ML20100H291

Environ Assessment of Operation of Onsite Low Level Radwaste Holding Facility (Interim Storage) at Susquehanna Steam Electric Station, Final Rept

ML20100H291
Person / Time
Site:	Susquehanna
Issue date:	07/31/1981
From:	Hawley K, William Kennedy, Murthy K Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:
Shared Package
ML20100H280	List: ML20100H279 ML20100H291 ML20105B046
References
08336, 8336, NUDOCS 8504090090
Download: ML20100H291 (150)

Text

{{#Wiki_filter:f,. - a 3 ATTACHMENT 1 i FINAL REPORT Environmental Assessment of l i the Operation of On-Site Low-Level Radioactive Waste 1 I Holding Facility (Interim i Storage) at Susquehanna Steam l Electric Station l ) l ~ July 1981 b l Prepared for t Pennsylvania Power and Ught Company b !1 Allentown, PA 18101 under Contract 23112 04789-E 1 ? i r. r a b. ii @Ba11eBe E Pacific Northwest Laboratories 8 l b I" y u i 8504090090 810803 PDR ADOCK 05000387 X PDR

{ i I l, j i I l .) ~-~ l n - * *N FINAL REPORT I-ENVIRONMENTAL ASSESSMENT'0F THE OPERATION OF ON-SITE LOW-LEVEL RADI0 ACTIVE WASTE HOLDING FACILITY (INTERIM STORAGE) AT SUSQUEHANNA ~- STEAM ELECTRIC STATION } I K. S. Murthy K. A. Hawley W. E. Kennedy . R. F. McCallum I. C. Nelson 4 - ~ " I D. G. Watson f. July 1981 3 [ Prepared for l Pennsylvania Power and Light Company P Allentown, PA 18101

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a.'.. r ACKNOWLEDGEMENTS e The authors wish to thank E. M. Toomey for editing the report and Toni Jewell for the preparation of the report. j. e h e na e o e m 9eeh e-9 e e ....... _......... -,. ~ .e,

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k CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1 i 2.0 PURPOSE AND NEED 3 3.0 PROPOSED ACTION 4 3.1 GENERAL DESCRIPTION AND LOCATION OF THE FACILITY 4 i 3.2 WASTE DESCRIPTION 7 3.3 DESIGN FEATURES 8 3.4 FACILITY OPERATION 12 3.5 SAFETY AND SECURITY. 14 ~ 3.6 EXPOSURE TO OPERATING PERNNEL 16 4.0 ALTERftATIVES TO THE PROPOSED ACTION 17 4.1 THE NO ACTION ALTERNATIVE (OFF-SITE DISPOSAL) 17 4.2 0FF-SITE OPERATION OF A LOW-LEVEL RADI0 ACTIVE WASTE HOLDING FACILITY 18 4.3 ON-SITE INTERIM STORAGE IN EXISTING FACILITIES 18

5.0 DESCRIPTION

OF AFFECTED ENVIRONMENT 20 6.0 ENVIRONMENTAL CONSEQUENCES T ~ . ~ '; 25 S.1 ENVIRONMENTAL CONSEQUENCES OF OPERATION OF THE LOW-LEVEL RADI0 ACTIVE WASTE HOLDING FACILITY (PROPOSED ACTION) 25 6.2 ENVIRONMENTAL CONSEQUENCES OF ALTERNATIVES TO THE PROPOSED ACTION 26 7.0 COST-BENEFIT DISCUSSION 28 8.0 COMPLIANCE WITH APPLICABLE LAWS AND REGULATIONS 30 REFERENCES 31 APPENDIX A: ' SUSQUEHANNA STEAM ELECTRIC STATION LOW-LEVEL RADWASTE HOLDING FACILITY TECHNICAL CONCEPT - JULY 1981 I . A-1 .n. a-wee e e ha 1ii 8 i

L FIGURES Page. 1 Plan View of Susquehanna Steam Electric Station 5 2 Artists Rendering of Low-level Radioactive Waste Holding Facility 6 3 Proposed Action for Storing Low-Level Radioactive Waste at Susquehanna SES 10 4 Susquehanna Site and Its Immediate Surroundings 21 %^ l P .e w g +- $f iy

