ML20095J917
| ML20095J917 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 04/24/1992 |
| From: | Lindbergh B, Schiffhauer C WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | WEST VALLEY NUCLEAR SERVICES CO., INC. |
| References | |
| REF-PROJ-M-32 HF:92:0473, HF:92:473, NUDOCS 9205040196 | |
| Download: ML20095J917 (20) | |
Text
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- HF:92:0473 Ore April 24, 1992 Sae:t Controlled Distribution of Revisions to the Operational Safety Requirements / Technical Requirements, Volume VI to Distribution ec: Original, MS 50B Attached are the following revisions to the Operational Safety Requirements / Technical Requirements, Volume VI, which has been assigned to you under controlled distribution:
- Latest Index
- obr /GP 1, Rev. 3 "WDP Airborne Radioactive Release Limits" OSR/CP-2, Rev. 2 " Radioactivity Content af Liquid Effluents Released from VVDP" Destroy or mark superseded the current Index; OS:t/CP 1, Rev. 2; and OSR/CP 2, Rev, 1, and place the attached copies in your controlled manual accordingly.
,/ Copies made from a controlled document are to be marked IMCONTRO' LED before distributtor..
To acknowledge receipt of these documents, sign, date, and return the attached ce;ntrolla distribution receipt acknowledgement to the undersigned by Mr , 1992.
For your conven. . .c e , a self-addressed, stamped envelope (off site recipients only) has been provided, For on-site recipients, a return address has been placed on the reverse side of the controlled distribution receipt acknowledgement; fold and place in the mail.
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M' ) _<f_L B. E.
Lindbergh,MordsProcess'e{
Records Management West Valley Nuclear Services Co. , Inc.
BEL Approved: b- flutL C. M. Schif pauer, Manager
Attachment:
As stated above i
u/ PRC0164 R12 /
OPERATIONAL SAFETY REQUIRDO'NTS/fECHNICAL REQUIRDENTS
( VEST VALLEY DEMONSTRATION PROJECT WDP Former WDT, NFS Identifier Rev. Title / Contents Identifiers OSR/GP-1 3 WVDP Airborne Radioactive M.11.5.2.4.
Release Limits WVDP 4.1 OSR GP 1 OSR/TR GP 1 OSP./GP-2 2 Radioactivity Content of Liquid M.ll.5.2.5.
Effluents Released from WVDP WVDP 4.2 OSR-CP-2 OSR/TR-CP 2 OSR/CP-3 4 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.
WVDP 4.14 (N LWTS 5.2,
(,) NFS 6.5, STS 1.2, CSS 4.2 M.ll.5.2.8.
TVS 3.0 M.11.5.2.1 VF 2.2, 2.3 OSR GP-3 OSR/TR-CP 3 OSR/CP-4 2 Effluert and Environmental M.ll.5.2.1.B.X Monitoring (WVDP 5.1)
OSR CP 4 OSR/TR-CP 4 BLB0578:3RM DATED: 04-24-92
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WDP Former WDP, NFS
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Identifier Rev. Title / Contents Identi fie rs OSR/GP-5 3 WVDP Emergency Power Requirements M.11.5.4.3.
NFS 6.4 M.11.5.2.1.D STS 1.3 M .11. 5. 2 .1. G CSS 4.4 OSR GP 5 OSR/TR GP-5 TR/GP-6 2 Storage Requirements for M.ll.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 2 Criticality Safety for Liquid M.11.5.2.2.
Transfer WVDP 4.3 OSR GP 7 OSR/TR-CP 7
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- TR/GP-8 2 Water Activity Alarms M.11.5.4.1.
NFS 6.9 TR GP-8 OSR/TR-GP-8 TR/GP-9 2 Control of Plant Equipment New Function and Configuration "R CP-9 OSR/TR-GP-9 OSR/GP-10 2 Airborne Effluent Monitoring M.11 5.4.4.
