ML20055E941

From kanterella
Jump to navigation Jump to search

Summary of 900621 Meeting W/Util Re Proposed Mods for Return to 100% Power.List of Attendees & Viewgraphs Encl
ML20055E941
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/09/1990
From: Alexion T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-74894, NUDOCS 9007130100
Download: ML20055E941 (29)


Text

-

M( $

+

' '4 .

UNITED STATES e _q. NUCLEAR REGULATORY COMMISSION M  !

, T.  ! WASHINGTON, D. C. 20666 s b

%, '...o / auly 9, 1990 Docket No. E0-313 LICENSEE: ENTERGY OPERATIONS. INC.

FACILITY: ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1)'

SUBJECT:

MEETING

SUMMARY

- PROPOSED MODIFICATIONS FOR RETURN TO 100% POWER i (TAC 74894) L On June 21, 1990, the licensee presented to the NRC staff proposed modifications for return to 100% power. Meeting participants are listed in Enc h rJre 1. Slides presented by the licensee are shown in Enclosure 2.

Ah0-1 is currently % ised to 801 power due to a license limit based on their latest Appendix K lut of-coolant accident (LOCA) analysis (a high pressure inje: tion (HPI) lira break scenario). The licensee is also currently using the 80% power limit to provide short-term resolution of a reactor building spray (RBS) pumps net positive suction head (NPSH) issue.

The licensee presented a background and design basis discussion of,the HPI line break and NPSH issues, a description of.the modifications planned, an overview of the operator actions required, and the current status and schedule. .The modifications, all of which are outside containment, include 4 new cross-connect lines with 8 new valves that tap off the existing HPI trains upstream of the splits which eventually inject into the reactor coolant pump loops (the current arrangement is 2 cross-connect lines located downstream of thesplits). The modifications will require no additional operator action to address the HPI line break issue, but it will require the operator to limit HPI flow under certain conditions to address the NPSH issue. The modifications are planned to be installed during the next refueling outage 3 i (October to December 1990), and the supporting license amendment fcr 100% power 1s scheduled for. submittal in August 1990. The licensee also mentioned that they).mightbesubmittingrequestsforrelieffromcertaininservicetesting (IST requirements regarding the 8 new valves in a separate letter.

i'

-The staff inquired about the option to install cavitating venturis, which was unsuccessfully attempted last year. The licensee abandoned this option because the magnitude of the vibrations experienced was not predictable with available theory. The staff also inquired about the class of piping that will be used (Class 2),thespecificISTrequirementsfromwhichreliefmayberequested (possibly the test interval), and some details regarding the operator action needed to address the NPSH issue.

0 9007130100 900709 'O

  1. k PDR ADOCK 05000313 'd P PDC

$ ~j

_ f ig:

4 n .2- ,

p s

The staff did not' identify any major concens with the modifications or review schedule proposed by the: licensee. _The staff did; request that the application.

include a description of the post-modification testing to be performed prior-L to start-up from.the refueling-outage.

Original signed by .

Thomas W. Alexion, Project Manager-Project Directorate IV-l'-  ;

Division of Reactor Projects . Ill, IV, Y and Special Projects

Enclosures:

i As stated ~ l cc w/ enclosures:

. See next'page l I

DISTRIBUTION-

.N' NRC & Local PDRs FMiraglia 1 JPartlo*:

PD4-1 Reading RDudley

.TAlexion' OGC

.EJordan.'

NRC Participants

,Y ,ACRS(10) .

JCaldwell,RI~

L RBorchardt RII h JClifford,RIII MSlosson,RIV&V g-D' '

0FC :PDIV. - *P (A)D :  :  :  :  :

p.....:.. . .. .:. ...:............:............:............:..........._:....__.__

!_NAME : Alp .c :R ley -  :  :  :  :  :

DATE;:i...........:]..[.........:............:_...........:............:............:.........

/7490' ': .

/90!  :'  :  :  :  :

il

.0FFICIAbRECORD-COPY-Docunient Name
' ' AN0174894 -

l i

a(

i

. s j s "*$

g. ..

a y i i.

