ML20248E991

Summary of 890322 Meeting W/Util in Rockville,Md to Discuss Resin Intrusion Into Condensers at Plant.Licensee Requested to Provide Commitment to Evaluate Procedures Involving Steam Generator Tube Rupture Event.Viewgraphs Encl

ML20248E991
Person / Time
Site:	Summer
Issue date:	04/04/1989
From:	Hayes J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8904120431
Download: ML20248E991 (29)

Text

.__ _ __ . _ _ _ ________ -

q -

Docket No. 50-395 April 4, 1989 LICENSEE: South Carolina Electric & Gas Company FACILITY: V. C. Summer Nuclear Station, Unit No.1

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL ,

On March 22, 1989, the NRC staff, consisting of representatives of the Office of Nuclear Reactor Regulation, Region II and the Summer Senior Resident Inspector, met with representatives of the South Carolina Electric & Gas Company (SCE&G) to discuss the resin intrusion into the condensers at V. C. Summer Nuclear Station. The meeting was held at the NRC office in Rockville, Maryland. A list of those persons who attended the meeting is included as Enclosure 1.

DISt,USSION A handout was provided at the meeting which represented SCE&G's current view-graphs for the presentation. This handout is included as Enclosure 2. During the meeting the licensee the steam generators; (2)provided (1) of the chronology a historical summary the event and recoveryofoperations; the condition of (3) management decisions on the attempt to cleanup; (4) factors influencing management's decision; and (5) the steam generator action plan.

At the conclusion of the meeting the staff requested that the licensee provide the following in a letter prior to restart:

(1) A corraitemt to inform the NRC when the Summer Station deviates from the EPRI Guidelines for Secondary Water Chemistry and advise the staff what the licensee is doing to return chemistry to within the guidelines. A method for doing this would be through the 10 CFR 50.72 reports. If this method were used, the report should be filed within 24 ho.r; of being outside the guidelines.

(F) A commitment to evaluate the V.C. Summer procedures involving a steam generator tube rupture event in view of the recent steam generator tube events at North Anna and McGuire.

(3) Detail steps to prevent further intrus' of resin into the system.

c hl John J. Hayes, Jr., Project Manager n Project Directorate II-1 48 Division of Reactor Projects ' .I, NRR 000 88

Enclosures:

gg As stated l

M cc w/ enclosures:

gg See next page wz

@ (SUM MEETING

SUMMARY

) *SEE PREVIOUS CONCURRENCE \

o a-l

$$a. MDRPR* D. :DRPR \\!

l P.dlm E ce sam E'

( 0 9/89 v /89 a

}

l

)

• a Mr. O. S. Bradham South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station cc:

'Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop, Cook, Purcell and Reynolds 1400 L Street, N.W.

Washington, D. C. 20005-3502 Resident Inspector / Summer NPS c/o U.S.~ Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II -

U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Ceorgia 30323 Chairman, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 29180 Attorney General Box 11549 Columbia, South Carolina 29211 i

Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control  :

2600 Bull Street Columbia, South Carolina 29201 South Carolina Electric & Gas Company Mr. A. R. Koon, Jr. , Manager Nuclear Licensing ,

Virgil C. Sumer Nuclear Station  !

P. O. Box 88 Jenkinsville, South Carolina 29065 lII

__ _ _ _ - - - -- - 1

.i ,

l ENCLOSURE 1 ATTENDANCE MARCH 22, 1989 SCE&G NRC A. Koon. Jr. J. Hayes, Jr.

O. Bradham C. Cheng i D. Moore E. Reeves D. Nauman E. Adensam J. Skolds K. Wichman

.W. Bacon F. Witt H. Conrad .,

C. Hughey R. Prevatte-J. Richardson I

i l

l l

l J

1

.. ENCLOSURE 2 3 .

l 1

l NRC PRESENTATION STEAM GENERATOR RESIN INTRUSION MARCH 22,1989 {

WASHINGTON, D. C.  ;

4

r  : . .

