ML20198B901
| ML20198B901 | |
| Person / Time | |
|---|---|
| Site: | Portsmouth Gaseous Diffusion Plant |
| Issue date: | 12/24/1997 |
| From: | John Miller UNITED STATES ENRICHMENT CORP. (USEC) |
| To: | Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| GDP-97-0218, GDP-97-218, NUDOCS 9801070111 | |
| Download: ML20198B901 (51) | |
Text
f ~4 USEC A GWI Energy Company -
JAMES H. Mou.ER Dir; (301) 564-3309 Wce PRE 81oENT,PRooucTioN L Far (301) 571-8279 -
December 24,1997 Dr. Carl J. Paperiello SERIAL: GDP 97-0218 Director, Oflice of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S; Nuclear Regulatory Commission Washington, D.C. 20555-00')1 Portsmouth Gaseous Dilfusion Plant (PORTS)
Docket No 70-7002 Transmittal of Revision 15 to Portsmouth Certification Application
Dear Dr. Paperiello:
In accordance with 10 CFR Part 76, the United States Enrichment Corporation (USEC) hereby submits twenty (20) copies of Reviiion 15 (December 19,1997) to USEC-02, Application for United States Nuclear Regulatory Commission Certification, Portsmouth Gaseous DilTusion Plant.
Revision 15 incorporates changes to the Emergency Plan, Fundamental Nuclear Materials Control Plan (FNMCP), Physical Protection Plan, Transportation Security Plan, and Classified Matter Protection Plan that were implemented during the period June 13,1997 to November 15,1997. The changes to these programs and plans have been reviewed in accordance with 10 CFR 76 and have been determined not to require prior NRC approval. Revision bars are provided in the right-hand marg!n to identify the changes. Revision 15 was implemented effective December 19,1997.
Revision 15 of the FNMCP and Transportation Security Plan, contain certain trade secrets and commercial and financial information exempt from public disclosure pursuant to Section 1314 of the
- Atomic Energy Act of1954 (AEA), as amended, and 10 CFR 2.790 and 9.17(a)(4). In accordance with 10 CFR 76.33(e) and 2.790(b), Revision 15 to these plans is Letter GDP 97-021C).
The Physical Protection Plan and Classified Matter Protection Plan, prepared pursuant to 10 CFR
- 76.35(j), contain National ',ecurity In ormation and/or Restricted Data. These documents are also f
considered to be proprietary commercial and financialinformation pursuant to 10 CFR 2.790(d)(1). In 9001070111 971224" PDR ADOCK 07007002 ill10Rllllllllllll e
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.,,y3 6903 Rockledge Drive. Bethesda, MD 20817-1818
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Telephone 301-564 320^ 1:n 301564-3201 hirp://www.usec.com Omces in Livermore, CA _ Paducah KY lbrtstr 3uth, OH Washington. DC l
3~
r. Dr; Carl J. Paperiello -
+ December 24.' 1997 GDP 97-0218 Page 2 adcordance with 10 CFR'76.33(e),2.790(b),95.37, and 95.39, Revision 15 to these plans is being submitted under separate cover (USEC Letter GDP 97-0220),-
Should you have any questions or comments on Revision 15, please call me at (301) 564-3301 or..
Steve Routh at (301) 564 3251.
Sincerely,-
s J nes H -Miller -
ice President, Production
Attachment:
USEC-02, Application for United States Nuclear Regulatory Commission Certification, Portsmouth Gaseous Diffusion Plant, Revision 15, Copy Numbers I through 20
Enclosure:
cc:.
- NRC Region III Office USEC-02 Copy Nea. 21,172 NRC Resident inspector - PGDP USEC-02 Copy No. 22
- Mr. Joe W. Parks (DOE)
USEC-02 Copy Nos. 24 through 28 m-y
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.s.
t
'OATil AND AFFIRMATION -
I, James H. Miller, swear atul affirm that I r.m Vice President, Production, of the United States Enrichment Corporation (USEC), that l'am authorized by USEC to sign and file with the Nuclear Regulatory Commission 'his Revision 15 of the USEC Application for United States Nuclear Regulatory Commission Certification, Portsmouth Gaseous Diffusion Plant (USEC-02), that I am familiar with the contents thereof, and that the statements made and matters set forth therein are true
- and correct to the best of my knowledge, information, and belief.
.-l Jamcs II. Miller On this 24th day of December,1997, the officer signing above personally appeared before me, is known by me to be the person whose name is subscribed to within the instrument,' and acknowledged that he executed the same for the purposes therein contained, in witness hereof I hereunto set my hand and' official seal.
Y W
State of Maryland, Montgomery Co[]nty Ihurie M. Knisley, Notary Public u
My commission expires March 17,1998 e
i y
-, +
APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COh1511SSION CERTIFICATION
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PORTShlOUTil GASEOUS DIFFUSION PLANT REh10VE/ INSERT INSTRUCTIONS REVISION 15 DECEMBER 19,1997 Remove Pages Insert Pages VOLUME i List of Effective Pages List of Effective Pages ilii, vil/viii, xv xxii i/ii, vii/viii, xv - xxii SAR 3.1 SAR 3.1 3,1 73/3.1-74 3.173/3.174 SAR 3,5 SAR 3.5 3.5 29 through 3.5 32 3.5 29 through 3.5-32 VOLUME 2 List of Effective Pages List of Effective Pages ilii, vii/viii, xv - xxii ilii, vii/viii, xv - xxii SAR 4,1 SAR 4.1 4,1 51/4.1 52,4.1 99/4.1 100 4,1 51/4.1-52,4.1 99/4.1-100
/'v)
SAR 4,5 SAR 4.5 4.5 4.5-9/4.5 10
-. 9/4,5-10 VOLUME 3 Emergency Plan Emergency Plan i/ii,1-1/l1,19/110,2304.5556,5-9/510 i/ii,1-1/1-1,1 9/l 10,7.-3/2-4,5-5/5-6,5-9/5-10 FNMCP FNMCP iii/iv, 5-5/5-6 iii/iv,5-5/5-6 Transportation Security Plan Transportation Security Plan 2, 9,19, 22,26a, 38, 39 2, 9, I 9, 22,26a, 38, 39 Physical Security Plan Physical Security Plan Cover Page,2,8,11,16,18,36. 48. 49,51,52, Cover Page, 2,8,11,16,18,36,48,49,51,52, 54,68,78,85, Addendum I 54,68,78,85, Addendum 1
,,ote: These pages are not transmitted to all document holders Classified Matter Security l>lan Classified Matter Security Plan Cover Page, 2,8,12,13,18,19,21,33,39,46, Cover Page, 2,8,12,13,18,19,21,33,39,46, 51,52,53,54,71,72,73,74,78,79,102,103, 51,52,53,54,71,72,73,74,78,79,102,103, 104,105,106,107,108,110,1:1,112,114,115, 104,105,106,107,108,110,111, i12, 114,i15,
-s 124, Addendum 1, Cover Page to Addendum 4, 124, Addendum I, Cover Page to Addendum 4
(*,Y Addendum 3, Addendum 3,1 Note: These pages are not transmitted to all document holders
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p SAR PORTS December 19,1997 Q
Rev.15-Before a tank car of R-114 is unloaded, it is sampled and analyzed for moisture content.
