ML20246B418

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Forwards Rev 4 to TR-IRTS-5, STS Process Instrument Limit & Rev 3 to TR-IRTS-7, Sampling Analysis Requirements for Tank 5D-15B
ML20246B418
Person / Time
Site: West Valley Demonstration Project
Issue date: 06/23/1989
From: Domes L, Schiffhauer C
WEST VALLEY NUCLEAR SERVICES CO., INC.
To:
WEST VALLEY NUCLEAR SERVICES CO., INC.
References
REF-PROJ-M-32 25667, NUDOCS 8907070329
Download: ML20246B418 (6)
v • d • e


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D. L. Bonenberger MRC - 0360, 0658, 1350, 1360 Attached are the following revisions to the WVDP OSR, Volume VI -

l Operational Safety Requirement Manual, which has been assigned to you under controlled distribution.

o The latest Table of Contents. Please replace the previous Table of Contents with th'e attached.

o TR-IRIS-5, Rev. 4 STS Process Instrument Limits o

TR-IRTS-7, Rev. 3 Samp. ling and Analysis Requirements for Tank SD-15B Copies of procedures made from a controlled document are to be marked UNCONTROLLED before distribution.

't To acknowledge receipt of.this controlled copy, please sign and date the attached controlled copy distribution sheet by July 7, 1989, to:

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

P.O. Box 191 West Valley, New York 1A171-0191 Y0 5-L. E. Domes, Word Processor Records Management West Valley Nuclear Services Co., Inc.

MD Approved N.

didt C.M.Schiffhab, Supervisor N

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Attachments: As stated above 8907070329 890623 A

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/N OPERATIONAL SAFETY REQUIRBENTSpanauuCAL REQUIREMENTS

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. WDP Former WDP. NFS -

Identifier Rev.

Title / Contents Identifiers OSR-GP-1 1

WDP Airborne Radioactivity M.11.5.2.4.

Release Limits WDP 4.1 OSR GP-1

.OSR/TR-CP-1

.OSR-GP-2 1

Radioactivity Content of Liquid-M.11.5.2.5.

Effluents Released from the WDP WDP 4.2 i-OSR-CP-2 OSR/TR-CP-2 r

l OSR-CP-3 2.

Building and vessel Ventilation M.11.5.2.1.

Systems Operability

.NFS 5.3, STS 1.1, 1.2, CSS 4.1, 4.2, SRF 8.2, LWTS-5.1 M.11.5.2.7.

WDP 4.14

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LWTS 5.2,

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NFS 6.5, STS 1.2, CSS 4.2 i

M.11.5.2.8.

TVS 3.0 M.11.5.2.1 VF 2.2, 2.3 OSR GP-3 NR/TR-GP-3 OSR-GP-4 1

Effluent and Environmental M.;1.5.2.1.B.X Monitoring (WDP 5.1)

OSR CP-4 OSR/TR-GP-4 t

BLB0578:ENG-392 DATED 06/23/89 i

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t-IC WVDP Foruner UVDP, NFS Identifier Rev.'

Title / Contents Identifiers

.0SR-CP-5 1-WVDP Emergency Power Requirements M.11.5.4.3.

NFS 6.4 M.11.5.2.1.D

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STS 1.3 M.11.5.2.1.G CSS 4.4 OSR GP-5 OSR/TR-GP-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-CP-6 OSR/TR-GP-6 OSR-GP-7 1

Criticality Safety for Liquid.

M.11.5.2.2.

I Transfer WVDP 4.3 OSR GP-7 OSR/TR-GP-7 f

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TR-GP-8 1

Water Activity Alarms M.11.5.4.1.

NFS 6.9 TR GP-8 OSR/TR-GP-8 TR-CP-9 1

Control of Plant Equipment New Function and Configuration-

'TR GP-9 OSR/TR-CP-9~

OSR-GP-10 1

Airborne Effluent Monitoring M.11.5.4.4.

5fstem Operability NFS 6.5

'STS 1.1, 1.2 CSS 4.1 OSR GP-10 OSR/TR-GP-10 OSR-CP-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 OSR GP-11 OSR/TR-GP-11 BLB0578:ENG-392 DATED 06/23/89

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Former WVDP, NFS-WVDP.

t Identifier Rev.

Title / Contents Identifiers s,,

J OSR GP-12 1

Fissile Material Limits and' N.11.5.1.1.B

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Requirements for Waste Packages CPCRIT 9.'1, 1

9.3, STS 1.4, I

TRU 9.1, 9.2, IAG-1, IAG-2 y

M.11.5.1.1.J-RER 1.1 M.11.5.4.1.J RER 1.3 M.11.5.6.1.J RER 1.2 OSR GP-12 OSR/TR-GP-12 TR-GP-13 1

Evacuation Alarm and Emergency

'Neu Paging System Operability TR GP-13 OSR/TR-CP-13 TR-GP-14.

