ML20199C552

Refers to 980121 Meeting in Region IV Ofc Re Radiation Protection,Chemistry & Radwaste Program Activities,Per Licensee Request.Specific Topics Included 1997 Performance Indicators & Improvement Opportunities.Attendance List Encl

ML20199C552
Person / Time
Site:	Callaway
Issue date:	01/28/1998
From:	Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Randolph G UNION ELECTRIC CO.
References
NUDOCS 9801300037
Download: ML20199C552 (48)

Text

o-fe a4% i UNIT ED ST ATES

f. ,\ NUCLEAR REGULATORY COMMISSION f e nEclONIV

%.' ,f 611 RY AN PLAZA DRIVE. SulTE 400

$9 #

/ AR LING TON. T E XAS 760118064 January 28, 1998 Garry L. Randolph, Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fultor,, Misscuri 65251

SUBJECT:

CALLAWAY PLANT RADIATION PROTECTION PROGRAM PERFORMANCE This refers to the meeting conducted in the Region IV office on January 21,1998. This meeting was conducted at ?5e licensee's request to discJss the radiation protection, chemistry, and radwaste program activities. Specific topics of discussion included: 1997 performance indicators, challenges and improvement opportunities, and plans for Refueling Outage 9.

In accordance with Section 2.790 of the NRC's " Pules of Practice," Part 2, Title 10, Code of

. Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.

Should you have any questions conceming this matter, we will be pleased to discuss them with you.

Sincerely, Blaine Murray, Chief -

Pl:at Support Branch Division of Reactor Safety Docket No.: 50-483 License No.: NPF-30 /

f

Enclosures:

1. Attendance List

2. Licensee Presentation cc:

Professional Nuclear Consulting, Inc.

19041 Raines Drive rierwood, Maryland 20855 Gerald Charnoff, Esq.

Thomas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.

Washington, D.C. 20037 lll11!II:llill

~''

llll!Illl 9801300037 980128 PDR ADOCK 05000483 P PDR

o Union Electric Company 2-H. D. Bono, Supervising Engineer Quality Assurance Regulatory Support Union Electric Company .

P.O. Box 620 Fulton, Missouri 65251 Manager - Electric Department Missouri Public Service Commission

'301_ W. High P.O. Box 360 Jefferson City, Missouri 65102 Ronald A. Kucera, Deputy Director Department of Natural Ret.ources P.O. Box 176

- Jefferson City, Missouri 65102 Otto L. Maynard, President and

- Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 Dan 1. Bolef, President Kay Drey,- Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, Missouri 63130-Lee Fritz, Presiding Commlssioner Callaway County Court House

~10 East Fifth Street Fulton, Missouri 65151 Alan C. Passwater, Manager Licensing and Fuels Union Electric Company -

P.O. Box 66149

- St. Louis,- Missouri 63166-6149

- J. V. Laux, Manager Quality Assurance -

Union Electric Company P.O. Box 620 Fulton, Missouri 65251 a

4 Union Electric Company DISTRIBUTION w/ Enclosures 1 and 2:

DCD (IE35)

Regional Administrator Callaway Resident inspector DRS Director.

DRS Deputy Director i DRP Director DRS-PSB Branch Chief (DRP/B) ,

Project Engineer (DRP/B)

Branch Chief (DRP/TSS)

C. A. Hackney, RSLO L. T. Ricketson, DRS/PSB MIS System RIV File 4

l-l e

i DOCUMENT NAME: G:\DRSLTRS\CWMS0121.LTR To receive copy of document. Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:PSB C:DRS\PSB LRicketson:ng ~

BMurray h '

01f#98 01M98 OFFICIAL RECORD COPY 4

i

v. .

E e

Union Electric Company '

DISTRBtlTION w/ Enclosures 1 and 2:

gDCD(M)' J'~ Regional T Administrato[@ .