3.1.1.6.7.9 Maintenance When a cell coolant system requires maintenance, the cell (half cell in X-333) liquid is first drained to the R 114 drain tanks. After the hquid R-114 has drained. the vapors are removed by the vapor pumps to 15 inches vacuum or lower and discharged through the condenser into the drain tank. The exhaust pumps are then used to evacuate the system to approximately 28 inches vacuum or as close as is reasonably achievable. 'Ihese pumps discharge their vapors into the unit venti'ation exhaust duct to atmosphere, except for the X-333, where the vapors are exhausted into the cold recovery exhaust system to atmosphere. During this part of the evacuation, the vent gases are 100 percent R-114 vapors.
After the system is pulled down to approximately 28 inches vacuum, it is increased to atmospheric pressure with dry air and again pulled to approximately 28 inches vacuum by the exhaust pump.
The system is once again increased to atmospheric pressure with dry air and turned over to Maintenance.
A purging operation must be performed to reduce R-114 vapors. This is necessary because when R-il4 vapors are exposed to an open flame (550'F), they are oxidized to high!y toxic phosgene gas, j
3.1.1.6.8 Conditioninc-Gas Storace Facilities and Distribution Lines 3.1.i.6.8.1 Descrintion and Location!
The Portstrouth GDP has two conditioning-gas (CIF ) storage systems: one located on the ground I
3 floor of the X-330 Process Building at the east wall near the center of the building, and the other located on the ground floor at the west wall near the center of tl.e X-333 Process Building.
Each ft ility consists of a 2,000-ft' storage drum, loading manifold, instrumentation and alarms necessary for s fe operation, and the valves and piping that connect the storage drum to the unit bypass piping (see Figi e 3 ' J.6-11). Normally, the X-330 storage drum room will supp!y conditioning gas for the X-330 and X-u6 Process Buildings, while the X-333 storage facility supplies conditioning gas for that building only. Ilowever, either facility can supply conditioning gas to any cell or system in the three process buildings through the process building service piping.
The system were designed to store vaporized chlorine trifluoride (CIF ) used in cell treatments.
3 CIF is a powerful oxidizer and a very volatile and corrosive gas. When it comes in contact with oil, 3
water, acids, rubber, and R-ll4, the reaction products formed may include C10, HF, CIF, Cl, ClOF, 2
2 CIO F and ClO F.
2 3
Because of the toxic, corrosive, and sometimes explosive nature of these gases, extreme care must bc exercised during cylinder changes and valving operations to prevent releases.
.a s
m 3.173
4 SAR PORT 5 December 19,1997 Rev.15 Cylinders of CIF are tiansported onto the plantsite by commercial carriers. The cylinders are 3
stored at a variety of different buildings, including X 742, until Operations supervisors request cylinders l
of the material. It is the responsibility of Chemical Operations personnel to transport the full and empty CIF cylinders to and f om the storage drum rooms. Cascade Operations personnel are responsible for 3
connecting and disconnecting the cylinders, monitoring the feeding, aaministering the CIF to the desired 3
system and disposing of the reaction products after the cell treatments have been completed.
The two storage systems are basically of the same t : sign and configuration and have similar instrunentation. Each system has a two-position, cylinder-loading manifold connected with a tested and certified 3/8-inch copper pigtail using lead and teflon gaskets. (See Figure 3.1.1.6-12.) The metal enclosure with plastic windows (Figure 3.1.1.6-13) provides protection for the operator when opening and closing the cylinder valve. In case of gasket " burn out" or cylinder valve failure, a mechanism is attached to the cylinder valve so that the cylinder valve may be closed from outside the storage drum room.
Vaporized ClF is allowed to flow from the cylinders to the storage drum by natural evaporation.
3 No external direct heat may be applied to these cylinders at any time. The vapor pressure in a CIF3 cylinder at 80"F is 42 psia. After a cylinder has been feeding for approximately one hour, the pressure in the cylinder will decrease to the storage drum pressure because of evaporative cooling that allows the upper liquid level temperature to drop well below 32*F. The liquid level in a feeding cylinder is indicated by a frost ring on the cylinder.
Normally, each system will provide an inveatory of 150 to 360 pounds (at approximately 6 to 12 psia drum pressure) of vaporized CIF. Two cylinders ofliquid CIF, containing about 150 pounds each 3
3 when full are connected to the charring manifold and are tightly secured by a heavy metal band and a valve retaber to prevent the cylinders and cylinder valves from turning when the cylinder valve is operated.
There may be as many as six full cylinders of CIF stored in these areas at a given time. Both the full and 3
empty cylinders are chained to a storage rack which is bolted to the concrete-block wall (see Figure 3.1.1.6-13). Cylinders of compressed nitrogen, used to purge the cylinder manifold and pigtails, ore also stored in the same manner. Cylinders of compressed nitrogen, with pressure regulators, are used to purge the loading manifolds because the building nitrogen supply-header pressure is only 10 psig; therefore, the possibility of back-feer'mg CIF into th building nitrogen header is avoided. Two cylinders are connected 3
to the loading manifold and as many as four full cylinders are chained in storage racks to prevent accidental tipping.
A black-iron pipe connects the CIF piping in the storage drum room to the plant fluorine (F )
3 2
l header (see Figure 3.1.1.6-11). Redundant block valves were used in case of v- 'e seat failure. The normal pressure found in the plant F: distribution header is approximately 23 psia.
Fluorine is added to the CIF in the storage drum befort he mixture is admiristered to a cell or l
3 system for drying or unplugging treatments. The mixture will preclude the formation of compounds in the systems that may be exp'.osive when exposed to spark or excessive heat. These reactions are discussed in datailin the portion of Chapter 4, Accident Analysis, which deals with the UF cold recovery systems.
O 3.1-74
SAR-PORTS December 19,1997-
'Rev.15
' The location in the X-710 lluildmg where the greatest amount of fissile meerial can be present is the sample container cleaning facility. At this location the uranium contents of sample containers are dumped to a five-inch cylinder for eventual return to the cascade. This facility is a controlled access area where normal " worst case" assumptions of uranium assay are taken to assure criticality safety (e.g.,100%
U 235).
3.5.2.5 Laboratory and Pilot Plant Safety Systems, Design Features, and Administrative Controls The criticality alarms in X-710, X 760, and X 770 are safety systems. There are no design features or administrative controls, other than normal laboratory procedures, identified for the Laboratory and Pilot Plants.
