ML20079B121
| ML20079B121 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 01/31/1991 |
| From: | WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| Shared Package | |
| ML20079B114 | List: |
| References | |
| REF-PROJ-M-32 TR-IRTS-5-DRFT, NUDOCS 9106130319 | |
| Download: ML20079B121 (7) | |
Text
__.._ ____ _ _ _- - - _ - - _-
f WVHS-SAR-004 Rev. 6, DRAFT A.4
- classroom instruction on the basic theory,. process concepts, subsystems, components and procedures which comprise the STS and SMWS processes. This t
training will be supplemented by the use of vendor prepared materials related 1
- to basic functions of valves, pumps, instruments, process controllers and/or other vendor material specific to the STS and SHWS systems. Further training reference material and information on the WVHS and Training Procedures, Temporary operating Procedures, Standard Operating Procedures, TRs/OSRs, and I
applicable Occurrence Reports will be kept in the Training Resource center.
Training and Developmunt Departmonc personnal will develop the qualification standard, training aids and perform lecture videotaping. Training will also provide instruction, tutorial activities and operator qualification guidance, j
D.1D.3.4 TRAINING CONTENT OUTLINE 1 Due to the integration of SHWS with the current operations of STS, the training program content will include STS operations, as described in l
section D.10.3.4, as well as the following e Wash water addition to Tank 8D-2 e Mobilization pump operation ,
e Tank 8D-2 solide level monitoring prior to wash solution processing 4
e OSRs Qualification Standards currently used for STS operations will be used for the SKWS. These etcndards include both knowledge and skill objectives.
Supervisors oversee the on-the-job training program which requires demonstration of the proficien les set forth in the qualification standard, continitous training on new matarial is injected into both the qualification program and the required annual requalification program. Included in this program is the ongoing job training which is specific to performance of job skills.
l RLW4284:3RH Page 233 ;
0106130310 010610 PDR PROJ M-32 P CW.
1 WVNS-SAR-004 Rev. 6, DRAFT A. 4 As required in DOE Orders 5480.5 and 5481.20 on-the-job training will continue to provide personnel with f amiliarJty in all aspects of the position. Such training will include normal procedures, emergancy actions, radiation control practicas, location and function of the pertinent safety systems, configuration control procedures and TRs/OSRs.
D.10.3.5 QUALIFICATION VEAIFICATION/ DOCUMENTATION D.10.3.5.1 EIAMINATIONS Prior to becoming a qualified SMWs operator, verification is required to ensure that the stated learning objectives and skill objectives have been achieved. Tho stated objectives will be used in the development of the following evaluation methods.
j l
i A written examination covering all aspects of the qualification program with a passing grade of 80%.
l An operational walk-through examina*. ion performed by SMWS Engineering, Training or Supervisory personnel with a passing grade of 80%.
i D.10.3.5.2 DOCUMENTATION The qualification program shall be documented in sufficient detail to permit independent evaluation of the scope of the training program. Procedures '
specific to training are f ound in WV-538, and the Training Policies and Procedures.
Documentation for each module of the training program will include identification of performance goals, and objectives.
A qualification standard will be kept for each trainee, which documents all significant steps of training.
RLW4284:3RM Page 234
. o WVHS-SAR-004 Rev. 6, DRAFT A.4 D.10.3.5.3 QUALITY ASSURANCE QA reviews operator compliance with procedures and that operators are trained to perform the activity for which they are responsible. This is done as a regularly scheduled QA function but surveillance frequency or schedule is unknown to operations personnel.
Periodic QA audits are performed on the Training and Development Department where qualification standards, training raterials, and classroom presentations are subject to survwillance. Content of training modi 4 and presentations is reviewed for compliance with quality requirements.
D.10.3.6 REQUALIFICATION DOE Orderu 5480.5 and 5480.20 state that; "Potraining and reexamination shall be regaired at least annually on all proc 6dures for handling abnormal nuclear facility conditions and emecgency sitsetions relative to the employa's assigned responsibilities, and at least every two years on all other subjects in which the fissionable material handler, operator, or supervisor is expected to be proticient."