i ~ GLOSSARY AND ABBREVIATIONS ALARA - a,s icw as reasonably achievable BWR - boiling water reactor CFR - Code of Federal Regulations cfs - cubic feet per second CST - condensate storage tank DAW - dry active waste DER - Department of Environmental Resources (Pennsylvania) DOLI - Department of Labor and Industry ha - hectare HEPA - high efficiency particulate air (filters) -Hz - hertz (cycles per sec'ond) Liner - a steel inner container that is designed to fit in an NRC certified shipping cask LLRW - low-level radioactive waste LLRWHF - Low-Level Radioactive Waste Holding Facility 6 tal - megawatt (10 watts) mrem - millirem (10-3 rem) msl - mean sea level NRC - Nuclear Regulatory Ccomission NUREG - Nuclear Regulatory Commission Publication Applicant - Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. pH - measure of alkalinity-acidity R - roentgen rem - special unit of dose equivalent . R/h - roentgen per hour SES - Steam Electric Station V E'

s 1.0 EXECUTIVE

SUMMARY

This is an environmental assessment report on the proposed action to store waste in an on-site low-level radioactive waste holding facility (LLRWHF) at Susquehanna Steam Electric Station (SES) Units 1 and 2. This facility is intended to be used for contingency storage in the event that off-site disposal facilities are not available. The analyses and conclusions in this report are based on data provided by the Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (Applicant). Units 1 and 2 are each designed to generate 1050 MW of electricity; the first unit is anticipated to be in operation within the next two years. The proposed action, described in detail in Chapter 3.0 of this report, involves the operation of a 3 3 facility sized to temporarily store about 1700 m /yr (60,'000 ft /yr) of low-level radioactive waste (LLRW) generated from both units. This waste will be packaged in steel liners or in 55 gallon steel drums, and stored for up to four years per unit or until the waste can be shipped to off-site disposal sites. The holding facility was not planned at the commencement of construction of Units 1 and 2 because at that time off-site disposal sites were available. In recent months however, waste quantities that will be accepted at off-site disposal sites have been restricted. Developing circumstances.suggest that adequate off-site disposal may not be available when required for Susquehanna SES. The LLRWHF will measure about 88 m x 73 m (290 ft x 240 ft) and occupy a land area of about one hectare (ha) (2' 5 acres). The Applicant shall comply with all applicable existing laws, regulations and permit requirements for the operation of the facility to protect public and occupational health' and safety. j .The estimated cost of the facility will be $23 million with an annual estimated cost of $350,000 for operation and maintenance. If off-sit'e storage were not l available and in the absence of this facility, the operation of Susquehanna SES Units 1 and 2 might have to be suspended until adequate storage became available. The estimated economic impacts from suspending operations would include:

1) cost of replacement power at $600 million per year for both units, and 2) loss of revenue needed for payment of the fixed annual cost of

$475 million for carrying the investment. Other impacts would include temporary loss of regional employment and possible interruption of power supply with consequent impacts on the regional socioeconomics. l 1 L

J j. I Impacts from facility operation to the general public would be substan-- tially less than applicable limits and insignificant in comparison to the natural background radiation dose. The estimated radiation dose to a hypothe- ' thical individual continuously residing at the site boundary would be less than 5 mrem /yr. However, based on professional judgement, it is reasonable to expect that essentially no radioactivity would reach the site boundary from a potential ~ accident such as a waste container rupture. The occupational radiation doses will be maintained as low as reasonably achievable (ALARA) within applicable limits (10CFR20). It is concluded from this assessment that the potential environmental impacts of operating the LLRWHF would be insignificant. o 8 e S e h

2.0 PURPOSF AND NEED The Susquehanna SES is located about 8 km (5.0 mi) northeast of Berwick, Pennsylvania, and consists of two 1050-MW boiling water reactors (BWR). The need for the power that will be generated at this facility has already been addressed in a Final Environmental Impact Statement (NRC 1981. NUREG 0564) l relating to issuance of an operating licensing by the Nuclear Regulatory Commission (NRC) for operation of the Susquehanna SES. Routine operation.and maintenance of the plant would result in the genera-tion of LLRW. It consists of a variety of radioactively contaminated material such as paper, rags, protective clothing, etc., which are collectively described as dry active waste (DAW). Low-level waste also includes process wastes such as filter treatment sludges, spent filter cartridges, and spent ion-exchange resins. Based on the experience at other BWR operating plants, the Susquehanna SES is expected to produce about 1700 m3 (60,000 ft ) of LLRW per operating 3 year for two units (assuming no allowance for volume reduction other than trashcompaction). At the time the Susquehanna SES was planned LLRW from operating power reactors in the eastern U.S. was packaged and shipped to a low-level waste disposal facility operated by Chem-Nuclear Systems, Inc. at Barnwell, South Carolina. However, in recent months, significant restrictions have been placed on the amount of packaged LLRW that will be accepted at the Barnwell site. The long-term availability of alternative disposal sites in Beatty, Nevada and Hanford, Washington has also become less certain. Although deliberations are being held across the country for establishing state and regional disposal sites, operation of additional LLRW sites is uncertain. In view of these uncertainties, the Applicant proposes to establish an on-site LLRWHF with the capacity to temporarily store.LLRW g'enerated for up to four reactor-years per unit of operation. The use of this facility would only be necessary if off-site disposal were not available. Permanent retention of these wastes in the proposed facility is not planned. The only wastes to be temporarily stored are those low-level solid wastes that are incidental to the production of power bf the Susquhanna SES; acceptance of any off-site generated wastes for storage in this facility is not contemplated. 3 i. emens e = m