SCE&G ATTENDEES i Dan Nauman Senior Vice President, Power Production Ollie Bradham Vice President, Nuclear Operations Jack Skolds General Manager, Nuclear Plant Operations I Dave Moore General Manager, Engineering Services Mel Browne Manager, Systems & Performance Engineering Frank Bacon Associate Manager, Chemistry -

Al Koon Manager, Nuclear Licensing i

1 9

e 1

I l

i l

Ollie Bradham i 4

1 1

i KEY POINTS OF PRESENTATION o PROMPT SHUTDOWN DECISION FEBRUARY 14 o INFORMED MANAGEMENT DECISION TO STAY ON LINE AFTER INITIAL CLEANUP e CONTRIBUTORS INFLUENCING DECISION e BASIS FOR ASSURED STEAM GENERATOR INTEGRITY e ACTIONS TO PREVENT RECURRENCE

NRC PRESENTATION Wednesday, March 22,1989 INTRODUCTION O. 5. Bradham l

HISTORICAL

SUMMARY

S.G.'s EVENT CHRONOLOGY M. N. Browne ,

MANAGEMENT DECISIONS J. L. Skolds STEAM GENERATOR ACTION PLAN D. R. Moore

SUMMARY

& CONCLUSIONS O. 5. Bradham l

l l

I l

(

j 1

Mel Browne

PLANT AND STEAM GENERATOR DESCRIPTION e 3-LOOP WESTINGHOUSE, 900 MWE o MODEL D3 STEAM GENERATORS e FEEDWATER PREHEATER e ALLOY 600 TUBES, MILL ANNEALED e CARBON STEEL SUPPORT PLATES CONDENSATE POLISHING (50%)

e FEEDWATER DEAERATOR 1

l i

l

STEAM GENERATOR HISTORY

l PRESERVICE INSPECTION

. 7 TUBES PLUGGED JULY 1984 e FORCED OUTAGE e PLUGGED LEAK AT ROW 1 U-BEND IN "B" S/G OCTOBER 1984 l

e FIRST REFUELING l e PLUGGED LEAK AT ROW 1 U-BEND IN "B" S/G I e 4 TUBES PLUGGED - PRIMARY SIDE INDICATION I MAY 1985 "

e FORCED OUTAGE e PLUGGED LEAK AT ROW 1 U-BEND IN "B" S/G l e PREVENTATIVELY PLUGGED ALL ROIN 1 IN "B" S/G OCTOBER 1985 e SECOND REFUELING e' ROTOPEENED ABOUT 50% OF HOT LEG TUBES e 166 TUBES PLUGGED - PRIMARY SIDE INDICATION MARCH 1987

. THIRD REFUELING e SHOTPEENED REMAINING HOT LEG e STRESS RELIEVED REMAINING U-BENDS e 171 TUBES PLUGGED - PRIMARY SIDE INDICATION

e UPDATED BASELINE INSPECTION

• 100% FULL LENGTH INSPECTION ,

i

. MULTIFREQUENCY '

e MlZ 18 EQUIPMENT e

REMOVED SUSCEPTIBL(HOT LEG PLUGS e TUBE REMOVAL. .

e TOTAL OF 1091 TUBES PLUGGED e NO TUBE PLUGGED AS RESULT OF SECONDARY ATTACK i

/

l I

l L _ - - - - _ ---- -- --

sI, , i I f 3 I

-- L L/00 ;

5,5

.ma , i

!.: . .90/E0 m

,. LO/CO w

5 i: o

1. 3/30 s i ti

-6L/30

' ' ' ' ' 8 i l' r i i i , , , , , , , , , , , ,  ; .. ,tjgg 8 8 8 8 8 8 8 8 8 o g o o o cocoooo8oo c o 8

$. $. $. c o n o co c o . 8 s' s'seee0$2333*oyg

; 92a d d d

1'  : -

CLEANUP CONSIDERATIONS i

~

e MAXIMUM S/G BLOWDOWN FLOW e HIGH CONDENSATE AND FEEDWATER FLOW VELOCITIES e BULK WATER CHEMISTRY REPRESENTATIVE e LOW SLUDGE e LOW MAGNETITE  !

e LOW HEAT FLUX e LOW CORROSION RATES e LOW OR NO OXYGEN IN FEEDWATER t

e LOW POWER / TEMPERATURES e OTHER CONTAMINANTS WERE LOW l

l I

,y e 6 e

4 Jack Skolds

INITIATING EVENT e Blowdown Demineralizers e Valve inside Tagout Boundary e Operator Error e Corrective Action

- Procedure Chan ges '

- System Study

- Modification i

l I l,'

' 2 8

7-2 0

3-D g

G N N I

H M S

I E I

' 2 G

IN N H

SMI J ,

F E

R I

E 8 g

L L O D O D 4 P

[ P

% L F

X

~

2 2

1 6

D V

X Y

RN AI MM '

Y RN AI J ,

. I.

