ML20009C271

From kanterella
Jump to navigation Jump to search
Process Control Program for In-Container Solidification of Concentrated Liquid Waste & Filter Sludge.
ML20009C271
Person / Time
Site: Oyster Creek
Issue date: 07/07/1981
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20009C264 List:
References
351.28, NUDOCS 8107200422
Download: ML20009C271 (16)
v • d • e


Text

Mle EEEEEE UJ Jersey Central Power ;;o: g ;g;g

& Light Company ATTAONENT I l l

PPOCESS CONTROL PROGRAM FOR IN-03NTAINER SOLIDIFILATION OF '

CJNCENTRATED LIQUID TASTE )

I AND FILTER SIL'DGE FOR OYSTER CREEK NUCLEAR GENEPATIIG STATION USING Hittman Nuclear & Developnent Corporation Portable Solidification Systen i

Title Page Revision No. ! Date Process Control Program for In-Container Solidification of Concentrated Liquid T 0 7/7/81

a n
  • c aM Filter sl udge -

8107200422 810713 DR ADOCK 05000219 PDR

1 .

Proc. No.351.28 i Rev. O, 7/1_0/81 i

. TABLE OF CONITNTS i

i Page

! 1.0 Purpose 1

~

2.0 Collection and Analysis of Samples 1 3.0 Test Solidification and Icceptance Critela 3 8

i i

1 1

1 1

1 1

1 l

s i e I

I i i i

i i

i TITLE RAGE REV1SiON NO. DATE I-i Precet.s Control Program for In-Container Solidification of Concentrated Liquid i I

Waste and Filter Sludge O 7/7/31 i

k

  • -- - e--, , r-,.,-- , , - , - - - - - , . . ,,,,n.,n.n-,nnn,.mm m, man.,-v,-,- ,- , .,,,,,,r -,r..-v.ww.,-, - - , , - , - .

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

Proc. No. 351.28 Rev. O, 7/10/01 1

4 e

I LIST OF EFFECTIVE PAGES_

i t

i Page Revision No. Date i

T 0 7/7/81 1 0 7/7/81 ii 0 7/7/81 1 0 7/7/81 2 0 7/7/81' l 3 0 7/7/81 i 4 0 7/7/81 4

4 i

i I

i 1

i r

t 1

l r

(

  • I i I l

l i

i l TITLE PAGE REVISION NO. DATE __

i Process Control Program for In-Container ..

11 0 7/7/81 i hOsk b b#hkTEe SgggggntratedLiquid I

L

_m. _.= _ ____ _ .. . _ _ _ _ _ _ _ ~ _ __ ._ _ _ _ _ _ - - -

. I l

Proc. No. 351.28 f Rev. O, 7/10/81 l

1.0 PURPOSE l i

, 1.1 'Ihe purpose of the Process Control Progrant (PCP) for the solidification '

j l

i of Concentrated Liquid Waste and Filter Sludge is to provide a program which will assure a solidified product with no free liquid prior to 4

transportation for disposal.

1.2 'Ihis document shall be considered cmplete only when used in concert i

with the Pittman Nuclear and Develognent Corporation and JCP&L procedures

~

for waste solidification. This PCP provides for detentdnation of the 4

range of weeptable ratios of waste, additional water (if required) ,  ;

cenent and additive that will result in an acceptable product for transportation and burial. A range of the ratio of cement and additive that must be mixed with the waste to achieve acceptable solidification are determined in test colidifications. Assurance that quantities of canent and additives in this range are actually mixed with the waste is covered in Operating Procedure 351.28 Solid Rad Waste Operating

Procedure Using Hittman Ccment Solidification System. A Waste Solidificatior.

Data Sheet will be prepared to document this information for every test solidification.

l 2.0 COILEcrION AND ANAIESIS OF SAMPLES i

2.1 General Requirements

, 2.1.1 As reqaired by the Radiological Effluent Technical Specifications i

for Ph3's and BWR's, the PCP shall be used to verify the

{ solidification of at least one representative test specimen

{ frca at least every tenth batch of each type of wet radioactive waste form (e.g. , bead resin, filter sludge, concentrated liquid waste, etc.) .