Callaway Resident inspector DRS Director DRS Deputy Director DRP Director

- DRS-PSB '

- Branch Chief (DRP/B)

Project Engineer (DRP/B)

Branch Chief (DRP/TSS)

C. A. Hackney, RSLO L. T. Ricketson, DRS/PSB MIS System RIV File l

t

)

DOCUMENT NAME: G:\DRSLTRS\CWMS0121.t.i R To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy

RIV

PSB C:DRS\PSB LRicketson:nhp> BMurray y 01/f98 01M98 OFFICIAL RECORD COPY l 300003 jti e+f t

Oc tat c 1

(, ( NE 5/DC+I / /

ENCLOSURE 1 MEETING: UNION ELECTRIC - CALLAWAY PLANT

SUBJECT:

Radiation Protection Activities and Performance DATE: January 21.1998 ATTENDANCE LIST NAME ORGANi2ATION ' POSITION TITLE Dwight Chamberlain NRC Deputy Director, Division of Reactor Safety

- Blaine Murray NRC Chief, Plant Support Branch, Division of Reactor Safety R:y Azua NPC Project Engineer, Project Branch B, Division of Reactor Projects Ltrry Ricketson NRC Senior Radiation Specialist, Plant Support Branch, Division of Reactor Safety Mike Evans Union Electric Superintendent, Radiation Protection Rcn Roselius Union Electric Superintendent, Chemistry and Radwaste I

e

=

Re?""

XRC Region IV Briefing Callaway Plant January 21,1998 Radiological Protection Areas

-Health Physics

-Chemistry

-Radwaste Presented by:

M.S. Evans, Supt. HP R.R. Roselius, Supt. Chem /RW l

Purposm Provide an update on Callaway Plant operations and performance Dialogue on issues and F1ivities related to Radiological Protection das Progrrr s a tt ,y PLRflT

.Provice information and answer questions on topics ofinterest to NRC Auenda '

• 1997 Performance Indicators

-HP

-Chemistry '

-Radwaste Challenges and improvement Opportunities

-Axial Offset (AO)

-Failed Fuel

-Refuel 8 Corrective Actions

-Radwaste Processing '

-Department Challenges and improvement Opportunities Refuel Outage 9

-Schedule

-Goals

-Radiological Considerations  :

-Shutdown Chemistry

cnunuMY Perfbrmance Indicators .

PlaflT Health Physics

- Manrem Exposure

- Liquid Rad Effluents

- Gaseous Rad Effluents

- Surface Contamination 4 Chemistry

- Chemistry Index

- Primary to Secondary Leakage

- RCS CRUD (Co-58) ,

- RCS Dose Equiv. Iodine (DEI)

Radwaste

- Liquid Radwaste Influents

- DAW Generation

- Low Level Solid Radwaste l - Radwaste Burial Performance

~ - ~ - -

. PERFORMANCE OBJECTIVE: MANREM EXPOSURE Achieva m nrem cxposure of lesnthan 12 for 1997 in cupport of a three-year average of less than 100 manrem by end of 2001. RDA/MSE PERFORMANCE

SUMMARY

l Current Situatson Exposure goal was raised from 12 Manrem to 16 Mantem in July 1997. The initial ep goal 400 r assumed NO failed fuel. Current projedions show that we will be dose to the 12 Mantem initia'ly 336

' ~' proposed. The Power redudion to 70% for AOA accounts for doses being lower than projeded.

300 4  ; y The 12.8 Manrem for 1997 is the lowest Manrem achieved during a Non-Outage year.

224

'. : 7 194- 191 187 .;i.

200 i l!  !  ;

1S Actions 100 2  ;

i L ' '

.: - ; Dose rates in the plant are elevated due to failed fuel. We are continuing to monitor all areas of the  :

~

l j 14 L i .:' ) # ant to ensure tWy uNates of @W postings hM condh dange. _j 0!'"'i '

'; 1

- 1995 INPO Performance indicator (3 Year Average) = 161.0 '

1992 1993 1994 1995 1996 1953 INPO Performance Indicator (3 Year Average) = 147.0 D Annual Manrem DM Average MANREM EXPOSURE

~

I GOOD THREE YEAR AVERAGE: 149.3 Manrem 18 -

GOAL: < 16 Manrem (See Note Above) 15 - ,

12 - 10.5 ^

8 N7 9- 12~1 11'.0' 9- 7.7 84 .

S.3 6- 5.2 3.9 3-0 ' ' ' * ' '

2.0 1.9 1.3 1.1 '4.