The reexamination program will be dceigned to review yearly:
- Changes to procedures; e Modifications to equipment; e Subject matter not reinforced by direct use (e.g., fund amentals I and operation of seldom used equipment and procedures); and 1
e All procedures for handling abnormal nuclear facility conditions and emergency situations, i The requalification program will provide for maintaining current knowledge and skills of the applicabic operators. The requalification program will be conducted every two years and will include but not be limited tos l
l e Equipment and Plant Modifications; e EAne and OERe/TPe; e Operating Procedures; ,
RLW4284:3RH Pago 235 l
l
_. .._,,m _ _ _ _ _ , . . _ _ - . . _ . _ . _ _ _ _ . _ _ _ . _ _ . . - _ . _ _ _ _ _ _ _ _ _ _ _ . _
WVNS *ShR-004 Rev. 6, DRAFT A.4 e occurrence Reports, accidents, or near misses which )ccur locally ,
or elsewhere if appropriates e Changing sources of radioactivity, criticality potentials or other potential environmental hazards; e New outlooks or methods regarding the ALARA concept; and e saf ety (fire,1ersonnel injury, etc. ) .
Drills on abnormal or emergency procedurse will be incorporated into che continuing training program. The drills will be used to assess the operators know) edge of the procedures to follow in emergency or abnormal operating conditions. The drills will be as realistic as possible without endangering property or personal welf are.
l Additional information on the STS operator Trainir.g and Qualification Program can be found in McKenzie, 1986.
D.10.4 NORMAL STS/SMWS OP3 RATIONS D.10.4.1 STS/SNWS PROCEDURES The STS/SMWS will be operated usin; procedures prepared, reviewed and approved per the requircraents of the WVNS Po. cy and Procedures Manual. Procedures will be written to cover all aspects pf STS/SHWS operation. STS/SHWS Procedures (normal operations) are listed in Section D.10.3.4.2.
D.10.5 EMERGENCY PLANNING An emergeacy plan has been developed for the WVDP. This plan is described in Section A.10.5 of Volume I. operation of the STS/SMWS will not require any modification to the procedural requirements of this plan. Specific emergency response provisions to deal with STS/SMWS contingencies will be developed in accordance with the existing emergency plan.
l l
l l
l RLW4284:3RM Page 236
._________..__.___.s _
i i
l WNS-S AR-004 Rev. 6, DRAFT A.4 REFERENCES FOR SECTION D.10.0 McKensie, 1986 S. P. McKenzie, "Supernatant Treatment System Operator Qualification Program," transmitted via WHS memo ECs 86:0023, J. C. cwynar to Distribution, March 25,1986.
1
(
l f
l l
l RLW4284 3RM Page 237 l
l
o WVHS-SAR-004 Rev. 6, DRAFT A.4 TABLE D.10.1-1 Minimuru Shif t Mannino Levels f or ODeration of the IRTS operatore Shift fattaysterg 'A" "B" funervisor Enoineer STS/SHWS 2 0 1 1 LWTS 1 1 1 1 CSS 2 1 1 1 DC 2 1 1 1 I
l RLW4284: 3RM Page 238 l
l
- t. - - - - - - . - . . . . - - . - - . - - . - --- - -- - - - - - - . - -- - .-
WVNS SAR-004 Rev. 6 l
FIGURE D.10,1-1 IRTS ORGANIZATIONAL STRUCTURE i i
l President and General ;ianager i
Plant Operations Manager i
l l-IRTS operations Manager l
STS/SMWS Shift LWTS/ CSS Shift Process control Supervisors Supervisors Engineering Manager i
239
WVNS-SAR-004 Rev. 6, DRAFT A.4 D.11.0 OPERATIONAL SAFETY REQUIREMENTS The OSR section of this volume has been deleted in its entirety and incorporated into Volume VI.
RLW4284:3RM Page 240 l
WVHS-SAR-004 Rev. 6, DRAFT A.4 3.12.C QUALITY ASSURANCE D.12.1 QUALITY ASSURANCE PROGRAM Table D.4.4-1 presents safety class, service class, and quality level for the structures, systeme and components associated with the STS and SHWS and Section D.4.4 presents information on the safety classificcaions which are used in conjunction with the service classes to define the quality levels.
The criteria and procedures used to determino quality level designation and the classification of structures, systees and components are presented in detail in Section A.4.4 of Volume I.