System Operability NFS 6.5 STS 1.1, 1.2 CSS 4.1 OSR GP-10 OSR/TR-CP-10 OSR/GP-ll 3 Storage Canister Loading and M.ll.5.1.2.B Spacing AFM 6.0 STS 1.4, CSS 4.3, L'JTS 5. 3 OSR GP-ll OSR/TR GP-11 ,
BLB0578:3RM 2- DATED: 04-24-92
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l WDP Former WDP NFS Identifier Rev. Title / Contents Identifiers OSR/GP-12 2 Fissile Material Limits and M.11.5.1.1.B Requirements for Vaste Packages CPCRIT 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 RER 1.2-OSR GP 12 OSR/TR-GP-12 TR-C? 13 1 Evacuation Alarm and Emergency New Paging System Operability TR GP 13 OSR/TR CP-13 TR-GP-14 1 WDP Meteorologi al System New Operability TR GP-14 OSR/TR-GP-14
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s TR-GP-15 i
1 Fire Brigade and Emergency New Response Team Training TR GP-15 OSR/TR CP-15 TR/GP 16 2 Plant Fire Prot tion Systems New TR GP 16 OSR/TR-GP-16 OSR/GP-17 0 TN-BRP and TN REG Shipping Cask New Lid Installation OSR/GP-18 0 Type B Shipping Cask License New Compliance Documentation TR/GP-19 0 Area Radiation Detector New j Requirements During Cask Fuel Loading BLB0578:3RM DATED: 04-24-92
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( WDP Former WDP, NFS Identifier ,Re v . Title / Contents Identifiers OSR/IRTS-1 3 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 3 Control of CSS Recipe for M 11.5.2.2.C Decontaminated Supernatant CSS 4.3 TR IRTS 2 OSR/TR-IRTS-2 OSR/IRTS-3 3 Maintenance of Spare HLW M.11.5.2.3.
Storage Capacity NFS 5.4 OSR IRTS-3 OSR/TR-IRTS-3 TR/IRTS-4 4 Depressurization of STS for M.11.5.6.1.D Maintenance TR IRTS-4 OSR/TR-IRTS-4 TR/IRTS 5 7 STS Process Limits M 11.5.1.1.D STS 1.4 TR IRTS-5 OSR/TR-IRTS-5 TR-IRTS-6 2 LWTS Manifold Control - CANCELLED New TR IRTS-6 OSR/TR-IRTS 6 TR-IRTS-7 5 Sampilng and Analysis New Requirements for Tank 5D-15B M.ll.5.1.1.H LWTS 5.3 TR IRTS-7 OSR/TR-IRTS-7 TR/IRTS-8 4 Sampling and Analysis New Requirements for Tanks 5-D 15 TR IRTS-8 Al and A2. OSR/TR-IRTS-S BLB0578:3RM -4 -
DATED: 04-24-92 i
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WDP Former WDP, NFS Identifier Rev. Title / Contents Identifiers OSR-IRTS-10 0 Criticality Control During New Processing of High Level Vaste Through Ion Exchange Columns Containing Ti-Treated Zeolite l TR-IRTS-11 0 Fissile Material Mass Balance New Across the LVTS Evaporatar
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BLB0578:3RM DATED: 04-24 92
000. Num:er OSR/GP-1 Revisica Nu= er 3 Revision Ca:e 04/24/92 Fngineering Release #1430 Per ECN #3353 Per ECN #390*
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P.C. Se x 191-West Vciley N.Y.11i71- CISI ,
OS R : 00012 7 4. R.'l DOE Approved: DW: 92:0397
'N V - t a t S Dated 03/17/92
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OSR-/GP-1 Rav. 3 ElfQEp OF REV?SION PROCEDURE If there are changes tr. 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.
Examoles
> The arrow in the margin indicates a change.