, 5

The staff'did not identify any major ~ concerns with the modifications or review [

schedule proposed by the licensee. The staff did request that the application-include a-description of the post-modification testing to be performed prior to start-up from the refueling outage.  :

( s  !

J .

Thomas W. Alexion, Project anager Project Directorate IV-1 Division of. Reactor Projects - 111

-IV, V and Special Projects

Enclosures:

As stated '

cc w/ enclosures:

See next page t

9

.'~ -

L ,

j '

1:e L

kk E

l fh' 1

i

? .

Mr. Neil S. Carns  ;

j ,Entergy Operations, Inc. Arkansas Nuclear One, Unit 1 '

CC: -

Mr. Early Ewing, General Manager Mr. Donald C. Hintz '

Technical Support and Assessment Executive Vice President Arkansas Nuclear One Entergy Operations, Inc.

P. O. Box 608 P. O. Box 31995 '

Russellville, Arkansas 72801 Jackson, Mississippi 39286 Mr. Jerry Yelverton. Mr. Gerald Muench  ;

Director Nuclear Operations Vice President Operations Support '

Arkansas Nuclear One - Entergy Operations, Inc. l Route 3 Box 137G P. O. Box 31995

-Russellville, Arkansas 72801 Jackson, Mississippi 39286 '

Mr. Nicholas S. Reynolds Mr. Robert B. McGehee, Esquire Bishop, Cook, Purcell & Reynolds Wise, Carter, Child & Caraway 1400 L Street, N.W. P. O. Box 651 Washington, D.C. 20005-3502 Jackson, Mississippi 39205 1

Mr. Robert B. Dorsum

- Babcock & Wilcox l

Nuclear Power Generation Division 1700 Rockville Pike,-Suite 525

- Rockville, Maryland 20852

i. Senior Resident Inspector i L U.S. Nuclear Regulatory Comission 1 Nuclear Plant Road . i Russellville, Arkansas 72801 -

l 1

-Regional Administrator, Region IV i U.S. Nuclear Regulatory Commission l l Office of Executive Director for Operations h 611 Ryan Plaza Drive, Suite 1000 1 Arlington, Texas 76011- I l

l' Honorable Joe W. Phillips 1 County Judge of Pope County i p Pope County Courthouse

l. Russellville, Arkansas 72203 L

j Ms. Greta Dicus, Director i Div.ision of Environmental Health l Protection l Arkansas Department of Health j 4815 West Markam Street l Little Rock, Arkansas 72201 l

I l

j

= n y c .: . . ENCLOSVRE 1=  ;

5.1 '

ARKANSAS NUCLEAR ONE, UNIT 1 PROPOSED MODIFICATIONS FOR RETURN TO 100*/ POWER JUNE 21. 1990 NAME ORGANIZATION-Thomas Alexion NRC/PD IV-1 Chester Poslusny NRC/PD IV-1 Dale James Entergy/ Licensing

  • Bill Eaton Entergy/MCS Design James 1Fisicaro Entergy/ Licensing George Jones Entergy/ Engineering Ed Jacks Entergy/Nuc.' Stand.

John Richardson Entergy/ Design Eng.

George Woerner III Entergy/MCS Design Darrell Williams Entergy/Nuc. Eng.

Kenneth Dempsey NRC/EMEB Vincent: Thomas NRC/SICB Jesse Arildsen NRC/LHFB Linh Tran NRC/PD IV-1 John Miller, Jr. Entergy/Nuc. Eng.

Randy Ellison BWNS James Pulsipher NRC/EbLB Walton Jensen .NRC/OEAB Richard Dudley NRC/PD IV-1 Mark Caruso NRC/SRXB Thomas Stetka NRC/ Region IV David Terao- NRC/EMEB Thomas Westerman

  • NRC/ Region IV Clay Warren
  • NRC/ Region IV:

1 l

l; l.