3.5.3 - Receiving and Storage Facilities 3.5.3.1 Non contaminated 31aterial Storage Facilities 3.5.3.1.1 General An industrial facility the size of the Portsmouth Gaseous Diffusion Plant is involved with many-types of operations and facilities. This broad range of activities necessitates the use of large quantities and numerous types of materials and equipment. Numerous storage yards and warehouses are required to accommodate these materials.
This section describes the storage facilities primnity uLd to store materials which are not contaminated with radionuclides.* The storage facilities for materials contaminated with radionuclides are described in Sections 3.2 and 3.3. A listing and brief description of the facilitie xamined in this assessment are presented in Table 3.5.3-1.
3.5.3.1.2 11arardous Materials Many of the facilities described in this section are used to store materials which could be considered hazardous under certain conditions, i.e., lithium hydroxide monohydrate (LiOHoH O)",
2 chlorine trifluoride (ClF ), compressed gases, petroleum products, hazardous waste products (stored in l
3 X-752) and, in some cases, materials which have been in contact with process gas (UF.).
Materials which art slightly contaminated and stored in the facilities listed in Table
~*
3.5.3-1 are described in the text of this section.
N
.. Lithium hydroxide monohydrate is similar to lithium hydroxide (LiOH). Therefore, for simplicity, this compound will be referred to as lithiunt hydroxide throughout the remainder of this section.
3.5-29
4 4
SAR PORTS September 15,1995 Rev.1 The compressed gases and petroleum products present hazards which are common to many industries and are of a general safety nature. These will not be discussed further, The hazards associated with CIF are described in Appendix A.
The hazards associated with LiOH, the hazardous wastes 3
products, and the materials which have been in contact with process gas are briefly described in the following paragraphs.
Lithium HydroxidcJLtOH)
Large quantities of LiOH are stored in the X 744 K, S, T and U Warehouses, and in specially constructed pole barns (X-744N, P, and Q). The LiOH is stored in DOT approved polyethylene-lined overpack steel drums which contain, on the average,425 pounds of LiOH each. LiOH is a toxic and caustic compound which is in the form of colorless crystals. It is a strong irritant, highly toxic via ingestion, and moderately toxic via inhalation. The lithium ion has a high central nervous system toxicity.
Large doses of lithium compounds have caused dizziness and prostration. Lithium compounds can cause kidney damage, anorexia, nausea, gathy, coma, and death. LiOH is a strong base and, in water, is very caustic.
Hazardous Waste Products. X-752 The hazardous waste products stored in the X 752 Hazardous Wastes Storage Area include:
degreaser sludges (e.g., trichloroethylene, paint wastes, laboratory chemicals (e.g., arsenic pentoxide, ethyl acetate, lead acetate, and hydrofluoric acids), cyanides (e.g. silver, sodium, and copper cyanides), and various other small quantities of hazardous xartes generated on plamsite. These materials are stored in small quantities in individual sealed containers. The majority of the containers are 55-gallon drums. The materials are stored in this area until they are shipped to a hazardous waste disposal site. While in storage, the materials are inventoried quarterly. Incompatible materials are stored in areas separated by a dike.
There are severallaboratory chemicals in storage which require refrigeration to prevent possible iegradation into autoignitable or autodetonatable materials or materials which emit toxic fumes. The stored quantities of these chemicals are extremely small. The stored materials in this category, as of October 31, 1982, are: 2 vinylpyridine (400 grams),1,3-acetonedicarboxylic acid (600 gms), olivetol (5 gms), methyl fluorosulfonate (magic methyl) (500 gms), epoxylite (partial can, less than 1 pint), lead tetraacetate (100 gms), pyruvic acid (300 gms), 2,3-dibromoquinone-4-chloroimide (40 gms), isoamyl nitrate (100 pms),
acetaldoxime (100 gms), and malonyl dichloride (200 gms). The types and quantities of these materials which currently require refrigeration is indicative of the substances which are expected to be stored in the refrigerated portion of this facility in the future.
Some of the degreaser sludge and small quantities of mercury are slightly contaminated with uranium. It is permissible for the sludge to be stored in this facility if it contains less than 0.5 grams of U-235 per liter. To date, the highest level of U-235 found in the stored sludge has been approximately 0.2 grams of U-235 per liter. This contaminated material does not present a criticality or significant radiation hazard.
O 3.5-30
4 December 19,1997 p
- SAR PORTS Rev.15 9
With the exception of the slightly contaminated materials described above, the materials stored in this area are not unique to uranium enrichment facilities and may be found in many industries.
Eauioment Which Has Been in Contact With Process Gas Some of the X 747 Storage Yards near the X-720 Maintenance Building contain some equipment which has been in contact with process gas. This equipment is identified and has been monitored by Industrial Safety and Pndiation Protection and found to be contaminated to some extent. Special instructions on the tag provide the employee with the necessary equipment needed or precautions that must be followed wNn working on the tagged equipment. Also provided on the tag are various surface and wipe readings found on the equipment.
The equipment marked does not preser.t a hazard to employees or the public who are not working ou, or in contact with, the equipment.
3.5.3.1.3 Confinement Systems The only significant confinement system in the facilities is the 8-inch concrete dike which encloses the X-752 liazardous Waste Sto. age Area. This dike has a two-fold function. It contains spills of the liquid wastes and, at the same time, segregates incompatible wastes.
(
Although not a facility system, the overpack steel drums with plastic liners which contain the lithium hydroxide stored in the X-744 K N P, Q, S, T, and U Warehouses provide the only containment for the substance. Failure of these drums and overpacks can result in a release oflithium hydroxide into the warehouses where there is a potential for it to enter the environment.
3.5.3.1.4 Monitoring and Protection Systems As indicated in Table 3.5.31, there are no monitoring and protection systems involved in the operation of these facilities. However, several of the facilities have evacuation alarms slaved to criticality alarms in nearby facilities.
3.5.3.1.5 Waste Disnosal Systems There are no special waste disposal systems associated with these facilities. Wastes from these facilities, except where prevented by diked areas in X-752 and X-720C, enter the plant sanitary sewer system or flow via the water shed and/or drainage system to one of the holding ponds or effluent streams and eventually'off plantsite.
3.5.3.1.6 Deleted l
O 3.5-31
SAR-IORTS January 19,1996 Rev.2 3.5.3.1.7 Fire Protection Systems Several facilities are protected by sprinkler systems; however, many of the outlying facilities have no fire protection systems o her than fire extinguishers (see Table 3.5.3-1).
3.5.3.2 Shipping and Receiving / Stores l
3.5.3.2.1 General The broad range of activities associated with an industrial facility the size of the Portsmouth Gaseous Diffusion Plant (GDP) necessitates the use of large quantities and numerous types of materials and equipment. Storage buildings and storage yards are required to accommodate these materials.
The Shipping and Receiving / Stores Operations consist of the receiving of all shipments of material for the operation of the GDP. The shipments are received, checked, and logged by Materials Control personnel, if inspection is required, this is handled by a quality control group with assistance from the Materials Control personnel. The material is then moved to its designated location.
l 3.5.3.2.2 X-746 Materials Receiving and insnection The X-746 Building is the general receiving area for the majority of the shipments of material for the GDP Flant.