O.7 ' 1.1 1.0 O.5 O.7 ~ 0.4 '

O.7 JAN FEB MAR -APR MAY JUN 'JUL AUG SEP OCT NOV DEC Obj 3 M nthly Adual -e-Projeded -+-Canulative Adual

~ - _ _. - _ _ _ _

m Manrem Exposure I gj 3 year average being maintained at approx.150 Manrem 1997 Manrem Goal

- Assumed NO Failed Fuel

- Based on best performance to date of 14.2 Manrem in 1994

- Revised in July 1997

- Power Reduction in August 1997 reduced General Area dose rates by approx.1/2 Improvement Opportunities

- AO Resolution

- Shutdown Chemistry

- S/G Dose Approx. 25-30% of outage dose Pursuing electro-sleeving tube repair, currently under review Anticipate approx. same failure rate as Refuel Outage 8 -

1998 Manrem Exposure Goal is 200 Manrem 1 -

185 Manrem Refuel Outage 9 Dose 15 Manrem Non-outage Dose

- .. ..~ .-. .. . . . . .

PI-17 LIQUID RADIOLOGICAL EFFLUENT RELEASES RDA/MSE l PERFORMANCE CUMMARY l Current Situation Cuth M Dose Both Liquid Radiological Effluent Total Curies and % of Whole Body (WB) dose limit were below

,, o.7 the Stretch Goals established for 1997. In early April, waste processing using filtration and 0.7 - 0s demineralization was discontinued. Several changes have been made to the Radweste filtration and

~ 0.6 demineralization process and procedures. These changes will allow us to retum to filtration and 0.6 -

-- 0.5 demineralization .

• 0.5 - .

- 0.4 0.4 - 0.3 N'

- 0.3 0.3 - '

Actions 0.2 -  :

~~*A 0.1 O. -

~

~1

• ' O.005 5*M*M ' 'O.I15 '

1992 1993 1994 1995 1996 EZICuries + % Whole Body Dose Limt 1

LIQUID RADIOLOGICAL EFFLUENT RELEASES Curies

% WB Dose Limit I~ GOAL: <2% WHOLE BODY DOSE LIMIT STRETCH GOAL: <1% WHOLE BODY DOSE LIMIT 82 01

--02 0.17 0.8 - o.1s c.11 o.is

-- 0.15 0.6 - -

1. ' 8

-- 0.1 0.4 --

STRETCH GOAL: <0.3 CURIES

'- ~* ~' - ' '

02- n. 3 .i54 0 18 ' *'7 -

- 0.05

.102 0 L.1 +b.052 E.036 F,.,3 7 t io , l.,  ;

L, l - .. ,

e 3, ,,, +, N O JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC PI-17 8553' M "th E-'"3 Year to Date + % Whole Body Dose Limit i

Liquid Radiological Effluents 1.a.i.

EM" Goal Re-evaluated in 1996

- Established 0.25 Curie Goal based on Industry Comparisons

- Percent of Whole Body Limit Remained at < 1%

Liquid Radwaste Processing

- Moved to Filtration and Demineralization in 1996

- Used Evaporators, Filtration, and Demineralization in 1997

- Will use Filtration and Demineralization in 1998 1998 Liquid Radiological Effluents Goal is <0.25 Curies and <1% Whole Body Limit I

_-___-_y____,

PI-18 GASEOUS RADIOLOGICAL EFFLUENT RELEASES RDA/MSEl PERFORMANCE CUMMARY l Current Situation Gaseous Radiological Effluent Total for 1997 was 483.0 Curies, below the Stretch Goal of 500 Curies Ct. ries. Gaseous effluent levels trended down over the last 5 months of the year due to reducing iT k Unit Power.