Revision On Pev. No. Deserlotion of Chances Pace (s) Dated 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release 1430 N/A 8/88 2 Per ECN 3353 Page 4 1/90 3 Complete Revision Per ECN 3902 All 04/24/92 l
WV-1807, Rev. 1 i s
OSR 0001274.RM
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. OSR-GP/-1 Rev. 3 RECORD OF REVISION fCONTINUATION SHEET)
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OSR/GP-1
(::) l OPERATIONAL SAFETY REQUIREMENT OSR/CP-1 TITLE: WVDP Airborne Radioactive Release Limits CRITERIA: 1. Release of airborns radioactive effluents shall not exceed licits established by DOE orders.
UNACCEPTABLE EVENTS: 1. Releases of airborne radioactivity exceeding DCE limits.
REPORTING REQUIREHENTS: For Operational Saf ety Requirement (OSR) violations, WV-987 " Initial Investigation, Oral Reporting, and Written Critique of Occurrences at WVNS" shall be followed.
[N Operational Safety Requirement OSR/GP-1 Page l Safety Limit
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l Limiting Conditions for Operation (LCOs) . . . . . . . . . . . . . . . . . 1 Surveillance Requirements (SRs) . . . . . . . . . . . . . . . . . . . . . . 2 Basis
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Attachments References
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
. . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . 3 IMPLEMENTING PROCEDURES:
EM-ll EM-101 SOP 15-11 SOP 15-48 SOP 50-35 SOP 70-30 SOP 80-5 SOP 80-6 1
til OSR:0001274.RM
OSR/GP-1 Rav. 3 OPERATIONAL SAFETY REQUIREMENT O'~
WVDP AIRBORNE RADIOACTIVITY RELEASE LIMITS APPLICABILITY This OSR applies to all airborne radioactive emissions from WVDP permitted process and ventilation stacks.
OBJECTIVE This specification ensures that the off-site doses from airborne radioactive releases from WVDP operations are less than the guideline values stipulated by DOE Order 5400.5, and 40 CER 61, for individuals in uncontrolled (off-site) areas.
SPECIFICATION SAFETY LIMIT OFF-SITE RADIATION DOSE TO THE MAXIMALLY EXPOSED INDIVIDUAL BY THE AIRBORNE PATHWAY SHALL BE LESS THAN 10 KREM/ YEAR EFFECTIVE DOSE EQUIVALENT.
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LIMITING CONDITIONS FOR OPERATIQH A.
THE TOTAL PARTICULATE RADIOACTIVITY RELEASE RATE FROM THE WVDP MAIN PLANT STACK SHALL NOT EXCEED 18 NANOCURIES/SECOND FOR LONG-LIVED GROSS BETA ACTIVITY AND O.18 NANOCURIES/SECOND FOR LONG-LIVED GROSS ALPHA ACTIVITY AVERAGED OVER A CALENDAR QUARTER.
B.
THE TOTAL PARTICULATE RADIOACTIVITY RELEASE FROM EACH OF THE OTHER STACKS AND ANY FUTURE VENTS OR STACKS FOR WHICH MONITORING IS OR WILL BE REQUIRED (UP TO A TOTAL OF NINE STACKS), SHALL NOT EXCEED 3 NANOCURIES/SECOND/ STACK'FOR LONG-LIVED GROSS BETA ACTIVITY AND O.03 NANOCURIES/SECOND/ STACK FOR LONG-LIVED GROSS ALPHA ACTIVITY AVERAGED OVER A CALENDAR QUARTER.
- 2. SURVEILLANCE REOUIREMENT.
A.