No credible SHWS equipment f ailure is expected to result in a loss of SMWS operating capability for a period in excess of six months or a radiation exposure resultant from repair / replacement in excess of 50 mSv/y (5 rem /y) and therefore, no SHWS structure, system, or component , is designated as Service Class I.
Structures, systems and camponents assigned Service Class II are so designated since their repair / replacement could result in a loss of SMWS operating capability of one to six months and/or a radiation exposure to repair / replace of 1-5 cSv (1-5 rem). No SMWS structure, system, or component is so designated.
Service Clgss III is assigned to those structures, systems or components whoue repair / replacement could result in a loss of operating capability of one to four weeks and/or an exposure to repair / replace of up to 1 rem. The SMWS mobilization pump support structure, mobilization pumps, and support equipment are so designated.
Structures, systems and components which by nature are reliable and compatible with their required availability based on a history of proven industrial performance are assigned Service Class IV.
Wnenover practical, equipment / component spares will be maintained on-site to minimize impact on operating capabilities should failures occur (Section D.6.5.3).
RLW4284:3RM Page 241 l
l
WNS-S AR-004 Rev. 6, DRAFT A.4 Section A.12.2 of Volume I discusses the implementation of the Quality Assurance Program based on DOE Order 5700.6B, DOE-ID Order 5700.6C and the eighteen criteria of ANSI /ASME HQA-1, 1986.
RLW42B4:3RM Page 242
WVHS-SAR-004 Rev. 6, DRAFT A.4 REFERENCE 5 FOR SECTION D.12.0 DOE 5700.6B U.S. Department of Energy, " Quality Assurance," September 1986.
HQA-1 American Society of Mechanical Engineers, " Quality Assuranco Program Heguirements for Nuclear Facilities," ASME NQA-1-1986, September 1986.
QM West Valley Nuclear Services Quality Management Program, April 1990 kLW4284:3RM Page 243 i
TR/IRTS.5 Rev. 7, Draft E RECORD OF__REV1STON PROCEDURE If there are changes to the procedure, the revision nutber increases by one.
These changes are indicated tu the left margin of the body by 4.n arrow (>) at the beginning of the paragraph that contains a che.oge, h%)(=,'ff;lD'~~~~~~.,.'
N$
h -
Exampla: .J..d ;;g
> The arrow in the margin indicates a change.
Revision On Rev No. Description of Changes Page(s) Dated 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release N/A 08/88 2 Per ECN No. 2607 6 2607A All 09/88 3 Per ECN No. 2845 All 02/89 4 Per ECN No. 2978 All 06/89 5 Per ECN No. 3174 13 11/89 6 Per ECN No. 3354 Page 3 01/90 7 Per ECN No. 4125 All 01/91 W-1807, Rev. 1 i MSS 0678 : 3PJi l
A....
TR/IRTS.5 Rev. 7, Draft E RECORD OF REVIS10!1 (CO!iTI!!UAT10!! SHEET)
Revision on Rev. !!o . Eoscription of Changes Page(s)
- .==
W-1807 Rev, 1 11 MSS 0678: 3RM
'k .. Rv raft E I
TYPE: 1 l TITLE: STS Process Limits j NUMBER:
OSR [ ] IRTS 5 l
l 1
Tech. Regmn't. {X)l 1 l
l 1
CRITERIA: 1. Vaste produced shall meet the qualification of the Process Control Plan.
>. 2. STS shall meet the Drurn Cell acceptance criterion of less than or equal to 5.5 uCi/mL of Cs 137 in LVTS concentrates used to produce the final wasta form for storage in the Drurn Cell, and a final product TRU concentration $68 nCi/g in the final vaste form if the waste is to be solidified in the CSS.
- 3. STS may transfer liquid from 80 1 to LVTS for volume reduct on if the 8
concentrates are retutned to the waste tank farm (8D 2). I l l P
> UNACCEPTABLE EVENTS: 1.
Failure of the STS to reduce Cs 137 concentrations in decontaminated supernatant and sludge wash solutions below j levels acceptable for processing by CSS and storage in th(
Drum Cell.
> 2. Final product * I concentration >68 nC1/g.
