05000338/LER-1980-017-01, /01T-0:on 800121,during Startup Physics Testing, F Values Exceeded Design Value Tolerance at hot-zero-power w/D-bank Inserted & Banks C & D at Insertion Limits.Caused by Presence of Quadrant Power Tilt.Safety Evaluation Done

/01T-0:on 800121,during Startup Physics Testing, F Values Exceeded Design Value Tolerance at hot-zero-power w/D-bank Inserted & Banks C & D at Insertion Limits.Caused by Presence of Quadrant Power Tilt.Safety Evaluation Done

ML19260D010
Person / Time
Site:	North Anna
Issue date:	02/04/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19260D007	List: 05000338/LER-1980-017, Forwards LER 80-017/01T-0 05000338/LER-1980-017-01, /01T-0:on 800121,during Startup Physics Testing, F Values Exceeded Design Value Tolerance at hot-zero-power w/D-bank Inserted & Banks C & D at Insertion Limits.Caused by Presence of Quadrant Power Tilt.Safety Evaluation Done
References
LER-80-017-01T, LER-80-17-1T, NUDOCS 8002070236
Download: ML19260D010 (2)

LER-1980-017, /01T-0:on 800121,during Startup Physics Testing, F Values Exceeded Design Value Tolerance at hot-zero-power w/D-bank Inserted & Banks C & D at Insertion Limits.Caused by Presence of Quadrant Power Tilt.Safety Evaluation Done

Event date:
Report date:
3381980017R01 - NRC Website

text

NHC FOHM 36G 11 {7)

LICENSEE EVENT REPORT 3

/

I I CON!HOL fiLCC6 l

l l

l l

(PLE ASE PHINT OR TYPE ALL REQUlHED INFORMATION) 1 1l1l1l@l l

l@

0l 0l@{ L

'l l A l '; j A l S l 1 l@ O l 0 l - l 0 nj P

O O

j o

i 1

r 9

LICt N3E E t O v 14 15 L li r N :, t '

J$t" r

l' ' 2E Tid JJ Si tA bd C0%'T R j@l n l I l 2 l 1 l ? l n l@l n l ' l 0 l A l q i o@

E1

"[)[r[ llhl 4 5l 0 0[ 0l 3l 3 EVE.NT DEschlPTION A DPRO9A C

E P.C E 5 lDurine the Startup Pkvsics Testino Pr o-n for North Anna r it 1.

rvete 2.

I o

2 l tha neasured values for F(delta F) e xceer'od the desien value t ol e rance at l

o 3

l hot-ze ro-powr with D-hank inserted, and uith Banks C and D at the insertion I

o a

l o l' ]

limits.

Th sod on these reasure eat results, it has been de terr,ined that the l

Lo 6

I cont rol rod insertion linits riven in T.S.

Ficu re 3.1-1 are no loneer annro-I o

/

inriate for l'ni t 1, Cycle 2 operation. We hoal th and sa fe ts of the reneral l

lpublic were not af fecte 8 Bis event is renortable nursuant to T.S.6,0.1.8.1.

o s

O

/

R 3 S Y S T E '.1

CAUSE

CAUi!

COYP VALV E CODE COD SU9 CODE COYENENT CODE SJ8 CODE SU3 CODE InlC @ lx @ l zl@ I z l z i 71 z i z i z l@ l zi@ L zJ @

o 9

7 8

9 10 11 12 12 13 IJ 2d Ct OVEN TI AL OLC.-E".U HEFORT HE;G ON (E g so EVENTVFAH O E POR T NO.

CC3E TNPE

'O

@ Olg; s1 01 1-1 Iol1171 1/1 10111 1 Tl 1-l I ol

_ 21 L.

23 24 20 l3 29 3d 31 32 AC TION FUTLHE EFFFCT W.; T E..,.

A TT AC w Y E N T NP-J 4 PA.W COYP.

COYPONENT TasEN ACTION ON PLn.T

- T90D H9243 SLaYiTTED F OP 3y B.

SUPPLtEa t' A *. ;- AC TU R ~ H I xl@l XI@

I z l@

lZ@

Iofo of I

I Y l@

LEJ@

I"l@

i z l o 19 la l@

33 34 h

Jn J.

