago and is believed the result of a unique set of circumstances rela ted to re-assignment of responsibility for coordination of this project of fsite. It is therefore considered to be an isola ted event. In addition, since 1977, changes have been i ma de to administrative practices rega rding of fsite coordina ted projects and an increased awareness of the status of these activities has ,

resulted. Accordingly, no further corrective actions are considered necessary.

i I

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