1 WVDP Meteorological System New Operability TR GP-14

' [)D OSR/TR CP-14 TR-GP-15 1

Fire Brigade and Emergency New Response Team Training TR GP-15 OSR/TR-CP-15 TR-GP-16 1

Plant Fire Protection Systems

'New TR GP-lo OSR/1R-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 1RTS-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 1RTS-2 OSR/TR-IRTS-2 i

BLB0578:ENG-392 DATED 06/23/89

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UVDF Former WDP, NFS j

Identifier Rev.

Title / Contents

' Identifiers OSR-IRTS-3 1'

Maintenance of Spare HLW M.11.5.2.3.

Storage Capacity NFS S.4 OSR IRTS-3 OSR/TR-IRTS-3

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TR-IRTS-4 2

Depressurization of STS for M.11.5.6.1.D Maintenance

-TR 1RTS-4 OSR/TR-IRTS-4' TR-IRTS 4 STS Process Instrument Limits M.11.5.1.1.D STS 1.4 TR IRTS-5 OSR/TR-IRTS-5 TR-IRTS-6 1

.LWTS Manifold Control New TR IRTS-6 1

OSR/TR-IRTS-6 TR-IRTS-7 3

Sampling and Analysis New Requirement for Tank 5-D-15B i

M.11.5.1.1.H i

LWTS 5.3

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TR IRTS-7 i

OSR/TR-IRTS-7 l

TR-IRTS-8 3

Sampling and Analysis New I

Requirements for Tanks 5-D-15 Al and A2.

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PROCEDURE If there!are changes to the' procedure, the revision number increases by:one.

. These changes are; indicated in the 'left margin of ' the body by an arrow (>) at-the beginning of. the paragraph that contains-a change.

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Date'd 5/20/88 All' 1

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l TITLE: STS Process Instrument Limits l NUMBER:

IRTS-5 w

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CRITERIA:

1.

Vaste produced shall meet the qualification of the Process Control Plan.

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2.

STS shall meet the design criteria of Decontamination Factor of 1,000 l

for Cs-137.

UNACCEPTABLE EVENTS:

1.

Failure of the STS to produce a decontamination factor of 1000 for Cs-137.

I I

I Safety Limit l

l Reporting Requirements:

l DOE-ID CONTROLLED LCO l

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Operating Limit l

l lWNS CONTROLLED IMPLEMENTING PROCEDURES:

SOP 50-23 SOP 50-36 SDP 50-42 SOP 50-33 SOP 50-37 S0P 00-13 MSS 0678:ENG-392 g

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TR-IRTS-5 6-Rsv. 4 j

TECHNICAL REQUIREMENT

.5 l

SUPERNATANT TREATMENT SYSTEN PROCESS INS 11tDNENT LIMITS

_ APPLICABILITY j

Requirement No. I 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.

OBJECTIVE i

To provide a means to monitor the decontamination factor for Cs-137 provided by the STS system and to assure that supernatant transferred to LWTS is decontaminated by a factor of at least 1,000 for Cs-137.

O 1.

LIQUID RADIATION MONITOR 50RE034 SHALL BE OPERATIONAL AT ALL TIMES TO ANALYZE CONCENTRATIONS OF RADIOACTIVE MATERIALS IN DECONTAMINATED SUPERNATANT PRODUCT TRANSFERRED TO TANK 8D-3.

THIS MONITOR SHALL BE CAPABLE OF BEING CALIBRATED TO A LEVEL CORRESPONDING TO 10 FERCENT (OR LESS) 0F THE Cs-137 TRANSFER LIMIT (I.E., :!; 0.55 pCI/ML). THE MONITOR ALARM 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 A1 ARMS SHALL BE PROVIDED IN THE STS CONTROL ROOM.

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 I

DF OF 1,000 AS DETERMINED FROM TABLE 1.

3.

RESPONSES TO ALARMS SHALL BE ACCORDANCE WITH S0P 50-33.

O MSS 0678:ENG-392 Page 1 of 4 i

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' SAMPLING' AND ANALYSIS SHALL BE IN ACCORDANCE WITH THE STS SAMPLE PIAN 4

CONTAINED.IN SOP 50-42.

2; CALIBRATION FOR RAD MONITORS SHALL BE PERFORMED EVERY:SIX' MONTHS,

_B_ ASIS 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.