The building is single-storied and roofed with steel framing and metal siding. It is located on the east side of the plar.t complex, south of the X 720 Building and north of the X-104 Guard Headquarters.
3.5.3.2.2.1 Waste Disnosal Systems The X-746 Huilding drains are connected to the plant sanitary disposal and drainage systems. The discharge of any of the hazardous materials listed in Table 3.5.3-2 (located at the end of this section) into these systems is prohibited. Accidental spills are reported immediately to the Plant Shift Superintendent, Em ironmental Compliance, and Utilities Operations.
l 3.5.3.2.2.2 Fire Protection The building i protected by an automatic fire sprinkler system and fire extinguishers.
3.5.3.2.2.3 Ventilation and Heating Systems There are hand-operated roof vents in the receiving and freight areas of this building. The facility is controlled by air condition and steam unit for office area and space heaters in the freight area.
O 3.5-32
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.i December 19, 1907 lO SAR-PORTS Rev.15 4.1.1.8.2 The Oxidizine effects of CIF, i
Explosions are produced whea Cl), w.
m contact with materials containing carbon and hydrogen, such as hydrocarbon oil or grease. The fonnation of oxides of chlorine (vesy unstable compounds) is a i
source of danger in the manipulation of CIF.
3 These compounds are obtained by the reaction of CIF with water, and certain oxides. The danger is 3
gteater if the CIF and water are present in approximately egnimolecular proportions.
3 Rcactions with water:
4 CIF + 31I 0 -> 6 liF + 3 F/l + 2 C!3 3
2 2 CIF + 2110 -> 411F + ClO + CIF 3
2 2
Materials which may be in the -nrichment system that will react with CIF include water, aluminum 3
oxide (A1:0 ), oil or grease, and R il4. CIF reacts rapidly or explosively with all of these compounds at 3
3 cascade temperatures except R ll4 with which there is only a slight reaction. (There is a substantial The flames of CIF have a very high intensity due to the heat reaction between CIF and R il4 at 750'F.)
3 3
of reaction. (They are comperable to an oxyacetylene flame.)
Reference:
Chlorine,Trifluoride by L. M.
Vincent and J. Gillardeau, Report CEA 2360.
f)
Although CIF does not react wit' oxygen or nitrogen, it is capable of reacting with most other 3
V elements, including the noble gases.
4.1.1.8.3 CIE3 storage Chlorine TriF :oride (ClF ) is delivered as a liquid on plantsite in 8 inch cylinders (Reference 10).
3 These cylinders are placed in the CIF storage rooms in the X-330, X 333 and X 742 Dvildint The 3
- buddy system" between operators is used when any activities are performed in the storage rooms.
The cylinders are connected to a feed manifold and the connections are leak rated wi'h CIF to 3
determine if the toxic gas reacts with the connector gaskets. This is accomplished with the cylinder valves clcsed. After it is determined that no leaks exist the high pressure cylinder contents are transferred to a 2000 ft) tank where the gas pressure is maintained below 12.5 psia.
These operations are performed with two operators present with one doing the work while the other ooserves. The operators wear neoprene gloves and face-shields while performing operations in CIF storage 3
facilities.
4.1.1.9 Natural Phenomena The natural phenomena which may affect cascade cperations are seismic events, floods, tornados and lightning. Lightning can interrupt power and cause a partial power failure. Ilowever, lightning is not foreseen as a credible problem which would lead to the release of UF to the atmosphere.
6
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4.1 - 51
SAR PORTS May 31,1996 Rev.?
4.1.1.9.1 l'loods The Portsmouth Gaseous Diffusion Plart ch/ation is soproximately 100 feet above the Scioto River flood plain. This elevation rules out the pcssibility of the plant flooding frem this source. The other possibility of flooding would be from nutximum precipitation (cloudburst) over plantsite. This could flood the ground floor of the process buildings. Accidents from ground floor flooding would be categorized as industrial accidents.
4.1.1.9.2 IcInadLu Tornadoes have been infrequent near plantsite during the past 20 years. The plant is in an area where tornadoes do occur. The effects of tornado winds on the Uranium Enrichment aystem may be only to remove the roef from the process buildings; however, the damages could include suprured pipe from fallen debris.
The probability of a tornado strikiag a point within the six county area surrounding the Portsmouth plantsite has been calculated to be low.
4.1.1.9.3 Seismic The prebt.bility of a seismic event affecting plant operation is an evalusion base earthquake with a 0.0$g ground acceleration and a return period of 237 years. The affect of such an earthquah has been presented in Case R 14.
4.13.10 Safety Systems A safety system must reduce the probability or mitigate the cons quence of exposure to criticality or the release of toxic / radioactive rnaterial to the atmosphere.
4.1.1.10.1 Deleted l
d.1.1.10.2 Criticality Alarms The criticality alamu are needed as safety systems to initiate evacuating the area of personnel in case of criticality. Also, pievention c.f additional perronnel from entering the building during criticality is justification for calling these alarms safety systems.
4.1.1.10.3 E Detection and Alarms The UF detection and alarm systems provide a warning to personnel to evacuate the area of GF releases which will mingate the effects of a release. These systems will be designated as safety systems on cells operating above atmospheric pre;sure.
4.1 - 52 l
l l
SAR PORTS December 19,1997 Rev.15 r
SECTION
4.1 REFERENCES
- 1. Shively, D. hi.. Risk of Inhabiting the PCF During a Criticality, GAT-T 3264 (UNCLASSIFIED),
x Goodyear Atomic Corporation, Piketon, Ohio, December 16,1983.
~
- 2. Westfall, R. bl., et al, Characterization of Low Power Criticality Events in Low-Enriched Gaseous Diffusion Plant Operations, ORNL/CSD/INF-84/1 (UNCLASSIFIED), h1artin-h1arietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
- 3. Westfall, R. hi. and Kr;ight, J. R., Radiation Levels in a Gaseous Diffusion Plant Assuming a low-Enriched Criticality Event Corresponding to the ANSI-Standard hiinimum Accident of Concern, K!CSD/Thi-85 (UNCLASSIFIED), Union Carbide Corporation Nuclear Division, Oak Ridge National laboratory Oak Ridge, Tennessee, Febntary 1984.
- 4. Regulatory Guide 3.34. Revision 1, Assumotions Used for Evaluating the Potential Radiological f,muggences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant. U.S. Nuclear Regulatory Commission, Washington, D.C., July 1979.
- 5. Le' Corche' P. and Seale, R. L., A Review of the Experiment Performed to Determine the Radiological Consecuences of a Cr,)lcality Accident Y/CDC ; 4 NCLASSIFIED), Union Carbide Corporation, Nuclear Division Y-12 Plant, Oak Ridge, Tennessee,1973.
