ML19332C891

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Rev 5 to West Valley Demonstration Project Operation Safety Requirements Document TR-IRTS-5, STS Process Limits.
ML19332C891
Person / Time
Site: West Valley Demonstration Project
Issue date: 11/09/1989
From:
WEST VALLEY NUCLEAR SERVICES CO., INC.
To:
References
26088, TR-IRTS-5, NUDOCS 8911290142
Download: ML19332C891 (13)
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Text

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Dam ' -November 9, 198 co;xa ctERK q.js cc:a r c: tex -

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' Sdi'" Contro11od'Distrib T P OSR, Volume 'xgat onal~ Safety.

'R$quirements Manual e-Ti ' Distribution cc: MRC :- 0360, 0658,1350,1360 Attached are the following revisions to the VVDP OSR, Vol ms VI -

Operstional Safety Requirements Manual, which has been assigned to you under controlled distribution: ,

o 'The latest Table of Contenti,.

o .TR-IRTS-5, Rev. 5 - STS Process Limits Please replace the previous-revision and table of contenes with the attached.. ,

Copies-of procedures made from a controlled document are to be marked NJLLED before distribution.

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To acknowledge-receigt of these controlled copies, please sign, date, 1- and return the attached controlled copy distribution sheet by November 23,.1989, to:

Ms. L. E. Domes, Records Management West Valley Nuclear Services Co. , Inc.

P.O. Box 191 West Valley, New York 14171 0191 For your convenience, a return address has been placed on the reverse side of the controlled copy distribution sheet; please fold, staple, and place in the mail.

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L. E. Domes, Word Processor Records Management f West Valley Nuclear Services Co., Inc.

Approved: $. t nA_

C.M.Schiffhher, Supervisor f, ,O Attachments: As stated at, ave.

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,f s OPERATICIIAL SAFETY REQUIREIGNTS/ TECHNICAL REQUIREMENTS ,

i' WEST VALLEY DEMotiSTRATION PIKUECT

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- WDF Former WDF, NFS Identifier- Rev. Title / Contents Identifiers-OSR-GP 1 1 WDP Airborne Radioactivity M.11.5.2.4.

Release Limits WDP 4.1 OSP. CP-1

- OSR/TR-GP-1 OSR-GP-2 1 Radioactivity Content of Liquid- M .11. 5. 2. 5. -

Effluents Released from the WDP -WDP 4.2 OSR-GP 2

' OSR/TR GP-2 OSR-CP 3 3 Building and Vessel Ventilation M.11.5.2.1.

L- Sy' stems Operability NFS 5.3, ,

! STS 1.1, 1.2, l' CSS 4.1, 4.2, SRF 8.2, LWTS 5.1-l' M.11.5.2.7.

WDP 4.14 LWTS'5.2, l4 %. NFS 6.5, l ;V-STS 1.2, CSS 4.2 M 11.5.2.6. ,

TVS 3.0 M.11.5.2.1 [

i VF 2.2, 2.3 OSR GP-3 l; OSR/TR-GP-3

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1 OSR-GP-4 1 Effluent and Environmental M.11.5.2.1.B.X Monitoring (WDP 5.1)

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OSR-CP-5 2 WVDP Emergency Power Requirements M.11.5.4.3.

NFS 6.4 t

M 11.5.2.1.D STS 1'.3

+ M.11.5.2.1.G CSC 4.4 OSR GP-5 OSR/TR-CP-5 TR-GP 6 .1 Storage Requirements for M.11.5.2.1.J

'+ Low-Level Waste LAG-1, LAG-2 M.11.5.2.1.I SRF'8.4 TR-GP-6 OSR/TR-GP-6 OSR-GP-7~ 1 Criticality Safety for Liquid M.11.5.2.2. '

Transfer WVDP 4.3 OSR GF-7 OSB/TR GP-7

(, TR-CP 1  : Water Activity Alarms M 11.5.4.1.

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NFS 6.9 TR GP-8 OSR/TR-CP-8 L TR-GP-9 1 Control of Plant Equipment- New H Function and Configuration TR GP-9 L OSR/TR-GP-9 OSR-GP 10 1 Airborne Effluent Monitoring M.11.5.4.4.