800 --

600 -

400 -- Actions Trending of Unit Vent and Radwaste Vent gaseous levels are being performed each shift to ensure 200 -  :

150 ne Hve acu ns are taken to wnufy aM conect any elevated levels in a umely manner. Gaseous 122 effluvats for the past 2 months have been lower than previous months this cycle due to the Power s

0+  ! + + l  ;

" '^^'

1992 1993 1994 1995 1996 GASEOUS RADIOLOGICAL EFFLUENT RELEASES g Curies Y 800 7 700- - GOAU 6 CURIES 600 - STRETCH GOAL: <500 CURIES 500 --

382.0

-  : 46j 7 473.0 483.0 '

400 - 361.0 409.2 436.0 449.3 -

300 --

200 - 15 100 - 53.3 0 i 53.3 39.9 61.8 141.0 65.0 21.0 27.2 26. ' 13.3 13.4 1 .3 1 JAN FEB MAR APR MAY JUN JUL AU SEP OCT NV D PI-18

Gaseous Radiological Effluents

=

, EE"" '

Significant Increase in 1997 due to Failed Fuel Power Reduction in August 1997 to 70%

1998 Gaseous Radiological Effluents Goal is 600 Curies

)

m

PI-19 SURFACE CONTAMINATION AREA RDA/MSE l PERFORMANCE

SUMMARY

l Current Situation

% MRCA 1997 Average % Surface Contaminated Area was 4.3%, below the 5.0% Stretch Goal.

10 T 8

6.5 6--7

dd M M M 4+ i

'.  : 1  :

i  ; i  ?  ?

i . i Actions 2-- l l [ ]  ;. ,; [ l l j None required.

0 +

'F' '

'+ '

1992 1993 1994 1995 1996 NOTE: % of RCA is based on 171,833 square feet.

SURFACE CONTAMINATION AREA

% of RCA 10 I

GOOD i

9-8t 7 -

5.s GOAL: <6%

6 - - - - - - - - - - -

_ STRETCH GOAL: <5%

5 -- -

43 4.:3., 4.2 4.2 4.2 4.2 4.2 -

43 g g

_ _ w = _ _

34 _ = _

_ _ =

_ . =

2- _ _= -

_EE _

= _

1~- 0.6 0.6 _ 0.5 0.5 0.5 0.5 t t!;

=

L5

11. 5 tL5 11 3 EE lllll, lllll+= lill!,

-lllll1; = lilli; = 111ll;

= l 1:I, = _ ll11, =l lill; = l lil; -

1.11; O i  ;

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC PI-19 e as o>2som opm

PI-13 CHEMISTRY INDEX RDA/ECO PERFORMANCE

SUMMARY

Cotrent Situation Plant power was increased 4% dunng December to a new level of 74%. Secondary plant chemestry 2 -- parameters remamed below industry medians. j l

Parameter . Callaway Value Industry Median i 1.5 -- ChlorM: 023 1.6 I M Sulfate 0.86 1.7 i~

1 '~

I  :

Scdium FW fron 0.33 2.8 0.8 5.0 j

NO HISTORICAL i .

. . 02 0.5 -DATA AVAILABLE'  ;

.- ) Actions Close monitoring of chemistry parameters continues.

1992 1993 1994 1995 1996 CHEMISTRY INDEX 4Y 2.5 -

i GOOD 2 -

GOAL: $1.1 1.5 - S1 RETCH GOAL: $1.0

1. 3 1. 3 1.03 1.03 1.02 1. 3 1.0 1.02 1.02 1.02 1 2 1.co m as e e m = a ur e er as a Wa 0.5 -  :

i Ws2 We 1, -

: 3  :  :  :: :  :  :  !

0 C:*t! i"~l:  !" 1-"  :

~

iL"  :

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV- DEC PI-13 " 'mn ecopper -wum msuirate echione -+-Smo nmning avg.

Chemistry Index

.a DE""

Indicator of Secondary Chemistry performance

- Measure of how well taking care of S/G 1.0 is best performance achievable All 5 index parameters better than industry median 1997 average 1.01 1996 average 1.06 l

)

l

.. . . . . _ . ._ .. .... g

. . . . .....,n -

..n . ... .. ..