  • - tied-in via speaker phone

(:

L L

f .

l [* . * : . . -ENCLOSURE 2 e

r ANO-1 r

x l RETURN TO II 100% POWER 1

. le MODIFICATIONS .

1c .

  • S" J T '

= . = -

y.g y %y r.

  • ^

}y g ge d w agi[ G ..

[ 4 b%$ %o : a 1= com m ,

~

2:= _.

l = i 10  ; .D ,

a -

{L i_ -. _ =._.a :t M[ L _ _ . _ _

n Tb,- e I. "gl ' (c

'M A 1

=- 4 n

[

[? June 21 1990 I

I i;

+ a

~ ENTERGY OPERATIONS

s ,,

ANO-1 RETURN TO 100% POWER MODIFICATIONS 4

. INTRODUCTION

- B'ACKGROUND OF ISSUES

-- HIGH PRESSURE INJECTION (HPI) LINE BREAK SCENARIO LOW PRESSURE INJECTION (LPI) AND i REACTOR BUILDING SPRAY (RBS) PUMPS l NET POSITIVE SUCTION HEAD (NPSH) i L . EMERGENCY CORE COOLING SYSTEM (ECCS) & RBS DESIGN BASIS i OVERVIEW r  !- 1R9 MODIFICATIONS SCOPE '

d I'

- HPI LINE BREAK RESOLUTION - VALVES /

INSTRUMENTATION

- NPSH RESOLUTION - INSTRUMENTATION i

REQUIRED OPERATOR ACTION OVERVIEW l'.

.HPI LINE BREAK - IMMEDIATE ACTION RBS AND LPI ACTIONS

.i-

- LONG TERM RECOVERY SCENARIOS

- CURRENT STATUS & SCHEDULES

- MODIFICATIONS

- LICENSE AMENDMENT REQUEST

- CONCLUDING REMARKS

' O y e :=L,

' '; r4> .,

4-

, s 1

14-i l

1 i

t l

I INTRODUCTlON i

I

];.

i-1 l

I

.t w M v n-~' ENTERGY OPERATIONS

.g ,

1 HPl BACKGROUND

. JANUARY 1989 REVIEW OF ECCS ANALYSIS REVEALED SPECIFIC SMALL .

BREAK NOT ENVELOPED BY . ANALYSIS BREAK OF AN HPI INJECTION LINE UPSTREAM OF THE COLD LEG CONNECTION AND l DOWNSTREAM OF THE FIRST RCS/HPi .;

SYSTEM BOUNDARY CHECK VALVE l

i - MARCH 1989 LICENSE AMENDMENT l SUBMITTED AND ISSUED LIMITING l

. POWER OPERATION TO 50%

l 11 . APRIL & MAY 1989 SUPPLEMENTuL INFORMATION PROVIDED JUSTIFYING  :

7 i 80% POWER OPERATION

. o

l. MAY 1989 AMENDMENT ISSUED ALLOW '

l I

80% POWER' OPERATION

. DECEMBER 1989 CAVITATING VENTURI ADDED DURING 1M89 TO ADDRESS HPI LINE BREAK SCENARIO

! -- VENTURI REMOVED FOLLOWING POST i MODIFICATION TESTING WHICH SHOWED l EXCESSIVE VIBRATION l ,

~

ENTERGY OPERATIONS

t .x . -

it li RBS/LPI NPSH BACKGROUND

. DECEMBER 1989 DESIGN CONFIGURATION DOCUMENTATION (DCD) PROJECT REVIEW OF ANO-1 DECAY HEAT REMOVAL SYSTEM IDENTIFIED CALCULATIONS ERRORS AND INCONSISTENCIES.

-- CONTAINMENT WATER LEVEL BWST AVAILABLE VOLUME WATER DENSITY i -- AVAILABILITY OF TRAPPED WATER

j. --

OTHERS

- COLLECTIVELY MAY HAVE RESULTED i

IN CAVITATION IN THE- LPI & RBS '

PUMPS.