L System Operability hFS 6.5 STS 1.1, 1.2 l'

l CSS 4.1' OSR GP-10 l~

OSR/TR-GP-10 OSR-GP-11 2 Storage Canister Loading and M.11.5.1.2.B Spacing AFM 6.0 STS 1.4, CSS 4.3, LWTS 5.3 l OSR GP-11 OSR/TR-GP 11 1

r[ BLB0578:ENG-392 DATED: 11-09-89 ,

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.;s. UVDF' Former UVDP,' NFS Identifier Rev. . Title / Contents Identifiers ,

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j- OSR CP 1 Fissile Material Limits and M.11.5.1.1.B Requirements for Waste Packages CPCRIE 9.1, 9.3,-STS 1.4, TRU-9.1, 9.2, LAG 1, LAG-2 ,

M 11.5.1.1.J. .-

RER 1.1

- M 11.5.4.1.J RER 1.3  :

M.11.5.6.1'J r RER 1.2 OSR GP-12 OSR/TR-G?-12

. TR-GP 13' 1- Evacuation Alarm and Emergency New Paging System Operability TR GP-13 )

OSR/TR GP-13  !

TR-GP-14 1 WVDP Meteoro1rgical System New ,

Operability TR GP-14 L/"'N1 OSR/TR-GP-14 h) TR CP 15 1 Fire Brigade and Emergency New Response Team Training TR GP-15 3 OSR/TR 'P-15 TR-GP-16 1 Plant Fire-Protection Systems New -

TR CP-16 4

OSR/TR-GP-16 OSR-IRTS-1 2 Maintenance of Carbon Steel M.11.5.2.6.

High-Level Waste Tank Integrity NFS 4.12 M.11.5.4.2.

NFS 6.3 ,

OSR IRTS-1 OSR/TR-IRTS-1 TR-IRTS-2 2 Control.of CSS Recipe for M.11.5.2.2.G Decontaminated Supernatant CSS 4.3 TR IRTS-2 OSR/TR-IRTS-2 . .

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UVDF. Former WDF, NFS '

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Identifier Rev.- . Title / Contents Identifiers-OSR IRTS 3 1 Maintenance of Spara 2LW M.11.5.2.3. l

. Storage Capacity . NFS 5.4

- OSR IRTS-3 OSR/TR-IRTS-3

= TR-IRTS 4 3 Depressurization of STS for: . M.11.5.6.1.D Maintenance TR IRTS-4 OSR/TR-IRTS 4- ,

'TR IRTS-5 5 STS Process Instrument Limits M 11.S.1.1.D

- STS 1.4 TR IRTS-5

-0SR/TR-IRTS-5 TR-IRTS-6 1 LWTS Manifold Control New

.- TR IRTS-6 OSR/TR-IRTS-6 l

TR-IRTS-7 4 Sampling and Analysis New Requirements for Tank 5-0 153 - M.11.5.1.1.H LWT3 5.3 TR IRT.1-7 L - -

OSR/TR-IRTS-7 l-1 3

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TR-IRTS-8 3 Sampling and Analysis New l Requirements for Tanks 5 D-15 TR IRTS-8 I' Al and A2. OSR/TR-IRTS-8 ,

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l BLB0578:FNG-392 - 4- DATED: 11-09-89 1

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TR-IRTS 5!  :

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RECORD OF REVISION

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! PROCEDURE k- / . 3 11f there are changes to the proceoure, the'revisior. number increases by one'.

-These charges are indicated in1the left margin of the body by an arrow (>) at ,

.the_ beginning of the ' paragraph ' that contait4s a change.

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Example:

>: The arrow-in the margin indicates a change.

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Description of Changes Revision Page(s)On Dated

'Rev. No.

O. Original Issue All

' 1' Dated 5/20/88 All -

1- Engineering Release - N/A 08/88.

Per ECN Ne. 2607-& 2607A 2 All 09/88

+ (,,) ((D 3' Per ECN No. 2845 All 02/89 4 Per ECN No. 2978 All 06/89 <

5 Per ECN No. 3174 1-3 11/89 1

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  • WV-1807, Rev. 1 i MSS 0678:ENG 392

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TR-IRTS-5

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-i-f3'. e -TYPE: l > TITLE: STS Process Lir,its l NUMBER: IRTS-5

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, Tech. Regan't. [X]l l 1 I

-CRITERIA: 1. Waste produced si.all meet the qualification of the Process Control Plan.

->- 2. STS shall meet the design criteria of a Decontamination Factor-greater than 1,000 for Cs-137 if the waste is to be sC.idified in the CSS.

>' 3. STS may transfer liquid from 3D-1 to LWTS for volume reduction if the

-volume reduced liquid is returned to the waste tank farm (SD-2).

UNACCEPTABLE EVENTS: 1. Failure of the STS to produce a decontamination faceor of 1000 for Cs-137.