1 I TITLF '

F%GE REVISION NC. DATE _

Process Control Program for In-Contain 3r Solidification of Concentrated Liquid 1 0 7/7/81 uncro n-A vi3 tov ny,A~o .

Proc. No. 351.28 L Rav. O, 7/10/81 4 2.1.2 For the purposes of the PCP a batch is defined as that quantity of raw waste to M transferrec to a disposable

! liner to fill the liner to the predetermined waste level.

2.1.3 If the initial test specimen frm a batch of waste fails to solidify then representative samples shall be collected from the tank frm which a batch is taken until samples for three (3) consecutive batches deconstrate solidification.

'Ihe Process Control Program provides for nodification of test rtoportions of waste, cement, and additive required to j

assure solidification of subsequent batches of waste.

. .2.2 Collection of Samples 2.2.1 Waste samples shall be collected.

2.2.2 If the contents of nore than one tank are to be solidified in the same liner then representative samples of each tank should be drawn. 'Ihe samples should be of such size that when mixed together they form samples of standard size for i

performing a test solidification. If the contents of a particular tank represents x% of the total waste quantity to f be solidified then the sa:rple of that tank should be of suc.h size to represent x% of the ccuposite samples.

2.3 Waste Solidification Data Sheet 2.3.1 A Waste Solidification Data Sheet shall be maintained for each test sample solidified. The waste Solidification Data l

1 f Sheet will contain pertinent information en the characteristics of the test sample solidified so as to provide a basis for achieving the solidification of subsequent batches of similar TITLE PAGE l REVISION NO. I DATE Frocess Control Program for In-Container Solidification of Concentrated Liquid waste and Filter Sludae 2 0 7 /7/s1

[

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

Proc. No. 351.28 Rev. O, 7/10/G1 wastes without retesting. We ccmpleted Data Sheet will be filed in the Document Control Center.

3.0 TEST SOLIDIFICANON AND ACCEPTANCE CRITERIA 3.1 Test solidification 3.1.1 An initial test solidification for both concentrated liquid waste and filter sludge were performed by obtaining a sanple of waste, conditioning the waste and mixing the waste with specified anounts of cement and additive. Wese test solidifications each yielded a solidified product which met the acceptability criteria of Section 3.2.

3.1.2 Subsequent test solidifications will provide a data base to cover the range of waste compositions encountered by operation of the process systars. Waste sanples will be analyzed to ensure that their characteristics fall within the range for which test solidifications have been performed.

3.1.3 Ccilecting, conditioning and nitxing of the waste with canent are controlled by Operating Procedure 800.

3.2 Solidification Acceptability W e following criteria define an acceptable solidification process and process parameters.

3.2.1 The sample solidifications are considered acceptable if them is no visible or drainab?e free water.

3.2.2 he sample solidifications are considered acceptable if upon visual inspection the waste appears that it would hold its shape if roToved fran the beaker and it resists penetration by a rigid stick.

TITLE l F%GE REVISION NO. DATE Process Control Program for In-Containbr Solidifi WasteangagonofConcentratedLiquid 3 lter Sludce O 7 /7 /o1

_ _ = - _ . -_ . . . _.

-. . . - . = . ., -. . - , . _ _ - . - _ . .

. o Proc. No. 351.28 Rev. O, 7/10/81 3.3 Solidification thacceptability 3.3.1 If the waste fails any of the criteria set forth in Section

3.2 the solidification will be termed unacceptable and a new solidification procedure will be established.