- 6. hia' enfant, Q. E., and corchand, ll.ht.,
- Facility Description of a Solution Critical Assembly:
SilEBA," Transactions, Winter hieeting, Volume 39, pages $55-557,1981, American Nuclear
(
Society, La Grange Park, Illinois.
- 7. Jones, S. A., Project Summary Reoort. Criticality Experiments on Low Assay SolutionL GAT-T 3100 (UN"LASSIFIED), Goodyear Atomic Corporation, Piketon, Ohio, September 21.1981.
- 8. Newton, C. E., llansen, A.11., and Fithian, C., An Assessment of the hiinimum Criticality Accident of Concern, il&R 82 2 (UNCLASSIFIED), ll&R Technical Associates, Inc., Oak Ridge, Tennessee, April 1981.
- 9. Investigation of Freon Discharge Incident-Cell X-33 6-8, GAT il27, October 17, 1985,
- 10. Duncan, D. T., et. al, Process llazard Anah sis for DOE X-742 Chlorine Triduoride Storage Area and ID, Plant Vendor Transportation of Chlorine Triduoride Cylinders, P}lA X 742, PrShi Corporation, Knoxville, Tennessee, h1 arch 1996.
O
+.1 - 99
l SAR IOR',S September 15,1995 Rev,1 2
e e
(Blank Page) t I
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SAR PORTS September 15, 1995 n
(v)
Rev.I The inadvertent exposure of a radiographer has been reduced to a very low probability by several standard industrial safety f,:atures. The x ray vault contains a fail safe audible warning alatm and flashing lights inside and outside the vault; they are activated 20-se :or ',s before the x ray tube head is energized.
A fail safe scram button is provided inside the vault, and it's location is clearly indicated so that the tube can be de-coergized before x rays are produced, thus preventing accidental exposure. The only access to the vault is beside the rmtrol panel and in full view of the radiographer, and the door has a kill switch that de-energizes the tube head when opened. The tube head can be re-energized only when the access door is closed and only at the control panel by the operator. All safety features are checked prior to each x ray session. The radiographers are trained in safety and radiography and wear radiation badge and dosimeters to detect radiation exposure.
Toxic chemicals are used in the processing of radiographs. Protective equipment, approved operating procedures, and adequate ventilation mitigate the toxic hazards of photographic chemicals.
4.5.2,5 Criticality Fissionable material in the form of U 235 can be found in purity and quantity in the X 710 Building to make a nuclear criticality possible. All containers are stored and handled in a nucien safe manner, llowever, a critical excursion emanating from somewhere within the X 710 Laboratory must l
be considered as a residual rtsk even though the probability of such an incident is extremely low.
1 O
At the onset of a nuclear criticality, the radiation clusters will sound an audible alarm. This U'
alarm initiates evacuation from areas 500 feet from the detected excursion. Due to the high populatior, density of the X 71013uilding during 0-shift and the speed of the event, several significant radiation exposures can be expected with possibly some fatalities, llowever, the personne! affected by the nuclear excursion will have to be in the near vicinity of the event (within 50 feet) due to the very localized nature of the criticality and the compartmentalization of the laboratory building.
4.5.3 Reccising and Storage facilities Accident Analysis The Receiving and Storage operations (non-contaminated) do not mvolve any significant safety hazards. The majority of the faahties do not contain any hazardous materials. The exceptions are brie 03 described below.
Large quant: ties of lithium hydroxide (LiOH), a caustic matenal, are stored in the X-744 K.S.T.
and U warehouses. It is possible that this mataial could be released to the environment. The oft-site
~
consequences of a LiOH release would be an envirciunental insult rather :han a safety hazard.
Small quantitics of several hazardous wastes are stored in the X-752 Hazardous Waste Storage Area, There is a low to extremely low probability that some or all of this material could be released as the result of fire, earthquake, or other natural phenomena. As with the LiOH, the off-site consequences of the release would be an environmental insult rather than a safety hazard, n
)
V 4.5 9
SAR PORTS December 19,1997 Rev.15 A discussion of the hazards associated with the use of CIF, is contained in the Cold Recovery l
(Sectica 4.1.4).
4.5.4 Communications and Data Processing Accident Analysis The Communications and Data Processing Systems do not use or contain fissile, radioactive, fiammable, or toxic materials. No significant hazards are involved with the systems operations.
4.5.5 Adtninistrative Facilities Archlent Analysis With the exception of the X 103 Auxiliary Office Building, the Administrative Facilities do not use or contain fissile or hazardous materials.
The 173-millicurie Radium-226 source used in the X 103 Badge Calibration Vault room is considered a hazardous material. These hazards are mitigated by an underground storage vault, shielded walls and door, access control, and infrequent use (once per month). Additionally, all passageways to the source storage vault have warning lights and bells actuated when the source is being used. The minor hazards associated with this source are very localized, and have no off site effects. No safety systems or special r.dmini;trative controls are required for safety.
4.5.6 IIcalth Protection Facilities Accident Analysis The operation of the health protection facilities at the Portsmouth Gaseous Diffusion Plant is similar to the operatloa of any other medical facility, and involves only standard industrial hazards and hazards associated with the use of X ray equipment which are routinely encountered and accepted by the public.
No safety systems or special administrative controls are required for safety.
4.5.7 Rish Assessment The general support facilities have an associated risk. The risk is, for the most part, extremely small and consists primarily of routme safety, industrial hygiene, and health physics considerations. The majority of this risk was identified in the X 710 Laboratories.
The laboratory risk is due to two complementing factors: the large shift (especially O-shift) population, and the reliance on laboratory safety procedures and personnel education to control hazardous operations. Ilowever, this risk is no greater than that found in other analytical laboratories. The risk associated witt. laboratory operation caruwt be reasonably reduced without hindering laboratory operations.
Tne laboratory risk is mitigated by administrative controls, laboratory procedures, housekeeping, and operator judgment. Installed in these facilities sie criticality alarms which only reduce the consequences of e criticality after the event has occurred.
O 4.5 10
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Emergency Plan PORTS Septembe r 15,1995 p
Revs 1 g
- 1. FACILITY DESCRIPTION USEC leases portions of I' ORTS from the Department of Energy (DOL) and conducts uranium enrichtnent activities at the plant. These uranium enrichment activities are regulated by NRC. DOE and DOE contractors also conduct activities and opeate other facilities at the site that are not regulated by the NRC.
1.1 DESCRIPTION
OF NRC REGULATED ACTIVITIES The primary mission of the plant is the urichment of uranium 'vith the isotope necessary to produce fuel for nuclear reactors (2"U) using the gaseous diffusion process. A basic summary of this process follows.
PORTS reenives uranium in solid UF. form, which is shipped by truck and rail in 10 or 14 ton cylinders in accordance with DOT regulatior.