I ili L

> 9mQ gO Za00 CMQ g

=

fG %G

>Ihg>< n e E53 OM5 O?4h>5, Pu

$u 0 0

oa ,

0m e c

p 9w g

(

E G

A 0o J' '

K A

E L

Pu *

~ .

3e f - ~  %

9-

?

- k[

> ( (, <

7 h

o 6 7 7

7 7

7 7 7 8 6 9- 9 9- 9- 9 9- 9 9- 9 9-c n r a

r p n g p e

v o n b e a A-u u a e D J M- J- A-S- N- J- F-1 0 1 0 9 8 7 6 5 4 2 1 3 1 0 2 1 0 2 0

m l l

nm Primary to Secondary Leakage Am

"?e?""

S/G integrity good Leakage dropped following RFO8 Lowest leakage experienced for last several cycles N-16 monitors Programmatic improvements in detection and response

....................g

RCS Cobalt 58 CALLAWAY CYCLE 9 Co-68 WEEKLY AVERAGE 1.40E-01 1.20E-01 l

1

'L 1.00E-01 i o l 3

N 2 8.00E-02 o

-t 6.00E-02 m

h <>

4.00Em ,

2.00E-02 j ,, l

,,, ,, s is s a a a a a U a a s s 5 a b $

$ h N $ l 2

e 2

~

h e

a f

.h 2 , \

DATE I

l

._ _n _ _ -. .

RCS CRED

.a lEY"  ;

Levels elevated compared to Cycle 8 Increases with changes in Axial Offset Trending up w/ ammonia addition CVCS letdown line dose rates have not increased i

P l

i j es-qeg-pg j' ucr-g

! ^oN-9 6 D

C

- 464*S-4g O

H sl:

+*d N -464ry-g y y t M

O @ I

.~

k g >

unr-6 L c

o l h >

CT

' 46-Kh/tc s

o 5 m a O <

O' Jm-t t O

C ~ 46-uer-og h W>

<l _

^

96-080-L l

96400-24 9 9 9 9 9 9 Q 8 n n d n & e s $

g B/ ton) Leg.130

g, RCS DEI-131 aW""

Fuel defect early in cycle 3 defects DEI 1.3E-2 uci/ml Tight defect

w-w user - - - ummer t -Tu,-

PI-14 LIQUID RADWASTE INFLUENTS RDA/RDM PEkFORMAN

SUMMARY

Current Situation l

Pnmary drain mfluen's have cominued to decine refecting an overall tighter piar:t and atterdion to Gasons per day unexplained influents. Average Dady enfluents for 1997 was 2f)56 gallons per day.

886 4000 -

h 3677 s  ; m 3352 3000 -- 54 .

j K 2 _858 i of i  !

l { RQ 2000 -- ,,o g^g  ?

'j 3 L.

% Actions issy m, e  % y 1000 -- DATA L 2 L E C f None required.

LVAILA8U f  ; q y { j [ b 0  ;

"' '  : '"*l' "; '

1992 1993 1994 1!$5 1996 LIQUID RADWASTE INFLUENTS 1

Gallons per day V 4200 --

Gooo 3500 --

2800 --

2490 2288 2150 2167 2125 2100 -- 1916 1988 1737 IIM _

_1901 1400 -- N

- -- z 700 -- =

0 --- l l l l l  :  :  :  :  :  :  ;

p JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

Liquid Radwaste Influents EI#""

Directly correlates to liquid effluent releases and solid radwaste generation-

- All time low

- 28% reduction from 1996

- 57% reduction from 1993 Reasons

- Plant material condition

- Coordination of draining with Operations

- Leakage monitoring and response

m rm m e- . .

r-~m m r-m - -

PI-15 DAW GENERATION RDA/RDM PERFORMAN SUtdMARY Current Situstion Generated 33 4 cubic feet ofincinerable DAW and 26 9 cubk: feet of compac*tble DAW during Cutsu- Feet Noamber,1997 20480

m. .,  :

s4 15000 -- 0 l?

$g 10000 -- 4 ) g4$

1' L q 6490 Actions 5000 a l 4  :.

R" .s .