1_ MM

'g I RD P

E l

[ P I

RD E

\ \

L 7

l 6

,I 8

7 A B 1 OW 6 L 2 2 D M n

1 1 1 1 6 V R 6

D X  ;

D V V _

X X M "

1 2 N __

E 1 TI t T

S Y

6 D

V X

O W S

G b

N

)^ - N I

S RWR f'J/

S O E A E OT K C LDI N O A CW U NA OT R 6 8 6

N OLM 5 B P P 5 P

N X M W

O D

N W 7 2

O 1 L

B R

O WD 6 V

X N

A E RWP L

A E OK U R C LDDN E S

U CWLA U OT N

[

E N NOL H D B N O

C

a; ... ' * ,

[ .

S g

gl B g $

8 II.

ain I

9L/C0 OL/C0

-j' daa

%. .... .. 3

(

t0/00

.h 5-a  ;

l

'92/20 l 2-02/20 ,

I i i i iiisi i i i i G tL/20 '

O O O o o o o o o o o o o o o o o o o o, q q q o o o o

o o

O o 8 o 8R848*d

• d = 4 6 l

MANAGEMENT DECISIONS e Based on EPRI Guidelines

• Safety was always considered first e Based on knowledge available at the time

• Quickest method of cleanup e immediately collected industry l information  ;

e Sulfate effects not clearly known

)

1

,, .e e

Dave Moore f.

)

i l

l l

e Introduction e Factors Considered e Decisions Based on Factors _

e Current Actions e Near Term Plans e Technical Summary

.g e

.- FACTORS e Bulk Water Chemistry e Boric Acid Soaking' e Hideout Conditions i

e Knowledge of Tubinn -

e Sensitization Aspect t b

e Condition of SG's l

e Plant Conditions *

• Oxygen Aspect

DEClSION5 l

e To Utilize Plant Case History ,

e North Anna Similarities  !

• 85 V.C. Summer.

Intrusion- .

• Almaraz Information e EPRIInformation e To Consider i Theoretical Data  !

e Sodium Sulfate Data 1

y s' .s

• 4 4

CURRENT ACTION e Flushing e Contaminant Removal .

• Cleaning e Moisture Separator Section e Bundle Wash e Sludge Lance

r NEAR TERM PLANS e Boric Acid Treatment. -

e Appropriate ~

Chemistry Control e Hydrogen Monitoring

=

TECHNICAL

SUMMARY

l e Safety First e Decisions Prudent .

e Current Cycle Actions e Future Actions

e 9

i Ollie Bradham

~

__________m-_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ . .

c - -

1  ;

SUMMARY

& CONCLUSIONS 1

o PUBLIC HEALTH AND SAFETY NUMBER I PRIORITY e PROGRAM MINIMlZES SHORT AND LONG N! '

TERM EFFECTS 7 e MONITORING ADEQUATE TO ASSURE  !

INTEGRITY e FUTURE DECISIONS TO PROTECT STEAM GENERATORS WILL BE CONSERVATIVE e APPRISE NRC OF SIGNIFICANT CHANGES IN CONDITIONS OF GENERATORS o

m .-

, , ,y- -

q.e DISTRIBUTION FOR MEETING

SUMMARY

DATED:- j

-Facility: V. C. Sunner

- *E M IRM NRC PDR ~

Local PDR.

PDII-1 Reading-

'E. Adensam E. Reeves P. Anderson J. Hayes

- OGC E. Jordan (MNBB3302)

B. Grimes'(9A2)

F.Cantrell(RegionIjl P.

'R. Hopkins Prevatte (Region egion II))

II D.'Verrelli Region II)

ACRS(10)

R. Borchardt (17019)

.cc: Licensee / Applicant Service List I

M J l i 1

l l

.-