Gaseous UF. is pumped through conveners that contain a barrier material with millions of microscopic tales. Because the "U atoms are lower atomic weight than"2 U atoms, the " UF passes 2
2 through the holes more readily.
k The gaseous Giffusion enriclunent process employs a series of compressors and converters to enrich UP. in "U. The fundamental building block of the process consists of a compressor and a converter that 2
form a stage. Stages are grouped together to form cells. The cells are then interconnected to provide what is known as a cascade. The compressors, which are driven by electric motors, are used to circulate the process gas and maintain flow through the cascade. The converters contain porous tubes called barriers through which the process gas is diffused. In each anverter, a portion of the process gas diffuses through the barrier and is fed to the next higher stage, with the undiffused gas %g recycled to the next lower stage The diffused stream is slightly enriched in the 235 isotope, w : the undiffused portion is slightly depleted in the 235 isotope to the same degree. Each stage also cona.s a gas cooler to remove the heat of compression from the process gas and a control valve for process control. The process is repeated through numerous cells unth the Osired enrichment level is reached. Separated 2"U or depleted material is stored at the plant for isture use or disposition.
Possession litnits for UF. are sumraarized in Table 1 1.
Numerous substances associated with the enrichment process could pose hazards if they were released to the envirotunent. Only a few of these substances are highly toxic and present in large quantities at the plant. Based upon the hazards and consequence analyses reflected in the DOE Safety Analysis Report, USEC has concluded that any haurdous release would most likely involve one or more of six substances. The following is a brief description of each of these substances, the manner in which it is used in the enrichment process, and the locations where it is stored or used at the plant.
f pg
Emergency Plan. PORTS December 19,1997 Rev.1$
1.
Uranium Hexafluoride (UF). In gaseous and liquid forms, UF could present a hazard. Material in these forms is primari!y located in the X-326, the X 330, and the X-333 process buildings, the X 343 feed vaporization and sampling facility, the X 344A toll enrichment facility, the X 342A facility, and the X 345 facility.
2.
C/dorine Tr#1uoride (CIF). Chlorine trifluoride is delivered to tne plant in 150 pound cylinders and is stored in 150 pound cylinders at the X 742 Facility and in two 2,000-ft' storage drums located in the X 330 and X 333 process buildings. Chlorine trifluoride is used for cell treatment on an as needed basis in the process buildings.
3.
Nitric Acid (HNO) Nitric acid is transported to plant site by tank truck and is stored in two tanks, 1,500 gallon and 3,000 gallon located 60 feet east of X-705 and directly north of the incirientor building. Nitric acid is pumped to a 100-gallon storage tank in X 705 and gravity fed to various systems, such as small parts, the neutralization sink, and spray tanks. Nitric acid is also stored in glass botti s in the X-720 toxic materials storage area. Nitric acid is used to decontaminate uranium-contaminated metal surfaces and in electroplating.
4.
Fluorinc (F). Fluorine is generated from hydrogen fluoride gas in.X 342A and is pumped to 2
storage tanks in the X-342B facility. The three F storage tanks measure 8 feet in diameter and 2
20 feet long. Fluorine is used to pacify and condition metal surfaces prior to exposure to UF, and for cell treatment on an as needed basis.
5.
Chlorine (Cl).
Chlorine is primarily used for the treatment of the sanitary water supply at IORTS. An important function of the water treatment process is pre-chlorination for removal of disease-carrying organisms Chlorine on plant site is found in the water treatment plant (X-611) in 150 pound cylinders, in the recirculating cooling water treatment pump houses (X-630 and X-633) in I ton cylinders, at the sewage treatment plant (X-6619) in 150 pound cylinders, and in bulk storage on the X 533 pad and the X-742.
6.
Hydrogen Fluoride (HF). liydrogen fluoride is used in the production of fluorine. Liquid liF is I
delivered to the plant in 850-lb cylinders and is stored in the X 342A Feed Vaporization and Fluorine Generation Facility. There, the liF is vaporized and piped to four fluorine generators, where it is dissociated to produce fluorine.
Table 12 shows the major locations and quantities of hazardous chemicals descritnd above.
1.2 DESCRIPTION
OF FACILITY AND SITE PORTS is located at latitude 39'00'30" north and longitude 83'00'00" west measured at the center of the plant on a 3,708-acre tract in Pike County, Ohio, one of the state's lesser populated counties. The plant s.ite is located between Chillicothe and Portsmouth, Ohio, approximately 70 miles south of Columbus, Ohio. Figure 1-1 shows the regional area surrounding the plant.
O l-2
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Emergency Plan PORTS December 19,1997
' Rev.15 Table 12. Hazardous chemicals.
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Name Locations Typical Quantity Uranium Hexafluoride X-326, X 330, X 333, X-400,000,000 pounds 342A, X 343, X 344A, X 345, X 745 storage locations
- Chlorine Trifluoride X 330, X 333, X 742 4,000 pounds
- Nitric Acid X 705, X 720 30,000 pounds Fluorine X-342A,-X 342B 700 pounds Chlorine X 533, X-611, X-6619, 50,000 pounds X-630, X 633, X 742
- Hydrogen Fluoride' X 342A 5,000 pounds a
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Emergency Plan PORTS September 15,1995 Rev.1 Table 13. Sununary of Continuous Monitored Stack and Vent Characteristics Dl%IENSIONS Coztrol I~EOW RATES De5 ice I.D.*
lleight (ft.)
Efficiency (in.)
LOCA710N Abose Abo 5 e Vol.
Vel.
hionthly Vol.
Percent Roof Ground (ACl3D (Ft./hlin.)
(SCIY
(%)
N 326 Top Purge Vent (X 326 P-2799/
5 103 165 379 2779 1.47E 4 07 99.99 X 326 Side Putre (X 326.P-2798f 5
103 165 626 4588 2.46E + 07 99 99 X 326 E Jet (X 326 P-616f 5
103 165 869 6372 3.546 + 07 99.99 X.330 Cold Recovery Vent (X 330-P.272) 4 12 78 415 4753 1.57E + 07 90 X 333 Cold Pecovery Vent (X-333 P-852) 3 15 97 429 8746 1.50E + 07 99 X.333 liuildmg Evacuation Vent (X 333 P-856) 4 15 97 917 10,508 2 27E+06 90 X 333 Seal Exhaust Systern Area 1 (X 333 A 851) 6 6
72 58 293 2.20E + 06 99 X 330 Seal Exhaust System Area 2 (x.330A.262) 4 6
72 37 424 1.71 E + 06 99 X-330 Seal Exhaust System Area 3 (X 330-A 279) 4 6
72 30 347 1.22 E + 06 99 X 326 Seal Edaust System Area 4 (X-326 A 512)
E 6
72 30 87 i 22E+06 99 X 316 Seal Edaust System Area 5 (x.32o A.328) h 6
72 27 77 1.35 E + 06 99 X 320 Seal Ethaust Systern Area 6 (X-326 A 540) p 6
72 29 83 1.20E + 06 99 X-344 Oulper (X.344 P-929) 1h 8
58 450 322 2.81 E + 06 99 01 D. represents imide diameter.
