ML20084S524

RO 50-254/76-27:on 760806,ECCS Analysis Performed by GE for BWR-3 Type Plant Resulted in Calculated Peak Clad Temp Greater than 2,200 F for Reduced Core Flows.Caused by Severity of Conservatisms Associated W/Using App K

ML20084S524
Person / Time
Site:	Quad Cities
Issue date:	08/19/1976
From:	Kalivianakis N, Spedl G COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NJK-76-313, RO-50-254-76-27, NUDOCS 8306170087
Download: ML20084S524 (2)

Text

lth Edison Quad-Citt.s Nucl*ar Power Station h '

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- - Cordova. Illinois 61242 Telephone 309/654 2241 IE FILE COPY NJK-76-313 A

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August 19, 1976 i O O2 Jhh,Q4 -

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J. Keppler, Regional Director 9 p.p'\

Office of Inspection and Enforcement -

Region lil U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Reference:

Quad-Cities Nuclear Power Station Docket No. 50-254, DPR-29, Unit I Docket No. 50-265, DPR-30, Unit 2 Appendix A, Section 6.6.8.1.h.

Enclosed please find Reportable Occurrence Report No. 50-254/76-27 for quad-Cities Nuclear Power Station. This occurrence was previously reported to Region ill, Office of Inspection and Enforcement by telephone on August 6, 1976 and by telecopy on August 6, 1976.

This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.I.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION i,< , ,

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N. J. Kalivianakis ,,/

Station Superintendent COPY SENT REGION- w NJK/GS/tv cc: G. A. Abrell

$?333 8306170087 760819 PDR ADOCK 05000254 S PDR AUG 2 3 1976

OCENSEE EVENT REPORT N CONTAOL BLOCK;l l l l l l l (PLEASE PRINT ALL REQUIRED'dNFfRM AT'ON) 1 6 NAME LCENSE NUMBER E PE 01 lllLlQlAlDl1l14 l 0 l 0 l-l0 l 0 l 0 l 0 l 0 l-l 0 l0 l 25 l4 l1 l0 l0 l030 l , l0l1l 32 7 89 15 28 31 CATEGCRY SO OOCKET NUMBER EVENT OATE REPORT OATE 01 CONT l l l (_j lLl l0 l 5101-l 01215 l 4 l l018 l 0 l6 l7161 l O l 811 l 9 l 7 l 6l l 7 8 57 58 59 60 61 68 69 74 75 80 l EVENT DESCRIPTION DE l An ECCS analysis performed by General Electric for a BWR-3 Type plant resulted in a l 7 89 80 Eg l calculated peak clad temperature greater than 22000F for reduced core flows. This l 7 89 80

@ l analysis requires additional margin to current maximum average planar linear heat l 7 89 80 Q l generation rate limits to preclude operation in the area where the peak clad tempera- l 7 89 80 HE lture could exceed 2200 0F (R0 50-254/76-27). l E CODE COMPONENT CODE A votATON BE l Z I Z l W l Z l Z l 2 l Zl Zl Zl lZl lZl9l9l9l lN l 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION .

HE l The apparent cause of this occurrence is the severity of conservatisms associated l 7 8 9with using the approved Appendix K ECC5 evaluation model at less than rated core 80 HE Iflows. As an Interim corrective action taken until review of this generic concern l 7 89 resolution obtained, quad-Gities has 80 EU lwith the NRC Imoosed a 5% may be accomplished reduction in maximum and a final average olanar IInear heat generation rate limits l STA 3  % POWEN OTHER STATUS DISCOVERY OiSCOVERY DESCRIPTON 1 @_j l 0l 3l 0l l NA l W l NA l 7 8 9 10 12 13 44 45 48 80 ACTMTV CONTENT AELEASEO OF AELEASE AMOUNT OF ACTMTV LOCATON OF AELEASE 35 7 8 9 0 Ol 10 11 NA l

44 l

45 NA 80 l

PEASONNEL EXPOSURES NUMBER TY PE DESCAIPTON 3E l 0l 0l 0l [ZJ l NA l

7 89 11 12 13 eO PEASONNEL INJURIES NUMBER DESCRIPTON i DE l 0l0 l 0 l l NA l 7 89 11 12 80 OFFSITE CONSEQUENCES 39 l NA

[.

7 89 80 LOSS OA OAMAGE*TC FACIUTY TYPE DESCRIPTON NA 3] ]

7 89 l

10 l

80 PUBLICITY 1

l NA l

7 89 80 ADOITIONAL FACTOAS (Cause Description cont.)

QE l for core ficws less than 85% of rated. Quad-Cities has always typically maintained j 7 89 80 a 15% margin to these limits, so this occurrence is not expected to pose any

@ l operational problems. l NAME:

Gary Spedl

• PHONE:

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