4C 41 42 43 44 47 C AUSE DESCHIPTION AND COHR ECTIVE ACTIONS l The cause of the hich F(delta P) value is the nresenco of a nuadrant nouor tilt I

i o

j t ide n t i fied through incore fl'ix nap analvses and believeri to be tbo result r

n i

i l non-s ynne t r ic isotopic distr:bution in the fuel caused hv the Cycle 1 quadrant l

3 7

g g l power tilt. A sa fety evaluation has been pe r f o rr'ed t, 'ustifv oover eneration l

l with revised control rod insertion limits.

[

i 4

/

8 9 80 F ACIL! TY YETHOD OF S T A l'J>

.POAER OTHER STA TUS DISCOVERY D'SCOVERV OESCRIPTION a2 lT l<ll }l @ l Dj 0] 3]@l Physics Testing lCl@l Following Physics Testing l

7 H

9 13 12 11 44 45 46 80 A.TIVITY CO N T E P.T J

HE L E te E D OF HE LE a5E AYOUNT OF ACTIVITY LOCATION OF RELEASE -

1 6

z NA l

A l

1 H

')

10 11 44 43 80 rEas,.,EtFxp>;suaEs Hra TYPE DEKRIPTf0N D l 0 l o l Oj@l zl@l

=

l i

i 7

8 1

11 12 13 80 1937 310

1. a c.P. '. E t.

'. j b 3 ' E S l0l010 gj u

l i

/

H 1 11 12 gg tG,

'G i i > A v ) T ri F A ~ t L l T V

"^

80E207n 2Kl

.... r * > P T t )

L3@

o m

u

% Yf>TIa s s

l,_j; 12 1o1 1 :1 6 1 u

I Ill

!!Illilll.

H m

m s s.,

O h

N A *.' E 0 0 PDEPAREH i^*

P-ONE

/~'75

?"

~' '

Virginia Elect ric and Powe r Corpany Attachnent: Page 1 of 1 North Anna Power Station, Unit 1 Docket No. 50-333 Peport No. II.R/R0 80-017/0 lT-0 Desc ript ion of Fven t Du r ing the Startup Physics Testing Progran for " orth Anna Unit i, Cycle 2, the re a su rec' values for F6telta H) exceeded th" desien value tolerance at hot-zero-powe r wi th D-bank inse r ted, and a t 37 pouer with Banks C and D a t th" insert ion limits.

These neasurenents provide a basis for de te rnining that the es:ist ing control rod insertion lini t s given in Technical Specification Figuro 3.1-1 are no longer appropriate for Unit 1, Cycle 2 opera tion.

This event is reportable pursuant to T.S.

6.0.1.8.i.

Probable Consequences of Event The reasured va lues for F(delta H) do not constitute a viola t ion of Technical Specification limits since power was naintained at lecs than 57 of rated the rnal powe r.

'Ih e heal th and sa fe ty of the genera! public were not af fected by this event.

Cause

The cause of the high F(delta H) values is the presence of a quad rant powe r tilt which was identified through incore flux cap analyses.

It is believed that the quad ran t power tilt is being caused by a non-synne tric isotopic dist ribut ion within the irradiated fuel as a result of the quadrant powe r t L i t that uas present during Cycle 1 operation.

Innediate Corrective Action Prior to increaalng reac tor powe r above 57 of rated thernal powe r, a sa fe ty evaluation was perforned to justify power operation uith revised contrel rod inse r t ion 1inits.

A flux nap was taken at approxima tely 3? powe r uith cont rol bank D at its revised insertion linit, and the reasured value for F(delta H) wa s ve ri f ied to be acceptable.

After obtaining PRC concurrence fo r powe r operation in conpliance with the revised insertion limit, which was imple-reni ed adninistratively, reactor power was increased to 307.

k'ith D hank near its revised insertion limit at 30% power, flux nap results again provided an acceptable reasured value for F(delta H).

Scheduled Corrective Action The revised insertion limits along with the supporting safety evaluation vill be subnitted to the NPC as a Proposed Tec.hnical Specification Change for Unit 1, Cycle 2 operation.

An investigation is unde r uay *o de te rnine the prinary cause of the power tilt.

Actione Taken to Prevent Recurrence Once she primary cause of the power tilt has been de terrined, a plan will be developed and inplemented that util either elin'nate the primary cause for the pow r tilt, or acconedate i ts e f fec t s.

1937 31I