J Cesium concentration in Tank 8D-3 based on a DF of 1,000 from Tank 8D-2

'supernatant. This requirement sets STS product quality.by placing a cesium

-limit, which'is based on the weight fraction of the product,.therefore ensuring.

an acceptable: final product at CSS. -DF calculations for supernatant shall be based on samples of Tank 8D-3 and tank D-001, and are used to verify STS system

DF, Decontaminated supernatant with'a decontamination factor less than.1,000 as

/

measured.at Tank 8D-3 will be recycled to Tank BD-2 for rework. Transfers from

?m) - Tank 8D-3 to LWTS 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.

i ATTACIDENTS i

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> None REFERENCES None Dd 1

MSS 0678:ENG-392 Page 2 of 4 m

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LTABLE 1!

TR-IRTS-5'

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Rev. 4 TABLES OF CESIUM CONCENTRATION FOR VARIOUS SALT FRACTIONSi

}f SALT FRACTION MAXIMUM'ALLOVABLE CESIUM CONCENTRATION

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0.05 LL j

,..4 0.02 0.10.

10.03 0.15

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0.04-0.20 0.05.

0.25 0.06 0.30 0.07 0.35 g-0.08-

'O.41 0.09~

0.46:

0.10 0.52 0.11 0.57 0.12

=0.63 0.13 0.69 0.14 0.74 0.15 0.80 J0.16 0.86 0.17 0.92 0.18 0.98 0.19 1.05 0.20 1.11 0.21

.1.17-0.22 1.24 0.23 1.30 O.24 1.37 0.25 1.44

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0.26 1.50 0.27 1.57 0.28 1.64 0.29 1.71-0.30 1.78-0.31 1.85~

0.32 1.93

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0.33 2.00 0.34 2.07

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0.35 2.15 0.36' 2.22 0.37 2.30 O.38 2.38 0.39 2.46 0.40 2.53 1

C,.

(1 + 0.829. f,)

f, j

Basis:,C 0.452 DF Where: C - Cs 137 concentration (pCi/mL) 1 DF - Cs Decontamination Factor f

1 f, - Salt Fraction (g salt /g solution)

C, - 8D-2 Supernatant Cs-137 concentration (2150 pCi/mL)

.,q Referenco: Letter ER Faillace to P. J. Valenti, FB:89:0074 " Transmittal of j

4 5,)

Calculations to Estimate CS-137 Activity in LWTS Concentrates",

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TR-IRTS-7 Rev. 3

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l TITLE:

Sampling and Analysis l NUMBER:

IRTS-7 l., (

l OSR [ ]

l Requirements for Tank SD-15B l

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Tech. Reqmn't. [X]l l

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l CRITERIA:

1.

Vaste produced shall meet the qualifications of the Process Control Plan.

l UNACCEPTABLE EVENTS: 1.

Unacceptable product in SD-15A1 and A2.

I I

I Safety Limit l

l Reporting Requirements:

l DOE-ID CONTROLLED LCO l

l LCS l

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(~'g Surveillance Reqmn't. l l

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Tech. Requirement l

X l Critique l DOE-WPO CONTROLLED I

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Operating Limit l

l lWNS CONTROLLED IMPLEMENTING PROCEDURES:

SOP 00-13 SOP 71-2 SOP 71-11 SOP 50-23 MSS 0804:ENG-392 G

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TECHNICAL REQUIREMENT f'))'

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SAMPLING AND ANALYSTS REQUIREMENTS FUE TANK 5D-15B l

APPLICABILITY This requirement applies to samples taken at Tank 5D-15B prior to evaporation of STS' process effluent (decontaminated supernatant). This requirement applies only to decontaminated supernatant processing.

OILTECTIVE To establish the param-tric limits and sampling requirements for STS-decontaminated process effluent in Tank SD-15B.

REQUIREMENTS 1.

THE CONTENTS OF TANK SD-15B SHALL BE SAMPLED TO ASSURE THAT THE FOLLOWING REQUIREMENTS WILL BE MET:

AN ESTIMATED PROCESS CONTROL CALCULATION HAS BEEN PERFORMED TO ASSURE THAT AFTER EVAPORATION TO THE FINAL CONCENTRATION OF 37 TO 41 WEIGHT PERCENT, THE ACTIVITY LIMIT C 2.30 pCi/mL Cs-137 WILL NOT BE EXCEEDED.

2.

IF CALCULATIONS IN 1 SHOW THAT THE ACTIVITY LIMIT WILL BE EXCEEDED, THEN THE WASTE WILL BE RETURNED TO THE SUPERNATANT TREATMENT SYSTEM FOR REPROCESSING.

l 3.

PROCESSING FROM SD-15B TO THE EVAPORATOR MAY PROCEED IN PARALLEL WITH THE CONFIRMATORY ANALYSIS; CONTINGENT UPON MEETING THE REQUIREMENTS OF TR-IRTS-5.