Numbers generated using new weight to densrty convercion assumptions. All previous data for

d $ '( j  ; 'l 1997 has been updated with new conversion 6 gores (15#/13 for compactib'es and I?#/ ft3 for t _.c - . .. J y, _a ;'.

..! incinerables). Conversion figures used at the beginning of199; were 3 vests cid and did not n .

reflect the continuously changing nature of our waste streams.

1993 1994 1995 1996 DAW GENERATION 4500 __ Cubic Feet coop 4000 --

3500 -- -

3000 --

GOAL: <2,500 TOTAL 2500-- -

2000 ~ STRETCH GOAL: p,000 TOTAL 1500 -- 1192 1267 1327

, 994 103 1000 -- 666 soo --

0 '

,w ss W

' " - ~ ' ' '

~

~

' ' ~ ' '

PI-15 kk kB b b Month hk/ N

--*- Year-to-date N kUb SYP

-.--Year-to-Date herage bT Nb DkC

PI-16 LOW-LEVEL SOLID RADWASTE RDAfRDM PERFORMANCE

SUMMARY

l Current Situation 325.4 cubic feet (5.22 cubic meters) of waste were buned an December,1597. Thrs cor.s:sted of 100W "* 298.81.ubic feet of compactible DAWthat was processed by CNSIin March.1997 from shipment l 97-0014,218 cubic feet of compact.ble DAW from shipments 97-(D05 and 97-0035 processeo by MOO SEG (now GTS-Duratek) and 4 6 cubic feet from shipment 974]D03.

g_.

l48--

e; b

pus a.eo g$i?p' g__ ~

f y g ya k j f  ?.

Actions

>  ?

20 --f 4 '[ *! i J 17.06 L

?) None required.

, a "(; $!s .13 $f;  ;

L .f ,

1992 ':a93 1994 1996 1996 LOW-LEVEL SOLID RADWASTE Cubic meters 000o 70 --

60 --

G C 80 50 40 -- - ---------- ET_M_H_9 0_% _ _ _ _ _ _ _ _ _

30 -- 27.91

/'>

18.66 18.89 20 --

13.52 13.81 14 M18,05  ;

10 -- 5.2 o =m 2.63 .: 5.1 . .-  :.- .. . .  :. . . .

A h A N Jh kN Nh bb Nh hb TE23 Month + Year-1o-Date

l CALLAWAY BURIAL PERFORMANCE 8,000 --

7,000 6,000 j 5,000 -- WPO 2000. Goal -

3 4,000 -_ (3 yr. A'verage) _

$ 3,000 2,000 -

1,000 2d 1 -

0-- - - -

l- l - - I  ! l i Ol l 1989 1990 1991 1992 1993 1994 1995 1996 1997 Evaporator Bottoms i  : Resins / Filters mDry Actiw Waste ~x S/G Chem Clean Waste 3-Yr Avg

Challenges and Improvement

.ame

=" Opportunities

- Axial Offset

- Fuel Defect

- Refael 8 Corrective Actions

- HP

- Chemistry / Radwaste

- Radwaste Processing Department Challenges and Improvement Opportunities

- HP

- Chemistry / Radwaste

Axial Offset EaE' More significant than Cycle 8 Dcwn power to 70% due to shutdown margin concerns Currently at 74% w/ AO trending +

Corrective' Actions

- Core redesigned for Cycle 10

- RCS pH control- constant 7.1 pH cycle 9 and 7.2 pH cycle 10

- Ammonia Addition to RCS RFO9 Impact

- m - , , - - - - - - , - -

Axial Offset Cycle 9 AO - Cycle 9 Updated Inns Current RAOC Lanas @ 100% Power = -17%,+6%

13 -

11 Predicted-Westinghouse 9 --- Predicted-UEFCM 0 Measured-Inco s 7

A Measured-Excore 5

3 [ Power reduced to 70* Power increased to 72%.l D @ iPower increased to 74%.l j#

\ m _______________________o--- m_D_ _ __________ -

y,

,3 'h l Power reduced to 77%. F -F o :PH reduced to 6.9l

-5 "# \

~

Power reduced to 30%

D and retumed to 70%.