w t 3.0 PROPOSED ACTION This chapter describes the proposed action for interim storage of LLRW generated.by Units 1 and 2 of the Susquehanna SES. Appendix A contains more detailed information. 3.1 GENERAL DESCRIPTION AND LOCATION OF THE FACILITY The proposed action is defined to include the following: interim storage of LLRW generated by four reactor-years of operation per e unit interim storage period not to exceed four years per unit operation of the facility as necessary to hold the LLRW when licensed e off-site disposal facilities are unavailable The facility is designed to house the low-level wastes inside an uninsu-lated, sheet metal building with the solidified wastes placed within shielded concrete vaults and DAW stored outside the vaults in drums and metal boxes. The primary function of this metal building will be to provide weather protection for the stored wastes and to provide all-weather loading and off-loading capability. The primary function of the concrete vaults will be to provide radiation shielding around the solidified wastes. The LLRWHF will be located approximately 300 m (1000 ft) due west of the cooling towers for Units 1 and 2 (see Figure 1). The grade elevation of the LLRWHF is approximately 215 m (700 ft) ms1. This elevation exceeds both the probable maximum flood elevation of 167 m (548 ft) msl and the maximum his-torical flood elevation of 158 m (517 ft) msl (NRC 1980). The overall dimensions of the facility will be 73 m (240 ft) by 88 m (288 ft) with a centerline elevation of 13 m (42 ft). In addition, a control and equipment room 6 m x 9 m (20 ft x 30 ft) will be located adjacent to the north wall of the facility approximately 5 m (16 ft) from the northeast corner - of the structure (see Figure 2). ,s 4 %m

T 1 II A M 20 [ 5 2 6 9 10 3 22 7 4 13 21. I4 16 15 17 18 Eey 1 - Rad Waste Building 12 - North Gate House 2 - Unit 1 Turbine Building 13 - Combination Shop 3 - Control Structure 14 - Warehouse 4 - Unit 2 Turbine Building 15 - Change House 5 - Diesel Generator Building 16 - Project Office 6 - Unit 1 Reactor Building 17 - Welding Shop 7 - Unit 2 Reactor Building 18 - South Gate House 8 - Engineered Safeguards and 19 - Security Control Center Service Water Pump House 20 - Unit 1 Cooling Tower 9 - Acid Storage Building 21 - Unit 2 Cooling Tower 10 - Pump House 22 - LLRWHF 11 - Service and Administration Building FIGURE 1. Plan View of Susquehanna SES e l 5 l O o 1_

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= .l. , ) 3.2 WASTE DESCRIPTION The LLRWHF is designed to store dry, solid LLRW and dewatered solidified (cement) LLRW generated by the Susquehanna SES. The facility may also be used to temporarily store l'arge pieces of contaminated plant equipment. The LLRWHF will not be used to store gaseous wastes nor wastes containing free-standing liquids. Low-level radioactive waste is defined as contaminated material containing sources of radioactivity dispersed in small concentrations throughout large volumes of inert substances, and has no free-standing water. It generally consists of paper, high efficiency particulate air (HEPA) and cartridge filters, rags, clothing, small equipment, and other dry materials. Solidified waste is defined as wet, dewatered waste in the form of evapora-tor bottoms, resins, and sludges that have been immobilized in cement and con-tain less than 0.5 percent free-standing water by waste container volume or 3.8 liters (1.0 gal) of liquid in the waste container. Estimates of the annual waste generation rates for the two units range 3 (40,000 to 63,000 ft ) based on operation of both units. 3 from 1100 to 1800 m For this report a nominal figure of 1700 m3 (60,000 ft ) was chosen; Table 1 3 gives a breakd'own of the low-level waste volume by source and waste type. After four years of operation the two Susquehanna SES units will have generated approximately 6800 m3 (240,000 3 ft ) of LLRW that will have required storage; the capacity of the LLRWHF will be about 6800 m3 (240,000 ft ), 3 TABLE 1. Estimated Annual Low-Level Waste Generation Rate for Operation of Both Units 3 3 Source Waste Tvoe m /yr ft /yr r-- - DAW--compacted 500 17,800 DAW--noncompactible 150 5,000 Evaporator' bottoms (25 wt".) 510 18,000 Resins 90 3,200 Waste sludges 450 16,000 TOTAL 1,700 60,000 7