- hlonthly volumes are based on an as erage of data f rom 1992 to 1994
- These three sents physnally dacharge throu;t. toe mwrtonnected pqvs of the lis.ed damensions.
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Emergency Plan PORTS December 19,1997 O
Rev.15 2.1.4 Riorine (F) Release Flucrine generated from ilydrogen Fluoride gas in the X 342A is pumped to storage tanks in the X 342F 'a'ility. Fluorinc is used to pacify metal surfaces prior to exposure to UF. and for cell treatment on an am ied basis. Because fluorine is an extreme irritant and readily combines with water vapor to form liF. tucates could result in personal injuries or fatalities onsite. Ilowever, because of the small quantities of material available for releases, no hazards are projected to offsite populations.
2.1.5 Chlorine (Cl ) Release 2
Chlorine is used in water treatment. Chlorine is located at the water treatment plant (X 611) and at the sewage treatment p; ant (X-6619) in 150 pound cylinders, in the recirculating cooling water treatment pumphouses (X 630 and X 633)in 1. ton cylinders, and in bulk storage on the X-533 pad. A cylinder or valve tupture could release Cl gas and in a worst-case scenario the resulting plume could be carried 2
offsite. Unprotected on and offsite personnel could experience serious injuries or fatalities. Sheltering citizens in the path of the plume would greatly mitigate the consequences.
2.1.6 Ilydrogen Fluoride (liF) Release t
liydrogen fluoride is stored in the X 342A area. Releases could result in on-and offsite fatalities or serious injuries.
Possible releases could be attributed to valve failure, pigtail failure, or temperature / pressure control failure.
2.1.7 Chlorine Trifluoride (CIF ) Release 3
CIF stored in cylinders and drums in the X-330 arid X 333 process buildings and the X 742 could l
3 be released if a valve breaks and ignites nearby cylinders. Dispersion estimates indicate this release could result in an offsite hazard. Sheltering citizens in the path of the plume would greatly mitigate the consequences. Fatalities or serious injuries could be experienced in an unprotected onsite population.
2.1.8 Other Nonradioactive llazardous Material Releases Other nonradioactive hazardous material releases from offsite sources may pose a threat to the safety of personnel and impact plant operations and activities.
2.1.9 Natura! Phenoinena and Fire Natural phenomena, such as earthquakes, tornadoes, severe storms, and fires may cause varying degrees of damage to the plant. In themselves, these types of events may disrupt or threaten plant operations sufficiently to warrant the declaration of an emergency. These types of events may result in a nuclear criticality or hazardous materia' release as described earlier in this section.
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Emergency Plan PORTS September 5,1997 Rev.12 2.1.10 Security Related Events Security related events, such as bomb threats, civil disturbances, extortion, and hos. age taking, could also result in personal injuries or fatalities to on-and offsite personnel.
2.2 DETECTION OF ACCIDENTS AND OTIIER EMERGENCIES The PCF, located in building X 300, which also houses the PSS. cascade controller. and oper. tors, monitors, coordinates, and/or controls critical plant processes, power distribution, utilities, communications, plant alarm systems, and emergency operations.
Each process building has an area control room (ACR), which permits operators to monitor process equipment, make changes in operations, and take corrective action to mitigate alnormal operating conditions.
Systems are designed to ensure that the consequences of a major malfunctior, are mitigated prior to any adverse effect on the plant population and the general public. These in:lude UF detection equipment and associated alanns, a criticality accident alarm system (CAAS), automstic sprinkler systems, various chemical detectors, and other alarm systems. Alarm systems are under cont'nuous observation by operations personnel stationed locally, in the ACRs, and in the PCF, and are tested semi-annually.
Descriptions of the various alarms and detection methods for the hazards that have been analyzed follow.
2.2.1 Nuclear Criticality Previous plant analyses show the risk associated with inadvertent criticality is extremely low.
Analyses of possible criticality incidents reveal that both a fast-burst type reaction and a low power incident have little effect on personnel except those in the immediate vicinity of the incidert Criticality alarms are installed in facilities containing fissile materir.1 as escribed in Section 5.2 of the SAR. The criticality detection system consists of locator clusters aad an alarm system. When a criticality accident alarm activates, a radiation alamiis generated actuating building local horns and lights as well as audible and visual alarms in the PCF. Alarm activation requires evacuation of personnel trom the affected area to a designated monitoring station that is loca ed a safe distance from the area. On the basis of the alarmed location, the PSS or designee can direct the actions necessary to respond to the accident.
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1 Emergency Plan PORTS Decen.ber 19,1997 p
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The major physical components of the fire protection system consists of water supply system, pumps, sprinkler systems, and fire alarms. Mobile fire equipment is maintained onsite to support fire Oghting activities and back up the fixed fire suppression systems. The fire services, using test frequencies established in group procedures, oversees the testing and inspection program for the fire protection system and equipment. Further information pertaining to firc protection is provided in Section 5.4 of the SAR.
In the event of an ongoing release of radioactive or hazardous material, the goal is for personnel to escape from the vicinity without personal contact with the release :nd assist in ensuring that non-response personnel do not enter the vicinity of the release. In some cases, approved engineering controls are used to mitigate the effects of a minor release, i.e., gulpers at the autoclaves and on the cylinder valve change cart. In other cases, authorized members of the ERO shall take the appropriate actions to reduce and contain the release.
5.4 PROTECTIVE ACTIONS During emergencies, the PSS or designee or CM must determine the best possible means to limit exposure of onsite ani of fsite personnel to potential or actual threats, such as radioactive or toxic materials that may be accidentally released to the environment. Guidelines are provided to limit the exposure of personnel in the case of accidental releases to the environment. These guidelines are prescribed according to potential heahh effects and are called PAGs for radioactive materials and ERPGs for hazardous
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materials. Specific EPIPs have been developed for the protection of emergency workers and other onsite z
and offsite personnel.
This section describes the protective actions developed to limit exposure of plant personnel and the public following an emergency. The protective actions to be implemented onsite are the responsibility of qualifted plant personnel. In the event of an emergency the PSS or designee notifies onsite agencies such as the Ohio Nationt.1 Guard, Deferse Logistics Agency, and Ohio Valley Electric Corporation via telephone. The time of notification will be affected by the location of the emergency and the impact on the operations of these organizations. The appropriate offsite authorities are responsible for providing offsite protective actions.
5.4,1 Onsite Protecthe Actions 5.4.1.1 Alerting Whenever it is determined that a threat or potential threat to the safety of personnel on the DOE reservation exins, the PSS or designee directs that persons on the DOE reservation or within a specified area are alerted, whichever is appropriate. Alerting is accon.plished by use of the PA system, plant radios, telephones, or if required, by tunner. Transients on the DOE reservations (i.e. commercial dehveries, school buses, area residents) will be directed to exit the reservation. The alerting time will depend upon the severity and location of the threat to safety.