THE TOTAL PARTICULATE RADIOACTIVITY RELEASED FROM THE WVDP MAIN PLANT STACK SHALL BE HEASURED TO ENSURE THAT THE AVERAGE AIRBORNE t
OSR 0001274.RM Page I of 3 k
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OSR/GP-1 R3v. 3 B. THE TOTAL PARTICULATE RADIOACTIVITY RELEASED FROM ALL OTHER STACKS FOR WHICH MONITORING IS REQUIRED SHALL BE MEASURED TO ENSURE THAT THE
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() AVERAGE AIRBORNE RADIOACTIVITY RELEASED DOES NOT EXCEED 7.8 MILLICURIES / STACK GROSS BETA ACTIVITY OR 0.078 MILLICURE/ STACK CROSS ALPHA ACTIVITY IN ANY ONE MONTH.
- 3. RECOVERY IF THE RELEASE RATES SPECIFIED IN THE SURVEILLANCE REQUIREMENT ARE EXCEEDED, OPERATIONS SHALL BE CURTAILED AND CONDITIONS EVALUATED AND CORRECTED TO ASSURE THAT THE QUARTERLY LIMITS CAN BE MET BEFORE FURTHER OPERATIONS ARE PERMITTED.
E.A515 Per DOE Order 5400.5 and 40 CFR 61 Subpart H, the committed effective dose equivalent (EDE) from all stack effluents is limited to 10 mrem / year to any off-site resident, with an administrative surveillance level set at 1/12 of 10 percent of this limit per month for each stack or vent requiring monitoring.
The straight line gaussian plume dispersion model, the terrestrial food-chain pathway models in NRC's Regulatory Guide 1.109, and external and internal desa factors (using the ICRP's organ weighted risk model), are incorporated in the computer model required by 40 CFR 61. This model forms the calculational Ot basis for the radionuclide release limits in the Limiting Conditions for Operation (LCO) and the Surveillance Requirement (SR) of this OSR.
Annual average measurements of stack effluents show that the concentration of long-lived gross beta activity is typically on the order of 100 times the long-lived gross alpha component. Heasured eftluen't ratios of Sr-90 to Cc-137 are approximately 1:1; effluent ratios of Pu-239 to Am-241 are approximately 123. Using these data, gross beta activity is conservatively assumed to be 50 percent Sr-90 plus 50 percent Cs-137, and gross alpha activity is assumed to be 25 percent Pu-239 and 75 percent Am-241. The ventilation flow rates are not factors in the computer model.
The four radionuclides in the above ratios were input to the EPA-approved air dispersion and dose assessment code AIRDOS-PC (Version 3.0, 1990). One computer run was performed for the main plant stack using wind data collected during 1989 at the 60 meter elevation of the on-site meteorological tower.
Another run was performed for all other stacks (assuming a 10 meter release height) using wind data collected at an elevation of 10 meters.
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OSR/GP-1 Rev. 3 As determin6d from the AIRDOS-PC predictions and a survey of nearby residences, the maximally exposed off-site individual (for both elevated and ground-level releases) lives approximately 1900 meters NNW from the main plant stack.
The results from the computer runs were used to scale the radionuelide release rates so that the EDE to the maximally exposed resident from any stack or vent that requires monitoring would not exceed 10 percent of the limit (i.e.,
1 mrem / year) if the LCOs were met. If, in the future, more-than ten stacks (including the main plant stack) require monitoring, this limit on each stack will be revised to accommodate the additional stacks.
The administrative level of 1/12 mrem / month from any monitored stack or ' vent was obtained by reducing the 10 mrom/yr limit by a factor of 10 and dividing by 12 months. To obtain the monthly limits in SR Parts A and B, the release rate limits in LCO Parts A and B, respectively, were multiplied by the number of seconds in 30 days. Procedurally, action is rc red to investigata and report to management release levels at or above 75 percent of OSR limits (EM-ll). In addition, monthly tracking of airborne releases is provided to site management.
ATTACRMENTS O None REFERENCES DOE /EP-0096, A Guide for Effluent Radiological Measurements at DOE-Installations, 7/83.
DOE /EP-0023, A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Installations, 7/81.
DOE Order 5400.5, Radiation Protection of the Public and the Environment, 2/90.