I -1 I Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED LCO l j l LCS l l l

}/ Surveillance Regan't.-l l 'l l . Q]. I I I l l 1 l' Tech. Requirement X l Critique IDOE-WPO CONTROLLED I

I I I Operating Limit l l lWNS CONTROLLED j IMPLEMENTIF1 PROCEDURES:

-SOP 50-23 S0P 50-36 SOP 50-42 SOP 50-33 SOP 50-37.

SOP 00-13

> SOP 71 l-(

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TR IRTS ,

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, TEC~BtICAL RE/QOIREMENT j

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>l SUPERIIATalfT TREATHENT SYSTdi PROCESS UNITS I l

APPLICABII.ITY L:

> Requirement No. 1 applies to the maximum concentration of Cs 137 permitted in the

' discharge of the final ion exchange column in the STS. Requirement No. 2 applies ,

to the maximum Cs 137 concentration permitted in the transfer of decontaminated.

.supernatant from~8D-3 to the LWTS. Requirement No. 4 applies to liquid that is sent to LWTS for volume reduction and is ultimately returned to the WTF.

L OEJECTIVE

> To provide a means to monitor the decontamination factor for Cs-137 prw'ded by the STS system and to assure that supernatant transferred eventually to CSS is decontaminated by a factor of at least 1,000 for Cs-137.

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> ' DEFINITIONS 1

> STS processes three kinds of liquid.

> 1. Decontaminated Supernatant - liquid from Tank 8D-2 (either diluted or undiluted) that has passed through the STS ion exchange system.

> 2. Decontaminated Supernatant plus Flush - a final process step for STS operation which uses liquid from Tank 8D-1, or water, to push residual supernatant through the ion exchange columns. Typically 10,000 gallons-of Tank 8D-l' liquid or 6,000 gallons of water is used to flush the columns.

> 3. Liquid from Tank 8D water condensed from vapor generated in Tank 8D-2 and water generated from various STS operations. This 11guid has a relatively low salt concentration and a constan::1y increasing cesium concentration (as loaded zeolite is dun;-d to Tank 8D-1).

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MSS 0678:EhG-392 Page 1 of 4 m

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- TR.IRTS 5' I

Rev 5

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~ 1. LIQUID RADIATION MONITOR 50RE034 SHALL BE OPERATIONAL AT ALL TIMES TO ANA'.,YZE i' CONCENTRATIONS OF RADIOACTIVE MATERIALS IN DECONTAMINATED SUPERNATANT PR6 DUCT TRANSFERRED TO TANK 8D-3. THIS MONITOR SHALL BE CAPABLE OF BEING CALIB'JTED

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TO A-LEVEL CORRESPONDING TO 10 PERCENT (OR LESS) 0F THE Cs-137 TRANSFEL LIMIT ]

(I.E., s C.55 pCI/ML). THE MONITOR AIARM POINT SHALL BE SET SUFFICIENTLY LOW TO ASSURE THAT CONCENTRATIONS OF Cs 137 IN EXCESS OF 5.5 pCi/mL bEING TRANSFERRED TO TANK 8D-3 WILL CAUSE AN ALARM. AUDIBLE AND VISUAL AIARMS SHALL BE PROVIDED IN THE STS CONTROL P00M.

2. TRANSFERS OF DECONTAMINATED SUPERNATANT AND FLUSH WATER FROM TANK 8D-3 TO THE LWTS SHALL BE LIMITED TO A MAXIMUM CONCENTRATION OF Cs.-137 CORRESPONDING TO A DF OF 1,000 AS DETERMINED FROM TABLE 1. +
3. RESPONSES TO ALARMS SHALL BE ACCORDANCE WITH SOP 50-33.
4. " TANK 8D 1 LIQdID", AFTER PROCESSING THROUGH STS, MAY BE ROUTED FROM TANK 8D-O~>

V 3 TO THE LWTS FOR VOLUF't REDUCTION. THE VOLUME REDUCED LIQUID WILL BE L RETURNED TO TANK 8D-2. ADMINISTRATIVE CONTROLS SHALL BE USED TO ENSURE THAT h THIS LIQUID IS NOT TRANSFERRED TO CSS. AT NO TIME MAY THE ACTIVITY CONCENTRATION IN THE VOLUME REDUCED LIQUID EXCEED 50 pCI/ML. A i

DECONTAMINATION FACTOR IN STS SHALL NOT LIMIT TRANSFERS OF " TANK 8D-1 LIQUID" t  :

i FROM 8D-3 TO LWTS (REQUIREMENT NO. 2 0F THIS TR). TR-IRTS-7 DOES NOT APPLY l TO TANK 8D-1 LIQUID PROCESSING. TANK 5D 15B SHALL BE SAMPLED AND THE i l

l- ANALYTICAL RESULTS USED TO CALCULATE THE MAXIMUM VOLUME REDUCTION THAT CAN BE l ACHIEVED.