1 I Safety Limit I j l Reporting Requirements:
LCO lDOE ID CONTROLLED l l LCS l l l Surveillance Reqmn't. l l l
l l l l
l l Tech. Requirement l I X l Critique IDOE WVPO CONTROLLED I i Operating Limit i l I lWVNS CONTROLLED IMPLEMENTING PROCEDURES:
SOP 50 23 SOP 50 36 f; SOP 50-42 SOP 50 33 SOP 00 13 SOP 50 32 SOP 50 44 MSS 0678:3RM
TR/IRTS.5 l Rev. 7, Draft E TECllNICAL REQUIRD412iT _
f f ,y ,\ R , %-. . , ],', - - - -...... , ,,
.St.1_PERNATA_NT u; = TRFX_=_IND._4._T SYS_TD4_
m .
PROCESS._l.1_ H_ITS , , , , _\ J [ ? d . .[ ,,
[t * ' , . -
J.
APPL.lCA1111.1TY
> LCO No. I applies to the taaximum concentration of Cs.137 permitted in the discharge of the final ion exchange column in the STS, LCo No, 2 applies to the maximum Cs.137 and alpha TRU concentration permitted in the transfer of decontaminated supernatant or sludge wash solution frorn BD 3 to the LVTS, LCO No. 3 applies to 11guld that is sent to LVTS for volume reduction and is ultimately returned to the VTF.
Olu ECT'.VE
> To assure that the Cs 137 concentrations in decontaminated supernatant or sludge wash solut. ions transferred eventually to CSS will not exceed the Drum Cell acceptance criteria of less th.n or equal to 5.5 pCi/mL in LVTS concentrates ,
and the final waste form has an alpha TRU content of <68 nC1/g.
DEFINITIONS
> 1. Decontaminated Supernatant or Sludge Wash Solution - liquid from Tank 8D.2 (either diluted or undiluted) that has passed through the STS ion exchange sys t ern .
> 2. Decontaminated Supernatanc or Sludge Wash Solution plus Flush a final process stop for STS operaticn which uses liquid from Tank 8D 1, or water, to push residual supernatant/ sludge wash through the ion exchange columns.
Typically 10,000 gallons of Tank 8D 1 liquid or 6,000 gallons of water is used to flush the colwins.
- 3. Liquid from Tank 8D 1 water condensed from vapor Benerated in Tank 8D.2 and water generated from various STS operations. This liquid has a relatively low salt concentration and a constantly increasing cesium concentration (as loaded zeol'.. is dumped to Tank SD 1).
MSS 0678 : 3PJi Page 1 of 4
TR/IRTS 5 Rev. 7, Draft E
> 4. TRU Concentration Concentration of long lived alpha emitting transurenic radionuclides me.isured as gross alpha.
LIMITING CONDITIONS FUR OPERATION (ifD)
> 1. LIQUID RADIATION MONITOR 50RE034 SilALL BE OPERATIONAL AT ALL TIMES TO ANALYZE CONCENTRATIONS OF PAD 10 ACTIVE MATERIALS IN DECONTAMINATED SUPEPSATANT PRODUCT TPxiSFERRED 10 TANK 8D 3. TilIS MONITOR SHALL BE CAPABLE OF BEING CALIBRATED TO A LEVEL CORRESPONDING TO 10 PERCENT (OR LESS) 0F Tile Cs 137 TRANSFER LIMIT (1.E., 50.55 pCL/mL). Tile MONITOR ALARM POINT SliALL BE SET SUFFICIENTLY LOW TO ASSURE THAT CONCENTPATIONS OF Cs 137 IN EXCESS OF 5.5 pCi/mL BEING TRANSFERRED TO TANK BD 3 WILL CAUSE AN AIARM. AUDIBLE AND VISUAL ALARMS SHALL BE PROVIDED IN THE STS CONTROL ROOM.