- EOP GUIDANCE RF, VISED TO THROTTLE

! PUMP DISCHARGE TO ASSURE THE NPSH REQUIREMENTS COULD BE SATISFIED.

I l-I l

ENTERGY

~~ OPERATIONS

+ -

i

?

9 4

I

.t i

I p

l ..

a r

. EMERGENCY CORE COOLING

>: SYSTEM (ECCS)

L' l

AND F. RBS DESIGN BASIS -

OVERVIEW .

I l '

l t .;

, o r.

I I

i  !

. .:lf i

~!

l p ,

i 1

't '

2 M~' ENTERGY OPERATIONS

9.- \

ECCS & RBS DESIGN BASIS OVERVIEW THE ECCS & RBS SYSTEMS, ALONG WITH OTHER ENGINEERED SAFEGUARDS, ACT TO SATISFY THE REQUIREMENTS OF GDC 35, 38, & 41 BY:

-. PROVIDING COOLANT TO ASSURE CORE STRUCTURAL lNTEGRITY F

l

. MAINTAINING THE INTEGRITY OF THE REACTOR BUILDING

. REDUCING THE FISSION PRODUCTS 1 RELEASED TO AND EXPELLED FROM.

i THE REACTOR BUILDING 1  :

,. l-1 9

I l

L O h RA ONS

n ;. .t .

THESE SYSTEMS OPERATE IN THE FOLLOWING MODES:.

INJECTION OF BORATED WATER TO l c THE RCS FROM THE BWST BY THE HPI j SYSTEM.  :

l

. INJECTION OF BORATED WATER TO THE RCS FROM THE BWST BY THE LPI l SYSTEM.

p

'. INJECTION OF BORATED WATER TO- "

THE RCS FROM THE CORE FLOODING SYSTEM.  ;

L

. SPRAY OF- BORATED WATER TO THE L

,1 REACTOR BUILDING ATMOSPHERE FROM THE BWST BY THE REACTOR L BUILDING. SPRAY SYSTEM.

[" . RECIRCULATION OF BORATED WATER TO THE RCS FROM THE. REACTOR  !

"j BUILDING SUMP BY THE LPI SYSTEM (HPI PIGGYBACK FOR VERY SMALL 1 B.R E A KS). l

. -- RECIRCULATION OF BORATED WATER TO THE REACTOR BUILDING

. ATMOSPHERE 'FROM THE REACTOR BUILDING SUMP BY- THE REACTOR BUILDING SPRAY SYSTEM.

< i

~ ENTERGY OPERATIONS 4

k,y i- ;.

I ,, ,

sss i- 1

~ l

- i

s I 5 h  : MM"> 0 nv , nv , nv e a a eX eX -

ma L L c

., ) () (

, n ys y y e e s *N l n <.l <.ii,, c , a 11 il

y. 1

+ u

,l Z *N

< e i 4 4

!I!I!i!{lll ,

D+ 5+ B+ C+

f4 ,e .

-THE ACCIDENTS CREDITING THESE r SYSTEMS INCLUDE: i l

t . LARGE BREAK LOCA

. SMALL BREAK LOCA

. LPI LINE BREAK LOCA o

i. -

HPI LINE BREAK LOCA J

- MAIN STEAM LINE BREAK- 1 it l l '

L

- STEAM GENERATOR TUBE RUPTURE N.'

j l

u  !

i' 1

i

. l l

l I

i 1

L E !?s'5Ls L

,.,n,,- -4 e ^-4 eA -* A +-- ~ m - N & 4-n 4e e-- Ab me- - .m p &4-L 4+ k.A 4

-l i

I

(

t L

51 .

. 5:

'r i

J 1 -

s I

I i

1R9 MODIFICATIONS SCOPE i

l ,

k'.

l

1. I f (

kr t: L i 1 i I

d ,' I a

i I

i:

1- ,

i

.t

.c r

N _

h E~~~ENTERGY OPERATIONS

p .a.

L, .

