ML19257B282

LER 79-092/03L-0:on 791214,following Reactor Circulation Pump Trip,Fuel Bundles Exceeded Linear Heat Generation Rate Limits.Caused by Nodal Xenon Burnout & Unavailability of One Transient in-core Probe.Power Increases Halted

ML19257B282
Person / Time
Site:	Brunswick
Issue date:	01/09/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19257B280	List: ML19257B279 ML19257B282
References
LER-79-092-03L-01, LER-79-92-3L-1, NUDOCS 8001150476
Download: ML19257B282 (2)

Text

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LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

@ l 8N9 l C LICENSEE lBlE l P l 2 l@l 0 l0 l- l 0LICENSk le 15 l0 l0 l0 l0 l- l0 l0 l@l26 4l LICENSE NUYULH 2'J 1l 1l 1l Tire1l@l JO SI l l@

(. A f $d 7 COreE CON'T o 1 [,] l L J@l 0 l 5 l 0 l - l 0 l 3 l 2 l 468@l631 l 2EVE 11NT l4 DATE l 7 l'9 @ 0 11REPORT 14 7$

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DATE 7 8 60 6' OOCK ET NUMB ER EVENT DESCRIPTION AND FROBABLE CONSEQUENCES h o 2 At approximately 3% below the LHGR limit on a power increase following a reactor o a l recirculation pump trip (LER 2-79-88), an OD-1 was performed. Upon completion of l the OD-1, fuel bundles 9-26 and 43-28 exceeded the LHGR limit of 13.4 kw/ft. The j lo i4 l l lo Isl i maximum LHGR for these bundles was 13.58 kv/ft. l 10161I I

10171 1 o a Technical Specifications 3.2.4, 6.9.1.9b 80 l

7 8 9 COMP- VALVE SYSTEM CAUSE CAUSE CODE CODE SUSCODE COMPONENT CODE SUSCODE SUSCODE o 9 9

I Rl B lh l Alh to 11 32 X lh lZ lZ lZ lZ lZ l Zlh l Z l@ W @

PJ 18 19 20 7 8 REVISION SEOUENTI AL OCCURRENCE REPORT REPORT NO. CODE TYPE NO.

LE R RO EVENT YE AR h aga; l 7l 9) [--J l 0l 9 21 l/l l 0l 3 l (,,L,, ] l-l l0l 22 23 24 26 27 2B 79 30 _ 31 J2

_ 21 HOURS S8 IT FORL B. SUPPt lE MANUFA TURER AKEN AC C ON PLANT tETM lXl@[,H_j@ 34 l35B l@ lZ 36 l@ l0l0lOl2l 31 40 *

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43 44 47 3J CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l Power was immediately reduced to place LHGR in specifications. The cause for l i o l

exceeding the LHGR was approaching the limit with one TIP not available and a lt Ii1 l

[7 py] l nodal Xenon burnout. To prevent this occurrence in the future, power increases will be halted at 5% below the LHGR limit and an OD-1 performed. Further increases [

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80 Dis O RY DISCOVERY DESCRIPTION 4 POWER OTHER STATUS STA S Engineer Surveillance l y lEj@ ' '

lOl9l7l@l " N/A l lAl@l ACTivt TY COTTENT LOCATION OF RELEASE RELE ASEO 05 pELE ASE i 6 W @ W@l AMOUNTOF N/A 44 ACTiv.TY l

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7 8 9 10 ft PERSONNEL E MPOSURES NUMBE R TYPE DESCRIPTION j NA .

1 7 l 010 l0 l@l Z l@l PERSONNEL NJURIES NuveER oESCRiPrioNh l N/A W l 809 l 0 l 0 }@l 12 f 80 7

11 7 7 LOSS OF On OAVAGE TO 8ACILITY TYPE DESCRIPTION N/A

/ J 800115 &l 9

8 9 W @l10 NRC USE ONLY 80 7

• PUB L ICITY N/A l lllllllllIIlI*g.

] ISSUED g g y @l DESCRIPTION to 68 69 80. .

7 o W son, Jr. 919 457 9521 E,

. . PHONE:

NAME OF PREPARER f

LER CONTINUATION -- RO# 2-79-92 Facility: BSEP Unit No. 2 Event Date: 12-14-79 will be monitored with OD-l's and OD-2's. All nuclear engineers will review this LER.

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