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FOR EACH BATCH OF LIQUID ACCUMULATED IN TANK SD-15B,> ANALYSES SHALL BE PERFORMED ON A' REPRESENTATIVE SAMPLE IN ORDER TO CONFIRM THAT REQUIREMENT NUMBER 1 HAS BEEN MET.

L-BASIS l'

> Concerning the TDS, in order to remain within the composition (recipe) for which i

the final waste form has been qualified, the total solids range in SD-15Al and

.SD-15A2 must be between 37 and 41 weight percent.

In addition, the Cs-137 activity must be less than 2.30 Ci/mL which is derived from the maximum allowable cesium concentration for a salt solution of 37 weight percent found in table 1 contained in TR-IRTS-5.

To assure that these criteria are met following evaporation and concentration in the LWTS evaporator, the anticipated concentration and activity in SD-15A1 and 5D-15A2 must be estimated based on measured concentrations in 5D-15B. Attachment A shows the result of the calculation used to estimate the activity when conc'entrated.

Based on data from V

campaigns 1 through 6, the activity calculated from 8D-3 analysis is acceptable for calculating final activity.

j i

> The change to allow processing of 5D-15B in parallel with the chemical analyses is based on experience in campaign nos. 1 through 7 which resulted in Cs-137 l

activities at least 3 times less than the limit of 2.30 pCi/mL see attachment B, History of IRTS Concentrate Activity. Furthermore, an upstream sample is taken from 8D-3 prior to transfer to 5D-15B in accordance with TR-IRTS-5.

The STS i

effluent is also continuously monitored by on-line-radiation monitors per SOP 50-33.

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.- AT?ACHIGNTS Attachment A: -Predicted 'esium 137-Activity at Concentration C

Attachment B - History of IRTS Concentrate Activity REFERENCES SOP 00 13. -IRTS Integrated Run Plan s.

SOP 71-11 LWTS Samplin5 Procedures O

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TR-IRTS -

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'j PREDICTED CESIUK 137 ACTIVITY AT CONCENTRATION c.

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Predicted Activity l'

Predicted Activity l

Campaign l Transfer l-Based on 8D-3

-l Based on 5D-15B

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Number l Number I (uci/mL) l (pCi/mL) 1 5

1 I

I s

1 l

1 l

9.52 E-1 l

5.83 E-1 l

2 l

1.96 E-1 l

2.28 E-1 l

3 l

3.40 E-2 l

1.87 E-2 l

l-4 l

1.87 E-2 l

4.23 E-2 f

l 1

I 2

l 1

l 2.31-E-2 l

2.11 E-2~

l 2

l 1.95 E-2 l

1.59 E-2 l

3 l

2.35 E-2 l-1.67 E-2 I

I l

I 3

l 1

l 4.05 E-2 l

3.98 E-2 j

2

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6.02 E-2 l

5.43 E-2 l

3 l

6.50 E-2 l

8.90 E-2 l'

4 l

2.76 E-1 l

1.43 E-1 l

5 l

2.56 E-1 l

2.21 E-1 l-1 I

['\\g 4

  • l 1

l 2.81 E-1 l

L/

l 2

l 6.25 E-1 l

5.84 E-1 l

3 l

7.33 E-1 l

6.66'E-1 1

I I

6 l

1 l

2.81 E-1 l

2.88 E-1 l

2 1

8.89 E-2 l

1.12 E-1 l

3 l

3.36 E-1 l

3.37 E-1 l

Predicted activity when fully concentrated to 41 weight percent'(maximum allowable).

Ag - A, x Dg x TSg + (D, x TS,',

    • SD-15B was not filled with this transfer.

Sampling was performed after

/

transfer 2.

MSS 0804:ENG-392 Page 4 of 5 l

/g &

+

TR-IRTS-7 Rev. 3 ATTACHMENT B HISTORY OF IRTS CONCENTRATE ACTIVITY at 37 to 41 weight percent ACTIVITY CAMPAIGN IAB IDG NO.

(Cs-137 pC1/mL) 1 8801605 4.8 E-1 1

8801607 2.05 E-1 1

8801831 1.82 E-1 2

8801932 6.2 E-2 2

8801963 2.69 E-2 2

8802011 2.0 E-2 3

8802094 3.64 E-2 3

8802108 5.01 E-2 3

8802159 1 05 E-1 3

8802220 1.64 E-1 4

8802345 4.0 E-1 4

8802373 5.42 E-1 4

8802611 5.85 E-1 6

8803744 2.12 E-1 6

8803754 2.59 E-1 6

8803854 2.69 E-1 I

MSS 0804:ENG-392 Page 5 of 5

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