r 3.3 DESIGN FEATURES General Design Considerations The LLRWHF will be sized to store wastes generated by four yeais each of the Susquehanna SES Units 1 and 2. The design life of this facility will be 40 years. The LLRWHF will be a Non-Seismic Category I structure (i.e., one whose failure would not release significant amounts of radioectivity and would not require reactor shut down). The facility is not designed for the effects of a flood since the elevation exceeds the maximum probable flood level. However,, it is designed for a maximum rainfall intensity of 4.2 x 10-5 m/s (6 in/hr) and consequent surface run-off. ~' Architecture The LLRWHF will consist of a storage vault within the confines of an unin-sulated steel-framed, metal-sided structure. The walls of the vault will be reinforced concrete. The vault will be covered with removable, reinforced-concrete shield panels to permit the loading and off-loading of the waste containers. '~ A curb around the perimeter of the building will contain any liquid such as rainwater or fire-sprinkler water that may be introduced into the building. The curb will be designed to retain the volume of fire protection water that would be released if all the sprinklers were actuated for one-half hour. A system of floor drains and sumps will ensure drainage of additional flow. This system will route such water to a sump in the off-loading area so that it can be sampled and collected for disposal. Ramps will be provided for vehicular traffic over the curb.. The floor, curbing, sumps, and shield walls of the facility will be coated with a decontaminable, material to a height equal to the height of the curbing. r-Health and Safety Requirements The LLRWHF is designed to maintain off-site (beyond the site boundary) doses within the guidelines of 10CFR50 and on-site radiation exposure within the guidelines of 10CFR20. In both instances, the facility will be designed t 8 i' a

to maintain dose rates ALARA as outlined in Regulatory Guides 8.8 (NRC 1979) and 8.10 (NRC 1977). Exposure of on-site workers will be minimized by the use of concrete shielding around the stored material, shielded loading equipment, and controlled access td the facility. Since no radioactive materials would be released off-site, dose rates would be minimized through the use of shield-ing, distance, and the self-shielding properties of the storage containers. Provisions for the removal of equipment exhaust fumes are included in the facility design. The building ventilation system will be structured so that the flow of air draws exhaust fumes away from operators working on the floor of the facility. Containers The containers to be stored in the LLRWHF will be designed to preclude or reduce uncontrolled releases of radioactive materials during handling, trans-portation, or storage. Container material will conform to the requirements established in NUREG-75/087, Section 11 (NRC 1975). The waste container materials will not support combustion. All material stored in the facility will be packaged in a form that allows for eventual off-site ' shipment and per-manent disposal. All containers will be decontaminated for shipping to the standards of 49CFR 173.397 and/or other applicable burial site criteria before leaving the Rad Waste building and transported to the LLRWHF. Three types of containers may be used:

1) liners for the cemented waste, 3 (7.5 to 200 ft ) which will be stored inside the 3

ranging from 0.2 to 5.7' m 3 3 . vault area, 2) 55-gallon drums (0.2 m or 7.5 ft ) for the DAW that will be 3 (96 ft ) for the 3 stored in the open trash area, and 3) steel boxes 2.7 m DAW that will also be stored in the open trash area (see Figure 3). Loading and Off-loadino Systems The loading system (i.e., forklifts for DAW, a remote controlled crane for cemented waste), will be capable of handling the cemented waste and DAW, and transporting within the facility, placing, retrieving, and reloading. This system will also have the capacity to lift, transport, and replace all movable and temporary shielding devices,