40 CFR 61, Subpart H, National Emission Standards for Emissions of Radionuclides other than Radon from Department of Energy Facilities.
DOE-ID Order 5400.1 General Environmental Protection Program, 8/12/91 OSR 0001274.RM Page 3 of 3
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'Nes Vcliey , N .Y.14171- CIS I OSR:0001273.RM CCE Approved: DW: 92:0397 Wu, rce.: m Dated 03/17/92 i m,, ..,,y. < 7.,., s..,
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RECORD OF REVISION O 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.
Example
> The arrow in the margin indicates a change.
Revision On Pev, No. Description of Chancee Pacefs) Dated 0 Original Issue All 1 Dated S/20/88 All 1 Engineering Release 1430 N/A 08/88 2 Per ECN #4227 All 04/24/92 Update references, clarifying language added, radiological concentrations adjusted to meet new DOE Order requirements, added a reporting requirement O
WV-1807, Rev. 1 1
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OSR/GP-2 Rsv. 2 OPERATIONAL SAFETY REQUIREMENT GP-2 l
TITLE: Radioactivity Content of Liquid Effluents Released from WVDP CRITERIAt 1. Release of radioactive liquid effluents shall not excead i
limita established by DOE orders.
UNACCEPTABLE EVENTS: 1. Discharge of radioactive liquid effluent exceeding DCGs at the site boundary.
REPORTING REQUIREMENTS: For Operational Safety Requirement (OSR) violations, WV-987 " Initial Investigation, Oral Reporting, and Written Critique of Occurrences at WVNS" shall be followed.
Operational Safety Requirement GP-2 Page v
Safety Limits (SLa) . . . . . . . . . . . . . . . . . . . . . . 1 Limiting Conditions for Operation (LCoo) . . . . . . . . . . . . 2 Surveillance Requirements (SRs) . . . . . . . . . . . . . . . . . 3 Basis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 IMPLEMENTING PROCEDURES: SOP 15-1 EM-ll EM-101
- s. OSRt0001273.RM 111 1
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. OSR/GP-2 Rev. 2 OPERATIONAL SAFETY REQUIREMENT GP-2 TITLE: Radioactivity Content of Liquid Effluents Released from the WVDP BffJ,ICABILITY This OSR establishes limits for the controlled discharge of radioactivity contained in liquid effluents released from the site.
OBJECTIVE To provide reasonable assurance that concentrations of radioactivity deliberately released to the environment will meet the requirements of DOE Order 5400.5.
SPECIFICATION SAFETY LIMIT EFFECTIVE DOSE EQUIVALENT TO MAXIMALLY EXPOSED OFF-SITE INDIVIDUAL BY WATER PATHWAY SHALL BE LESS THAN 100 MREM / YEAR.
LIMITING CONDITIONS FOR OPERATION
- 1. LIQUID DISCHARGED TO THE ENVIRONMENT WITHOUT PASSING THROUGH A PERMITTED TREATMENT SYSTEM SHALL MEET ALL OF THE FOLLOWING CRITERIA:
O > A. GROSS o ACTIVITY LESS THAN 3.0 X 10 e yCi/mL ABOVE BACKGROUND
> B. GROSS B ACTIVITY LESS TRAN 1.0 x 10 pCL/mL (NOT INCLUDING H-3) ABOVE BACKGROUND
> C. TRITIUM ACTIVITY LESS THAN 2 X 10'3 yC1/mL ABOVE BACKGROUND PROVICED THAT THE SUM OF THE FRACTIONS OF A, B, AND C IS LESS THAN UNITY 1.e.,.SO THAT:
o uCi/mL + B uCi/mL - + Q ,C1/mL < 1, AND 3.0 x 10-e 1 x 10 2 X 10~3
> D. VOLUME RELEASED LESS THAN 10,000 GALLONS PER DAY.