3.3.2 If the test solidification is unacceptable then the same

' test procedures must be followed on each subsequent test of the same type of waste until test samples for each of three consecutive batches are solidified.

i i

u l

t i,

l i

TITLE '

PAGE l REVISION NO. DATE Process Control Program for In-Container l Solidification of Concentrated Liquid I wanto and Pilter Sludce 4 l 0 7/7/81 m ,y-, ..--,,,_.-,-,,,-_,,,,---,r-a

,r..,,rn.,.e,.-n.en~,,,.,r,,-.wn.. . . . _ . . . - . , , , . . . . . , . . . . , . . , - - - - - . , . ~ -

ATTACINENT II SAFE 1Y EVAulATION FOR PORTABIE RADWASTE CEMENT SOLIDIFICATION SYSTEM

1. Title - Portable Radwaste Solidification Systs using the Hittman Ntricar and Develognent Corporation Portable Solidification Systm.
2. Purpose 'Ihe purpose of this modification is to provide a Oment Solidification Syst s to process concentrated liquid waste and filter sludge in the New Radwaste Building storage area. 'Ihe systs is being installed to satisfy new site disposal criteria at Barnwell, South Carolina. 'Ihe liittman Nuclear Developnent (brporation In-Container Cement Solidification Systs is the basis for this modification.
3. System Affected A. Radwaste Solidification Systm B. Service Air Systm
4. Drawings Reference Ekluignent Arrangement (Attached as Figure 1)

Reference Flow Diagram (Attached as Figure 2)

'Ihe P&ID for the New Solids Radwaste Systs which interfaces the proposed nodification is depicted in the Hittman Nuclear and Develognent Corporation Drawing H615-5-003, Rev. D, Sheets 1 and 2.

5. Docunents 5.1 Special Operating Procedure, Radwaste Solidification Systm - Hittman Nuclear & Develognent Corporation Portable Cment Solidification Systs, by Plant Operation Department.

5.2 JCP&L Procedure 351.11, " Packaging Radioactive Waste for Shipment to Offsite Burial Site."

5.3 JCP&L Procedure 351.4, " Solid Radwaste Operating Procedure."

6. Effect on Safety 6.1 Doctznents Defining Safety Function 6.1.1 UDSAR 6.1.2 NRC Regulatory Guides 1.21, 1.26, 1.29, 1.30, 1.32, 1.143, and 8.8.

6.1.3 10 CFR Part 20, Part 50, and Part 71.

6.2 Description of System Related Function Since the Radwante Systs is not necessary to assure the integrity of the reactor coolant pressure boundary, to shutdown the reactor and maintoin it in a safe shutdown condition, or to prevent or mitigate the conseg e nces of accidents which could result in offsite exposures, it has no safety related function during plant operation.

6.3 Effect of Proposed Modification on Syst s Safety Belated Function Since the modification is for a non-safety related syst s as described in 6.2, it will not alter the safety function of the plant or reduce its margin of safety.

%e following areas are evaluated for the proposal nodification.

6.3.1 System Performance Performance of the existing system will be inproved because of the following.

A)  % e Portable Solidification Syst s will provide a solidified product acceptable for disposal at the Barnwell facility which meets current regulations.

Significant volume reduction is afforded over current shipnents in that the entire contents of both Radwaste Holdup Tanks SL-T-3A and 3B should be accomnodated in a single HN-600 sized liner. With two HN-600 sized liners stacked in a HN-100 cask for shipnent, there will be a volume reduction realized fr m current practice by a factor of four (4) .

B) Processing will take place completely in the liner storage area which is designed for waste shipping liner handling while providing full radiation protection for operating personnel because of the new concrete shielded

< cubicle and access way frun the process aisle. Within the " bathtub," this location will contain any spills.

W e Hydraulic Mixing Head Drive Assembly will be manually placed on the waste shipping liner for radwaste processing to proceed. We Hydraulic Mixing Head Drive Assembly will extend thrmgh the port in the process shield cover.

Radiation protection for operating personnel is afforded by the new concrete shield walls and cover plug.

Protection frm radiation frun stored liners is provided to personnel as they traverse the access way frm the existing process aisle to the new cubicle where processing will be performed. Also, a 13 foot high concrete shield wall will protect persc<mel atop the process shield cover as they handle tN Hydraulic Mixing Head Drive Assmbly.