-9 i

-11  % a _o g

-13 00 oa0 g D

ower reduced to 95%.l 0o

-15 *

-17 + 4 0 2 4 6 8 10 12 14 16 18 20 22 Bumup (GWDIMTU)

Ammonia Addition to the RCS

=

Efn?"

l

- Purpose - complex with Ni rich deposits on fuel and solublize the corrosion layer resulting in AO improvement Technical Bases - Siemens international experience

- Governed by procedure and 50.59 FSE Over 50 additions performed No CRUD Bursts or filter plugging

- RCS CRUD levels elevated

- - -- - -. - - - - - - - . == - .--

RCS Ammonia CALLAWAY RCS AMMOMATREND 3.50 3.00 1 50 --

jm

{

y < >

f

{

i

--.-- RCS

- -CVCS EFF.

1.50 0.00 = -

12/2/97 12/7/97 12/12/97 12/17/97 12f22/97 12/27/97 1/1/98 1/6/98 1/11/98 1/16/98 1/21/98 DATE

. $3.%

Axial Flux Distribution -

CALLAWAY AXIAL FLUX DISTRIBUTION DAILY AVERAGE p

AMMONIA TEST ,N

?

0.50 NI CALIBRATION GA!N 9 V &

f r

73% Power m ROD MOVEMENT GAIN 74% Power

-0.50

-1.00 -

pH REDUCTION GAIN

-1.50

-2.00 l -2.50 9/27/97 10/17/97 11/6/97 11/26/97 12/16/97 115/98 1/25/98

=

DATE

RCS Cobalt 58 and 60 CALLAWAY RCS RADIOCOBALTTRENDl 1.OE+00 1.4

, h 1.0E-01

{ 1 3 ppm Ammonia S $ 0.8 $

y 1.OE-02 a

p

- o

> i D

• J

! 0.6 m$

2 l E .

iE  : Ave. Co-58 1.0E-03 ---; b - 1, 0.4 0h - o- - Aw. Co40 0

x --.- AFD as  :

~

s 02 i;'

'[

8 -8 O -

T 5

5 1.0E $

O N

$ - -02 1.0E , _

AMM N .

] -0.4 CHEMISTRY STARTED 1.0E -0.6 11/06/97 11/16/97 11/26/97 12/06/97 12/16/97 12/26/97 01/05/98 01/15/96 DATE

. . . - - m- . . ,, - _ _ _ _ ,

Cycle 8 and 9 Comparison

,CALLAWAY CYCLE 8 vs. CYCLE 9 COMPARISON 6.00E-02 10 Ammoma RCS Chemistry started 12, 5.00E-02 j 5

.T

_ 4.00E-02 p 2 a o o 0 >-

3 $ + CYCLE 8 Co-58 3.00E-02 y { 5 + CYCLE 8 AFD y 5 + CYCLE 9 AFD

.o -5 s b

• 2.00E-02 y g 1.00E-02 ---

) -10 gr

k. - -

t  : .

0.00E+00 -15 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 MONTH

_ ~_ .

Fue! Defect M

DE" Failure in fresh, high flux assembly 20 x Fuel Reliability Index for zero defects RCS fission gases 0.5 -1.0 uci/g Fuel Failure Action Plan Potential outage impact oflarge spike at shutdown

Refuel 8 HP Corrective Actions

.a CALLAWAY Increase Manning of Vendor Technicians due to AO impact Engineering Evaluation of Pressurizer Spray Flow during Cooldown is being evaluated .

Implementing additional Guidance for Cavity and Head work activities Prioritize Temp Shielding Installation

- Loop Piping

- Pressurizer Spray and Surge Lines Establish ALARA contact in Outage Maintenance Facility Re-evaluating Cavity Decon, pursuing remote vacuuming and detergent decon in lieu of diver and strippable coating Installation of Permanent Postings for Bioshield Entrances during Outages Revised procedural guidance for RCP Shipping Container

. Surveys and included in Training of Technicians

Chemistry RFO8 High Dose Rate aufl" PLRnT SelfAssessment

- Detailed Assessment conducted w/ assistance ofindustry experts Independent Review by EPRI and Peers

Conclusions:

Root Cause - AOA Avoid modified 7.4 pH regime Shutdown Chemistry does not lower dose rate Keep H2 elevated during acid reducing conditions Extend Acid reducing time during shutdown Minimize acid reducing conditions during startup

--- - - -, c. , c Liquid Radwaste Processing

. nae -

cnunwar Implemented demineralization processing in July of 1996.