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ANNUAL AVERAGE CONCENTRATIONS OF RADIONUCLIDES IN ALL LIQUID DISCHARGED TO THE ENVIRONMENT, INCLUDING RELEASES FROM A PERMITTED TREATMENT SYSTEM, SHALL NOT EXCEED THE DOE DERIVED CONCENTRATION GUIDES (DCGs) AT SAMF'.E LOCATION WNSP006 (THE POINT W.!ERE FRANK'S CREEK LEAVES THE FENCED SITE SECURITY AREA).
SURVEILLANCE REOUIREMENTS
> 1. EACH BATCH OF LIQUID WHICH EXCEEDS THE CONDITIONS OF LCO NO. 1 SHALL BE SAMPLED AND ITS ISOTOPIC COMPOSITION SHALL BE MEASURED {
PRIOR TO INTENTIONAL DISCHARGE TO DETERMINE COMPLIANCE WITH ti NO. 2. RESULTS OF THESE MEASUREMENTS SHALL BE REPORTED MONTHLY.
i
> 2. ANNUAL AVERAGE RADIONUCLIDE CONCENTRATIONS AT SAMPLE LOCATION WNSPOO6 SHALL BE DETERMINED AND REPORTED IN THE ANNUAL SITE ENVIRONMENTAL REPORT.
BASIS
> 1. DOE Order 5400.5 requires that an effluent monitoring system shall be in place for each effluent stream which has a reasonable probability of exceeding Derived Concentration Guides (DCG).
Releases which may result in an annual dose commitment to any individual in the uncontrolled environment of greater than 10 mrem must be reported to DOE-HQ per DOE 5400.5. The concentrations listed under LCO NO. 1 correspond to the most restrictive of the DG4 3 cgs for radionuclides which might contribute a significant fraction of the total off-site radiation dose from liquida released from the WVDP site. The combinction of the restricted gross alpha, beta, and tritium radioactivity concentrations and the limit on total released volume combined with the dilution which inevitably occurs before any effluents from the immediate Project site cross the boundary of the Western New York Nuclear Service Center, will ensure that tho potential dose to an off-site individual from the fraction of site releases meeting LCO NO. I restrictions will be well below 1.0 mrem per year and is ALARA.
> 2. Effluents knich do not meet all of the criteria of LCO No. 1 must be sampled, analyzed, and reported monthly to ensure that annual average concentrations do not exceed the combined DCGs at the point where the discharge exits the alte at the Project security fence, (WNSP006). This will ensure that the effective dose equivalent to an off-site individual will not exceed 100 mrem / year and will meet the requirements of DOE Order 5400.1 and DOE Order l 5400.5. Confirming measurements at the exit sampling point-(WNSP006) will be reported in the annual Site Environmental OSR:0001273.RM Page 2 of 3
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l CSR/GP Rev. 2 l
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Report. ~ Prudent plant operation dictates that the quantity of radioactivity released.to the environment be kept as low as- ,
reasonably achievable.
ATTACHMENTS None REFERENCES DOE /EP-0096, A Guide for Effluent Radiological Measurements at DOE Installations, 7/83.
DOE /EP-0023, A. Guide for Environmental Radiological Surveillance l
at U.S.-Department of Energy Installation,-7/81. ,
DOE /EH-0173T, " Environmental Regulatory Guide for Radiological- '
Iffluent honJtoring and Environmental Surveillance", 1/91.
~
U.S. DOE Order 5400.1, " General Environmental Protection Program",
11/88.
> U.S. DOE Order 5400.5,;" Radiation Protection of the Public and the l Environment", 2/90.
Radiological Parameters for-Assessment of West Valley Demonstration Project Activities, WVDP-65, Rev. 2, 10/90.
U.S. DOE-ID Order 5494.1A, " Environmental Protection, Safety, and Health Protection-Information Reporting Requirements," 8/82.. s l-I wv-1807 JR5 OSR:0001273.RM Page 3 of-3
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