A penetration is required to convey c ment from the cement hopper into the process area. %e penetracion for the c ment feeder will be sealed to isolate the process area frm the environment. Contaminated air will have no path fr m the process area to the environ-ment except through the cement feeder when the cment hopper and cement feeder are apty. However, during processing, the waste shipping liner will be at a negative pressure (because of the dust collector) and air flow will be frm the cment hopper into the waste shipping liner. When processing is cortpleted, a slidegate valve on the cment hopper discharge, and a ball valve on the Hydraulic Mixing Head Drive Ass m bly seal the cement feeder frm the process area.

C) W e existing waste shipping liner and cask handling and loading procedures are cmpletely cmpatible with the future Interim Solidification Systm. %e truck bay in the New Radwaste Building will not contain any cmponents of the Portable Radwaste Solidification System and will, therefore, have unrestricted availability for transportation operations.

6.3.2 Seismic Classification h e system is classified as non-seismic.

6.3.3 Pipe Whip Protection Protectimi from pipe whip is not provided because of following conditions which are met as per the BTP APCSB3-1:

A) We service tmperature and design pressure of the system is less than 2000F and 275 psig, respectively.

B) The piping system will be physically isolated frm structures, systems, or cmponents inportant to safety'.

C) In the event of a single break, the unrestrained pipe movement of either end of the ruptured pipe in any possible direction cannot inpact any structure, system, or component important to safety.

6.3.4 Environmental Protection he modification will minimize leakage to the enviroment because:

A) Waste and chemical aMitions into the liner are nonitored and indicated continuously by the operator. Invel indicators within the liner provide visual indication of critical levels.

Quantitites of waste and ch mical addition to the liner will be known prior to operation.

Positive overflow protection will be provided by a high level indicator which will autmatically stop radioactive waste flow to the Hydraulic Mixing Head Drive Assmbly.

Cment addition will be an exact predetermined volme placed in the c ment hopper to preclude overfilling of the waste shipping liner. (If any overfilling of the waste shipping liner would occur, it would be contained by the QASL Radwaste Builddng Seismic Structure.)

B) Release of cment dust to the akosphere will be limited by the use of an HN&DC Dust Collector which will draw a r:egative pressure on the cement hopper during the hopper filling operation.

6.3.5 Missile Protection Since the system will not be inportant to safety, the protection against dynamie effects of missiles, pipe whipping, and dis-charging will not be required.

6.3.6 Fire Protection Not affected. No significant cmbustible materials are present in the Hittman Portable Cement Solidification Systs, nor are any cmbustible materials used in the process.

6.3.7 Natural Phencmena Protection Since the system will not be inportant to safety, the protection against the effects of natural phenmena such as earthquakes, tornados, hurricanes, and floods will not be required.

6.3.8 Single Failure Criteria Not a consideration, a the systs is not safety related.

6.3.9 Separation Criteria Not a consideration, as the system is not safety related.

t 6.3.10 Electrical Separation Not a consideration, as the system is not safety related.

. . .. . _ _ _ _ =- . -__.-_---_-__ . . . .

J 6.3.11 Material Canpatibility All materials are specified to be ocmpatible with the intended service. The waste lines will be rated for 300 psi service to provide adequate protection for this application.

7. Plant Procedures Requiring Change 7.1 JCP&L Procedure 351.4, " Solid Radwaste Operating Procedure"
8. Conclusion The proposed modification will not adversely affect Nuclear Safety for reasons stated herein and is, therefore, concluded not to constitute an un-reviewed safety question as defined in 10 TR 50.59(a) .

- - - - - -- , .----..-,w. , . . , --m,, ----e ..-. . - - , - ,-e -- - -- . .-- - - . e ,-- ,.-

SAFMY EVAIDATION SUbHARY SHEE7T

1.

Subject:

E.T. 328.13-5 - Portable Hittnan Solidification Systm

2. Personnel Responsible for Safety Evaluation:

L. Eutland (B&R)

R. A. Pinelli R. M. Ashby D. N. Grace

3. System (s)/ Subsystem (s)/Conponent(s) Affected:

Nmf Service Air System, Radwaste Solidification System

4. Conclusion of the Safety Evaluation:

Proposed modification does not constitute an unreviewed safety question as defined in 10 TR 50.59(a) .