- Last to use evaporators

- Cesium selective resin

-Install plant equipment used Demineralization discontinued in April 1997 due to elevated Co-58 levels Corrective Actions

- Admin limit placed on activity released

- New charcoal used for Cobalt removal

- 0.5 micron bag filter installed

- Implement used of additional charcoal bed for reprocessing Restarted Demin Processing in December 1997 1997 Totals 2.3 E-1 curies released 6.09 E-3 mrem (0.2% of annual lirnit)

w <;y, HP Department Challenges and onom PL E T Improvement Opportunities FSAR Review and Procedure Revision

- FSAR Review on-going

- STS Implementation in March 1999 ALARA Program Improvements

- Outage Review Board Membership Revised

- Post Job Review Threshold Reduced from 20 to 7.5 Manrem

- ALARA Suggestion Program

- Implementing site-wide simplified Suggestion Program for Refuel 9

- 1997 SOS Suggestions - 8, Requests for Resolution (Design) - 10 1998 YTD SOS Suggestions - 2, Requests for Resolution (Design) - 0 High Radiation Area Controls

- Signage is being revised for DHRA and DREA postings

- Installation of Gate for HP control of Emergency Personnel Hatch

HP Departnlent Challenges and m ..

m-1 PLE T Improvement Opportunities SelfAssessment

- ALARA Program assessment in January 1998

- Participation in Assessments at other plants

- Increase number of Self Assessments in HP Area Contamination Control

- Conditional Release Program revised, adding additional signage Health Physics Facilities and Equipment

- RCA Tool Room, Auxiliary Building 1974'-January 1998

,emnated Access Control Applications - February 1998

- RAM Storage Building - February 1998

- Laundry and Decontamination Facility - March 1998

- Remote Monitoring Task Team - July 1998

M F,y Chemistry and Radwaste Department

= Challenges and Improvement Opportunities

?n?""

SelfAssessments Chemistry Tecimician Fundamentals Knowledge Housekeeping Ownership PASS Performance Sustained Radwaste

• ^'"""b"i" # 7 performance In-line Gamma Spec 94 %

FSAR Review and In-Line Boron 99 %

In-Hne Dissolved H2 87 %

Procedure Revision

. . Grab Sampler 89 %

Inillative Overall 99 %

'l Refuel Outage 9 h""

ETl Scope Schedule Radiological Considerations Shutdown Chemistry

,,,,,,,,i.-,----mu--.. ,

Refuel 9 Scope YtM*"

S/G nozzle dam after fuel offload New refuel machine Replace B RCP Motor and pump internals 100% ECT of 4 S/G Electro-sleeving tube repair Safety train work 40 Design Changes implemented

Refuel 9 Schedule

.amn Ys??"*

Duration 28 days Shutdown to Mode 5 - 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> RCS Clean-up post H2O2 add - 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> S/G ISI and repair- 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> Fuel offload 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />

_ _ -------c ~

u Refuel 9 R.adiological Considerations h?**

- High Noble Gas Levels due to Failed Fuel Potential Iodine Spike after Shutdown

- Potential High Particulate Levels and Associated Hot Spot and Contamination Control Concerns Radiation Levels may be much higher than in the past due to magnitude of AOA

- - . . . - .. gu

w x Rediel 9 Shutdown Chemistry a

??nY' De-lithiate RCS Elevated H2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in acid reducing conditions Chem degas and H2O2 addition Clean-up prior to securing RCPs Flood up target 0.05 uci/cc Co-58 and 0.01 uci/cc I-131 Lessons Learned from other plants eg.

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