I.O

1M89 VENTURI MODIFICATION l 1 e

L . - OPTIONS CONSIDERED:

1 1)' VALVE ADDITIONS TO BALANCE FLOW OPERATOR ACTION REQUIRED [

l

2) 'CAVITATING VENTURIS PASSIVE - IMMEDIATE BALANCE NO- OPERATOR- ACTION REQUIRED ADDITION OF CAVITATING VENTURIS J

q PERFERRED SOLUTION - i CAVITATING VENTURIS INSTALLED DURING 1M89 u L' VENTURIS WERE INSTALLED INTO THE SYSTEM AND TESTED FOR PERFORMANCE l-n -

SIGNIFICANT NOISE OBSERVED-- LARGE L AMPLITUDE VlBRATION. IN . VENT STACKS [

L -

VENTURIS REMOVED AND UNIT RETURNED TO  !

80% POWER -

1-L I

6 4'

' '~ ENTERGY OPERATIONS L

L L

+ .

~

]',.

1 .~ -

HIGH PRESSUREJ

- 'l Isi LINJECTION N

a cvin.

cvins PUMP:-(HPIP)

REACTOR .g g y HPIP. ,A, m,

COOLANT t, PUMP (RCP) 5l

  • J RCP 9, W 'A.. 'A.. -l DA, un 'A,one 'Am ei> cviza [{ ,

rtizi. 3 rtizo?]

IMI RCP

  • J ;1A

'A D  : mai'A

.C, <--C><1 'A.c

~2 ,.sc q mia, cvien i HPIP

,B,.

X -y ,,,,,,

FWI A

  • J *'"'

RCP M >I; V

,B, 4--C)<] 'A. . 'A, q.

'A,on. <vizu I 3

- (( rtirm .c,

~,x x-m ll rtiee' RCP '

  • J
  • I T I

'A' ,,,,,, _ q mia. ,,,,,,s tviza ARRANGEMENT PRIOR TO. IM89  :

, ' ' -- ' ;I

. a,

- HEN)

GRO P P p . w

. i, -

I I Y

. I UI 'B, Pg a H S T P P ,-A H

~

p *

. SE( CHH w w

.E R J P . .

  • PNM I U

. A ,~

i '-

h*~

P w

=

- vJk yk J 3

e.

r r e e

,3 a

i n

r

{ I a

'J oi I, ~

v z

ec. a ., l 4 ,i i
n j n

I m M z M e M e ~

vic r I

>c i i i

' 1 v I ;c v I v

c

+

g N

- a z i ,

O I

,i ,

  • Aim
  • Ai~ *Ae.'m *V ,3 T i i ,

5 3

e ' '

i v X A n,

. c C

I r

F r

e r

g .

I

  • Ae i

. 'm D.

M i%3v e

i

' O.

1 c

e

"' M >

e a I ,,3 2 e

c.

i U-i j Dm *D. 9 8

J M a 1 j I

= l I Z 1

%. ]

~

_ $= g;,3a -

- - - - l_ - I__ 7

-. . m

  • A. *Ac.

' *A.' *V -

=

c . *

o. .

3

  • A3 m *Ao.

' *A3' m

)

P C< 3 RT ON( R C

x C

)

C TA = #

CLP < = .

AOM P. P, P, P .

EOU C o C C C B C' A RCP R, R, R. R' _

1 l= _

5 ~

-l,.e ,

.~

e--

POST 1M89 ACTIVITIES

. TASK FORCE MET TO REVISIT OPTIONS

- -TASK FORCE RECOMMENDED RECONSIDERATION OF SAME TWO OPTIONS

- CRITERIA ESTABLISHED FOR 7

l REINSTALLATION OF VENTURIS l- .

! - INDUSTRY EXPERTS CONTRACTED TO' l INVESTIGATE FLOW INDUCED VIBRATIONS 1 i

! - NSSS VENDOR CONTRACTED TO ANALYZE f i j.

SYSTEM RESPONSE WITH REDUNDANT INJECTION LINES AND DETERMINE j OPERATOR ACTION REQUIRED L  ! . RESULTS I - VIBRATION UNAVOIDABLE - MAGNITUDE NOT

[ PREDICTABLE WITH AVAILABLE THEORY l

- INDUSTRY EXPERIENCE DOES NOT l ENVELOPE' OUR APPLICATION .