5. Technical Specifications Affected:

None

6. FDSAR Sections Affected,:

None

7. A. What plant proceduret were reviewed in this evaluation?

JCP&L Procedure 351.4, " Solid Padwaste Operating Procedure" B. What changes, if any, to the procedares are recomended?

Added a new waste line to the SL System to route wastes to the portable system. Also changed the operation of valves SL-AOV-025A and B.

8. Recomnendation:

None

9. Omnents:

None Safety Evaluation Subnitted by:

?

//;

~

(/' ,

~ _

Date: $*/$~$l

i2 3 2a $

IL LII O t 0 5 ui ,

~ *4*

m ul h Q \L ^HQ W 2s

~

E $E

~

y

> 4- O -

i fl p-  %  %.

c l . , u .

e =e m

~~

\z L - - --

,,9 , & j ( ' f

Ng ,

x

,2, g 3-4 N (th g n U j!r \ u d x d 4>b

<ta a e g ,/ .a N "/ \ >

/ . . ..

x -

% h.

q _l g N  ;.

.u ll-O th i'

s z l:

v gJ -

O '

F J J

Il JJO - ,

tL j 4 0{-4 o -i I a_g te 2@  :

1 O ul J n.

o U! J 1- z W p. 4 tb  ! !

i--

... 4 6

W am mes G #

b-

9

+- .- - . . . _ _.m .

G

, ~> 0 y a .*

8 .) 0 4 LD e4 I9 ~

89 .

o

) _

o0 --

<b . . .

sJ a

/5h er h

2 .

i Vo ay ~-

Wg '2 c -

2 :* ~

l*u)5 5? . .

I I

N

~ ~ -- Q - - - -

a,

. . . . . . . p i  !

q  ;%

G '

jg q i~ /g

  • U - ,

. . . . . L 1 W o VI * #

_! 5 . . . . _ _

4 4 -  % ..

E

)

3 u w

-_ _. _ . 1, . -  %

%n]-.- . -

ig , ,

y S a 05 co .s -

$,4 .

e%q;/ k I

,,, (

e s ]g M . .

-4 4.m----"

p

,u.

b a

'o o

, N e to R Th k '

Nh\\ \

0 -- "i, / //// ///,

Q~g% $ w e-u .-

4 d  ? _J y 6 5 7 2 3

~ '

?. 6 O

n1 ,

+ d o -- ~ --- -

O 2

. jli. 9J zg,

  • no 0h g

^~

E t, os bu b,

-- . CD us g ,

t s -

3 s

.- ,-r..+ + -. - - , . , .-. , . - - - - - - - , . - - - -

  • e ,

9 qw-t u  %

N

\

D

\ Q A

. R 9

? -

I 5 ws 4th -n. r " E (v1got

- -tO!

$ $ 3 g To C $ k 55 ep i Ii j .yI. d~~ (wg 2 2 Psyw-I i'

44 C

d =

a -

b Y- $ SC sn L k<c" #

a h*

S .2 -

a3 o ?J < od ~

I o.

<w 3 l O r, J gOg d~

8& 0f< c T*

M

  • G]d -

O 4 l- . {R

?

' .s e* E dD S ,

. ez z-n.1 m. ,g. ,

+ e. z - -

g 3 d 6

,_ g g

.- , s 3 a s 4

t 2

  • )

kt J

)

l

'\o* .f, --J = 3 1

-2 s -

33[ a l $ .a s z: W s,s O .,

c- e4 l

c.

g < i

  1. $ E
  • 3 7, *f -

Fi l

e,()c

? -

c.

c o 50;

,' c c n e-

> - j w

  • w g a7,h a _-1,g 2% L [ b n f. y  ;, n es.vmop

,c<

q ' ' 3g- W1 4 3 g 3os w f,

f(

3o, o' dd z, g4f' -

% mp,3 l

e====ee** .- = = ~ * , - -

t-

Retrieved from "https://kanterella.com/w/index.php?title=ML20009C271&oldid=2474849"