> 2. FOR TRANSFERS OF DECONTAMINATED SUPERNATANT OR SLUDGE VASil SOLUTIONS OR PLUSil WATER PROM TANK SD 3 TO LWTS, THE CONCENTRATIONS OF Cs 137 (uci/mL) AND ALPilA TRU (pCi/mL) S}lALL NOT EXCEED THE VALUES AS DETEPJtINED FROM THE FOLLOVING EQUATIONS:
EQUATION 1:
C1 - MAXIMUM Cs 137 CONCENTRATION LIMIT IN BD 3 (uci/mL)
> SG - SPECIFIC GRAVITY C1 - 0.1 SG f 3 f 3- WEICHT PERCENT DISSOLVED P LIDS AND EQUATION 2:
> C2 - MAXIMUM GROSS ALPHA CONCENTPATION LIMIT IN 8D 3 (pCi/mL)
C2 - 0.034 C1 C1 - AS DETERMINED IN EQUATION 1
> 3. LIQUID FROM TANK 8D 1. AFTER PROCESSING THROUGH STS, MAY BE ROUTED FROM TANK 80 3 TO THE LWTS FOR VOLUME REDUCTION. THE CONCENTRATES WILL BE RETURNED TO TANK BD 2. ADMINISTRATIVE CONTROLS SHALL BE USED TO ENSURE THAT TilIS LIQUID IS NOT TRANSFERRED TO CSS. AT NO TIME MAY THE ACTIVITY CONCENTRATION IN TliE VOLUME REDUCED LIQUID EXCEED 50 pCi/mt. Cs 137 OR TRU MSS 0678:3RM Page 2 of 4
TR/IRTS 5 Rev. 7, Draft E CONCENTPATIONS CREATER TilA!1 EQUATION 1 AND 2 LIMITS SilALL !;OT LIMIT TRANSFERS OF LIQUID CRIGINATING FROM TANK BD 1, OR FROM 8D 3, To LWTS (LCO No. 2 0F TilIS TR). TR/IRTS 7 DOES NOT APPLY TO TANK SD 1 LIQUID PROCESSING.
SURVEILIANCE REQUIREMENTS
> 1. CALIBRATIO!10F RADIATION MONITOR $0RE034 SHALL BE PERFORMED EVERY SIX MONTilS TO ENSURE COMPLI ANCE WITH LCO 1.
> 2. VHILE OPERATING STS, A SAMPLE OF TANK BD 3 SHALL BE TAREN DAILY AND ANALYZED TOR Cs 137 AND CROSS ALPilA TO ESTABLISil COMPLIANCE VITH EQUATIONS 1 AND 2.
> 3. TANK SD 155 SilALL BE SAMPLED AND Tile ANALYTICAL RESULTS USED TO CALCUIATE THE MAXIMUM VOLUME REDUCTION THAT CAN BE ACHIEVED. VilEN LIQUID FROM TANK BD 1 IS BEING VOLUME REDUCED, TANK SD 15Al OR TANK 5D 15A2 SHALL BE SAMPLED TO ENSURE THE CONCENTRATION DOES NOT EXCEED Tile LIMIT IN LCO 3.
RASIS
> Satisfactory compliance with Equations 1 and 2 ensures the CSS and Drum Cell acceptance criteria of a Cs 137 concentration in LVTS concentrates of
<$.5 pCi/mL and a TRU concentration in CSS product of <68 nCi/gm.
Decontaminated supernatant or sludge wash solution with a Cs 137 concentration in excess of the limit in Equation (1) as measured at Tank 8D 3 will be' recycled to Tank 8D 2 for re':ork.
2 Volwue 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 uCi/mL (LWTS Design Criteria, VVNS DC 025, paragraph 2.2.1). VVNS will work to the design criteria laait because of the emergency nature of this action. Decontamination factor calculations and process control calculations designed to limit the activity concentration of vaste sent to the CSS should not be applied to liquid that will be returned to the high level waste storage tanks.
MSS 0678:3RM Page 3 of 4 l
TR/IRTS-5 Rev. 7. Draft E
- ATTAC11MENTS l
- None REFERENCFJ
- 1. Letter, E. R. Faillace to P. J. Valenti, FB:89:0074 " Transmittal of Calculations to Estimate CS 137 Activity in INTS Concentrates", dated 04/10/89
- 3. Memo, E. R. Faillace to C. J. Roberts , FB:91:0014, " Limit on Cs 137 and Alpha Transuranic Concentration in STS Product,"
dated January 17, 1991.
1 l
l l
l l
l l
'k P
MSS 0678:3RM Page 4 of 4
_ . . - . . _ . _ _ . . _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ , . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . , -. _ _ _ _ _ _ _ _ _ _ __.__