.. l

- WITH REDUNDANT-INJECTION LINES, l'

ADEQUATE FLOW POSSIBLE WITH NO

! OPERATOR ACTION i - ADDITIONAL MARGIN CAN BE OBTAINED WITH MINIMAL OPERATOR ACTION m i A ONS

m G H e et Shk. *

. - - - -- ~

~2

.g

, INJECTION ' PUMP - (HPIP) ,

= ITI N o REACTOR g cy,,33 ' m*

A8 HPIP A, ..

COOLANT t; cy,,,, cy,,,, .

PUMP (RCP) _ q Q

l WI

,9, W '/ '/ D*G 'A,*M212 '/I Mut213 TA CvtP20 MJ149 MtE6e wJt232

.] A H

I RCP*-C>d M

^

'A. >A

,C, M.c

-n un _} -C=C.

~ 23 -nn Cvnm N 1

,,,, n .'

wln G,,;;

.&*a ' 'B'

.A

,,, g3 tv1279 -

  • I AMJI218 NA Ev1294 m

M ,,,,a3 W

cg .n v :

RCP

  • _l ""'" *

>IA V

, B, 4-C><1 'A,,,3. . 'A..

CA ' 'A,,,,a . Cvim J.

j 3 *

}{ , A H.P I P

,,nx c.

RCP *

  • _I >A

.n, 4-C>G '

A 'A D.,Meu 'A cim-

,,,,, - j ,,,,3 PI,ANNED MODIFICATION

~

.<a .

m ..

RECIRCULATION MODE NPSH -

INADEQUACY RESOLUTIQH THE CHANGES IDENTIFIED TO PROVIDE ADEQUATE' ECCS AND RBS PUMP NPSH

' lNCLUDE:

I -

THROTTLE RBS FLOW PRIOR TO

; SWITCHING TO THE RB SUMP -

L REQUIRES THE FLOW INDICATION TO g l BE UPGRADED TO REG. GUIDE 1.97 CATEGORY 1 TYPE A I .

MOVE THE RBS FLOW TRANSMITTERS

,' p [

TO REMOVE RADIATION INDUCED l

ERROR -

N .

INCREASE THE BWST LOW LEVEL 1 TECHNICAL SPECIFICATION LIMIT I i I

(APPROXIMATELY 2.5 TO 3.5 FEET).

j  !

l 1

4 O y

$Ed$SIONS 1

i i

THE ANALYSES BEING REASSESSED DUE TO THE CHANGES TO PROVIDE ADEQUATE ECCS AND RBS PUMP NPSH INCLUDE:

. LPI AND RBS PUMP NPSH DURING RB SUMP RECIRCULATION ii .- POST-LOCA RB SUMP WATER LEVEL L

i . POST-LOCA EQ SUBMERGENCE 1 QUALIFICATIONS l

t i . BWST SEISMIC QUALIFICATION

' . POST-LOCA RB PRESSURE AND te TEMPERATURE PROFILES L i

. POST-LOCA OFFSITE DOSE-y

.t l- POST-LOCA -RB SUMP pH i

L i

J oER$NONS l

. ,se

-a .. ..

,\'

I

.>.' 4 u  ;

i 1

1 r

J i

i ,1

+

l,, I' J r

1

-! i

+e  ; l l 1 l

! < 1

% L REQUIRED OPERATOR ACTION L i

1, OVERV EW . , 1

'g.

1; l l" iU .

L (.. -

t-l ..

1. ;

1 -

I .

F- 1 i I

' ..l!- l. l

l:. j. J

]

i1 j ,

L (. ,' -

l n ,

1:

i H.!:. ,

IL _

l 4' 1

.\

l' l 1

i 1

l 1 ,

l; l i;

1-

> l l ,

t

l. ,

,3 .