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Emergency Plan PORTS January 19,1996 Rev.2 5,4.1.2 Personnel Evacuation and Accountability Protective actions for onsite personnel (including visitors and contractor personnel) include alerting, assemb. og and accounting for, sheltering in place, evacuating, monitoring, and decontaminating. As previously described, the plant's primary concern is to minimize the impact on plant personnel and the general public.
1.
Evacuation. When it is determined that a threat to the safety of plant personnel exists, the PSS or designee or Chi may order an evacuation of personnel from affected plant areas. Criteria l
that should be considered before ordering an evacuation includes wind direction, wind speed, and location of the emergency. Evacuation will be implemented immediately in the event of actuation of the radiation and gas reiease alarm systems. The evacuation alarm and announcement, including any special instructions, is sounded o/er the PA system, plant radios, or other plant communications systems as appropriate.
At the discretion of the PSS or designee or Chi, plant personnel, visitors, and centractors will l
evacuate to a designated assembly point or monitoring station or be sent to reception centers.
Personnel are sent to assembly points during non radiological events. Ilowever, personnel report to a monitoring station if the event involves a radiological release. Refer to Figure 12, PORTS Plant Layout, for loca m. of monitoring stations, if a site wide evacuation is ordered, personnel report to offsite reception centers.
The PSS or designee will provide directions on the specific evacuation routes. The l
appropriate selection of an assembly area and evacuation route is based upon plant conditions, wind direction, and weather. Evacuation to offsite reception centers is generally oy individually owned vehicles.
As discussed in this section, emergencies include natural events as well as radiological / hazardous materials inciients The procedures to be followed in these evacuations are included in the EPIPs, including designation of assembly areas Provisions are made for consideration of impediments to evacuation caused by weather conditions, traffic, or radiological / hazardous materials release.
When sheltering personnel would greatly mitigate the consequences of an emergency, the Chi or PSS or designee reconunends to shelter-in-place anJ plant personnel l
are notified over the PA system, plant radios, or other plant communications systems as appropriate.
2.
Accountabili*y. In an emergency, one of the most probable protective actions for site personnel is evacuation of a building or area. Provisions for determining and maintaining the accountability of personnel are established. Search and rescue operations may be initiated if a person is determined to be missing.
hionitoring stations are identified in Figure 12. Personnel po mitted unescorted site access are provided training on their assembly / accountability roles and responsibilities.
To ensure proficiency, site personnel participate in annual retraining and periodic evact'ation and accountability drills.
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, Emergency Plan-PORTS December 19,1997
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When releases oesur onsite before the evacuation of non-essential personnel can be completed, personnel are routed ta the established evacuation / decontamination monitoring stations.
Onsite contamination control measures are described in other plant procedures.
5.5.1 Emergency Radiatior Exposure Control Program 5.5.1.1 Radiation Protection Program This section of the plan describes measures that are used to provide necessary assistance if individual, are injured or radiologically exposed or contaminated, b
Li certain emergency situations, the acceptance of above-normal radiation exposure may be
}
warranteu. '.i may not be possible to perform ccrrective/ protective actions while maintaining exposures a
belaw Umits specified in 10 CFR 20.
Although an emergency situation transcends the noimal requ5ments for limiting exposure, there I
are EPA reccmmended levels of exposure acceptable in emergencie (ret fccth in Section 5.5.1.2).
y Ttree categories of risk versus benefit are considered:
1.
Saving of human life ar.d reduction ofinjury, t
2.
Protection of health and safety of the public, and
(
3.
Trotection of property.
l The CM authorizes emergency workers to receive emergency doses above the established plant administtr/ive exposure linuts Egosure guiddines for emergency situmions are described in the following section.
5.5.1.2 Exposure Guidelinos Exposure guidelme> fer radiological emergencies are consistent with the U.S. Environmental Protection Agency's PAGs summarized in EPA 400-R-92-001, Manual of Protective Action Guides and Protective actions for Nuclear incidents. Exposure guides for toxic / hazardous chemicals h:ve been incorporated 'n EPIPs and are unststent with the ERPGs established by the a;nerican Industrial Hygiene Association for ntremely hazardous chemicals.
The following are radiation e:.posure guidelines:
Doses to all workers during emergencies to the extent practicable, are hmit?d to 5 rem.
Justifications f r exposing workers beyond the 5 u m limit include the presence of conditions that prevent the rotation of workers or other commonly used dose-reduction methods.
Emergency exposures are limited to 10 rem for protecting valuable r gerty.
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Emergency Plan - PORTS December 19, 1997.
Rev.15 Emergency exposures are limited to 25 rem for life saving activities and the protection of large
+
populations.
Emergency exposures in excess of 25 rem are authorized only for rare situations when such exposure is unavoidable in order to carry out a lifesaving operation or to avoid extensive exposure h]
to large populations. Persons undertaking any emergency operation in which the dose will exceed 25 rem to the whole body do so only on a voluntter basis and with full awareness of the risks involved, including the numerical levels of Jose at which acute effects of radiation will be incurred and the numerical estimates of the risks of delayed effects. Details for providing this information and for documenting an individual's walingness to volunteer are in an EPIP.
For I.azardous material / toxic gas release incidents, the IC and emergency response personnel assess l
the incident scene and take appropriate protective and mitigative response actions based on available information, such as material safety data sheets, emergency response guidebooks. professional industrial hygiene guidance, and meteorological conditions.
During a UF. release onsite, the resulting hydrolysis products are uranyl fluoride particles and hydrogen fluoride (liF) gas. The radiotoxicity of uranium is insignificant when compared with the chemical toxicity of IIF and uranium. Therefore, exposure control during an emergency involving UF.
.U will be based on chemical toxicity.
W JY 5.5.1.3 Monitoring 1i~
Provisions have been made for 24-hour-per-day capability tu determine uranium uptakes received by emergency personnel. Personnel who may be required to respond to the scene of an emergency are required to wear thetmoluminescent dosimeters (TLDs). Issuance of self-reading dosimeters and maintenance of interim emergency whole body dose records are addressed in an EPIP. Emergency worker dose records are maintained in accordance with radiological protection procedures.
l 5.5.2 Decontamination of Personnel Onsite personnel decontamination facilities for emergency conditions are equipped with decontamination material and necessary supplies. The primary means of decontamination is through the use of equipment and supplies carried on emergency response vehicles. Other decontamination facilities are locatM in other areas of the plant. The decontamination facilities have provisions for disrobing, collecting contaminated clothing, showering of contaminated personnel, and donning clean clothing. Onsite personnei contain and process contaminated wastes.
Personnel exiting contamination control zones, contamination areas, high contamir.ation areas, or airborne contamination areas are monitored for contamination. The instruments used for this monitoring procedure are portav,e contamination survey instruments. if personnel contamination is detected, preventive measures are initiated to mitigate the possibility of the spread of contamination.
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