SURVEILLANCE REQUIREMENTS l

1. S,01PLING'AND ANALYSIS SHALL BE IN ACCORDANCE WITH THE STS SAMPLE PLAN-

[

l CONTAINED IN SOP 50-42.

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2. CALIBRATION FOR RAD MONITORS SHALL BE PERFORMED EVERY SIX MONTHS.

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b MSS 0678: ENC-392 Page 2 of 4

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.>. 3. WHEN TANK 8D-1 LIQUID IS BEING VOLUME REDUCED, TANK SD 15A1 OR TANK SD-15A2, ,

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AS NECESSARY SHALL BE SAMPLED TO ENSURE AN ACTIVITY CONCENTRATION OF C 50 CI/ML IS NOT EXCEEDED.

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1 The STS was designed to provide a supernatant decontamination factor of at least 1,000 for Cs-137._ Technical requirement No. 2 gives the maximum acceptable Cesium concentration in Tank 8D-3 based on a DF of 1,000 from Tank 8D 2 L supernatant. This requirement sets STS product quality by placing a cesium limit, which is based on the weight frae. tion of the product, therefore ensuring an acceptable final product at CSS. DF calculatior.s for supernatant shall be based on samples of Tank 8D-3 and tank D-001, and-are used to verify STC system DF. Decontaminated supernatant with a decontamination facror less than 1,000 as -

measured at Tank 8D 3 will be recycled to Tank BD-2 for rework. Transfers from Tank 8D-3 to UWTS containing flush water shall meet the conditions of requirement No. 2 of this Technical Requirement, but the system DF calculation,-as described above, is not used for the transfer. Due to the changing feed concentrations, it is not possible to get a representative system DF while using flush water.

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> Volume reduction of Tank 8D-1 liquid may be required as an emergency response to a leak in the waste tank farm. LWTS is capable of performing this volume reduction, to an activity limit of 50 pCi/mL (UWTS Design Criteria, WVNS-DC-025, paragraph 2.2.1). WVNS will work to the design criteria limit because of the emergency nature of this action. Decontamination factor calculations and process control calculations dasigned to limit the activity concentration of waste sent to the CSS should not be applied to liquid that will be returned to the high-level waste storage tanks.

ATTACHMENTS None REF9tENCES None MSS 0678:ENG-392 Page 3 of 4

/ . . . 3

%; V TABLE 1 -TR-IRTS 5-y , _ . , ,

Rev. 5- -j a s< TABLE 9 OF CESIUM CONCENThATION FOR VARIOUS SALT FRACTIONS N ' SALT FRACTION MAXIMUM ALIDUABLE CESIUM CONCENTRATION ,

YTiF ).?

  • 0.01 0.05'-

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WI 0.02- 0.10 l

$j O.03 0.15 )

~

O.04 0.20 H 0.05 0.25 O.06- 0.30

. 0.07- 0.35 0.08 0.41 l 0.09. 0.46 ,

0.52 j 0.10

'O.11. 0.57 l

'O 12 0.63 i 0.13 0.69 0.14 0.74 o 0.15' O.80 0.16 0.86 0.17 0.92 0.18 0.98 ,

0.19 1.05

-0.20 1.11 ' '

0.21 1.17 O 22 1.24 0.23 1.30

-0.24 .1.37 P(.. 0.25. 1.44 +

- (j 0.26 1.50 l , 0.27 1.57 l 0.28 1.64 l 0.29 1,.71 0.30 1 1.78.

0.31 1.85 0.32 1.93 0.33 2.00  !

0.34' 2,07 ,

, 0.35 2.15 l 0.36 2.22 '

L 0.37 2.30 O.38 2.38 l 0.39 2.46 0.40 2.53 ,

,C C,_

(1 + 0.829 . f,)

  • f,

-Basis:

0.452 DF Where: C - Cs-137' concentration (pCi/mL)

l. DF - Cs Decontamination Factor L. f, - Salt Fraction (g salt /g solution)

Co --8D-2 Supernatant Cs-137 concentration (2150 pC1/mL)

Reference:

Letter ER Faillace to P. J. Valenti, FB:89:0074 " Transmittal of "b 'd' Calculations to Estimate CS-137 Activity in LWTS Concentrates",

date.d 04/10/89 I

MSS 0678:ENG-392 Page 4 of 4 l

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