'! l l l  !

g  !

l M ENTERGY l l

t

~ OPERATIONS '

I l

J

, 4

REQUIRED OPERATOR ACTION OVERVIEW EOP ACTIONS DEVELOPED TO ADDRESS AN HPI LINE BREAK CURRENT GUIDANCE REQUIRES THE OPERATOR, IN THE EVENT OF AN ESAS, TO:

'l - VERIFY- EXPECTED HPI, LPI &

i RBS FLOW RATES i

. ' THROTTLE THE HIGHER LOOP A (B) HPI FLOW TO.WITHIN 30-GPM OF THE OTHER LOOP A (B) HPl .

i FLOW .

[ j PLANNED GUIDANCE WILL REQUIRE THE OPERATOR, IN THE EVENT OF AN p ESAS, TO:

- VERIFY EXPECTED HPI, LPI &

' l-RBS FLOW RATES r . IF ONLY ONE HPI TRAIN

~

ACTUATES, THROTTLE THE

, HIGHEST FLOW INJECTION LINE m TO WITHIN 20 GPM OF THE i

NEXT HIGHEST INJECTION lj FLOW LINE i

oEnftTons

I HI

.c. .

a EOP. ACTIONS DEVELOPED TO ADDRESS ECCS AND RBS PUMP NPSH

-CURRENT GUIDANCE REQUIRES THE OPERATOR, PRIOR TO REALIGNMENT FOR RB SUMP SUCTION TO:

. THROTTLE RBS PLOW TO BETWEEN 1100 AND 1300 GPM PER TRAIN e l

. THROTTLE COMBINED LPI AND HPl

. l FLOW TO BETWEEN 2800 GPM AND L 3200 GPM PER TRAIN

- i i i PLANNED GUIDANCE WILL REQUIRE THE OPERATOR TO:

! . THROTTLE RBS FLOW TO BETWEEN J  ! 1050 GPM AND 1200 GPM PER i

TRAIN

. IF HPi FLOW HAS NOT BEEN 1 SECURED' AND LPI FLOW > 3300 GPM, LIMIT HPl FLOW TO APPROXIMATELY 100 GPM UNTIL THE 20 MINUTE HPl TERMINATION CRITERIA IS MET L

!Wah l

., . .. . . .. .~ .. . . .. . . - ..- . -.. . - . . ..-... -- .- . . .~.. .--- - .

  • g. d 1. -;.  ;

i

, [ '- e ..

, Pr- - 3 t

?

L CURRENT STATUS .

AND L SCHEDULES ,

5-1";= i l-

't

~

i

= r 7  ;

L i

l

\

4-O

~ ENTERGY OPERATIONS

--- +

. _ _ . _ _ . . _ . _ _ _ _ _ _ . _ _ . . _ . _ . _ _ _ _ _ _ . . . _ _ _ , ._ _ . ~ _

1 CURRENT STATUS & SCHEDULE -

1 L . HPl MODIFICATIONS ARE PLANNED FOR 1R9, AS

!- ARE THE NPSH MODIFICATlONS l

l PLANNED RESOLUTIONS AME WELL UNDERWAY.

L- THE TWO MAJOR CONCERNS OF RESOLVING '

THE TECHNICAL ISSUES ~ AND OPERATOR o RESPONSES, .WE BELIE'/E, ARE ADDRESSED.

L

' i OPERATOR ACTION REQUIRED ARE A i

i: ' REDUCTION WITH RESPECT TO CURRENT EOP

! REQUIREMENTS.

L.

THE LICENSE AMENDMENT WILL BE SUBMITTED-IN EARLY AUGUST 1990 UPON COMPLETION 'OF AN ALYSIS.

MODIFICATIONS ARE ANTICIPATED TO FALL -

WITHIN THE FRAMEWORK OF 50.59 -AND' ALONG

':' WITH ANALYSIS RESULTS WILL SUPPORT A >

l LICENSE AMENDMENT TO RETURN TO 100%

!.., POWER.

i i -

a iI l

u A $'1 g y

-_