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.l WASTE TYPE WASTE TREATMENT STORAGE LOCATION COMPACTION (COMPA TIBLE) p----- I OPEN STORAGE DAW PACKAGE WITH AREA l I l l I l (NONCOMPACTIBLE) MINIMAL TREATMENT l g LLRW EVAPCRATOR HOLDING I . 90TT0fa5 FACillTY l l ~ l l SHIELDED l SP~NT CEMENT RES'NS IMM0BillZATION VAULT STORAGE g g AREA g J '1LUDGES FIGURE 3. Proposed Action for Storing Low-Level Radioactive Waste at Susquehanna SES The loading system for cemented wastes will allow the transfer of these ~ wastes from one area of the building to another as the vaults are filled. This 1 capability will also include the trash storage area in the event the vault storage is expanded into this area at a later time. The loading system will also be capable of retrieving dropped and damaged waste containers for repack-aging or other disposition. Trash Restraining System A trash restraining system will be designed to prevent any trash con-tainers from.being bicwn out of the confines of the facility during a tornado ) with up to a 134 m/s (300 mph) velocity. This will be accomplished through the use of a nylon netting or other suitable ma'erial, enclosing the trash t storage area and secured to anchors in the foundation and/or floor slab. All tornado wind loading is transmitted directly into the anchors. The system is designed such that failure of the building structures will not tend to cause l failures of the restraining system. Floor Drains System Under normal conditions 'there there will be no tree-standing liquids inside the building. Therefore, any free-standing liquids entering the facility would 10

i come from such sources as fire protection water, minute amounts of liquid from a breached cement container, rainwater or snow melt from roof leakage, cooling. system or fuel leakage from equipment inside the facility, snow brought in on vehicles, and liquids used for decontamination of containers before shipment, should that ever become necessary. All such liquids will be considered contami-nated until verified otherwise. The floor drain and curb system will collect any liquids spilled on the floor of the facility. The system will route all drain's to one or more collec-tion sumps located along the periphery of the building. Each sump will be equipped with liquid-detection devices that signal the main plant and facility control rocms whenever any liquid enters the suirps. Sampling of the liquids in the sumps may be performed from either inside or outside the building. These liquids may be pumped to portable tanks from either inside or outside the building. However, no permanent pumping equip-ment or piping is connected to the main plant. Ventilation System Two basic functions of the ventatilation system wil1 be: 'l)to remove' ~ noxious or irritating exhaust fumes when internal combustion engine-powered machinery operates inside the facility, and 2) to prevent excessive heat buildup from the roof in the summer. The system will move air generally in an upward direction away frem operators. Air inlets will be designed to evenly distri-bute air entering the facility even when it is closed. Inlets will be placed to prevent accumulation of snow and other substances from restricting the flow of air and to prevent these substances from being drawn into the facility. The system will exhaust through a damper tha.t opens when the fans are in opera- . tion and closes when the fans are shut down. r-Electrical System A power system will supply AC power to all the electrical loads in the facility at the appropriate voltage. These loads will include the lighting system, the ventilation system, the overhead crane, the power operated door, the fire detection system, and the fire protection system. The AC power :ystem equipment will be located in an enclosed space outside the facility storage .,3 11 de ,p m.

area. Convenience outlets for 125-eV, 60-Hz service and 480-v power and weld-ing receptacles will be installed in the control room, the electrical equipment room, and the loading area. All electrical equipment including cable contained within the storage area will function normally under all environmental conditions existing inside and outside the LLRWHF. As a result, provisions for a back-up electrical system to be used in the case of failure of the main system are not planned. The grounding system will establish a building ground grid to connect electrical and mechanical equipment and structures, raceways, duct banks, and other required grounds to the existing exterior station grounding system. Lighting The facility lighting will be in service only during loading or off-loading. The lighting will be adequate for safe, efficient handling of the waste con-tainers in the off-loading area, the dry trash storage area, and for safe and efficient handling of the shielded vault cover blocks. There will be no per-manent lighting installed inside the shielded vault area. Lighting for this area will either be provided on the container handling equipment or will be portable lighting. 3.4 FACILITY OPERATION The facility's operating function will be to temporarily store LLRW on-site until it can be shipped to an off-site location. The facility will be occupied only during periods of loading and off-loading activities. Storage of the low-level wastes will be segregated, the cemented wastes being placed in shielded vaults and the trash being stored in the open storage area. Fur-ther segregation will also occur to the extent practicable within both the vault and open storage areas to take advantage of the self-shielding proper-ties of the contained material. Wastes in the shielded vaults will be arranged with containers having a contact dose rate 13 R/h stored next to the vault walls and on the top layer. Containers with a contact dose rate ?_3 R/h will be stored inside this perimeter. Waste stored in the open storage area will be arranged with containers having contact readings i l mrem /h stored around 12 4

n p i e the outer perimeter of the storage area, containers with 5.10 mrem /h stored on top, and containers reading > 10 mrem /h stored within this perimeter. Loading the LLRWHF with solidified waste will generally proceed as follows. A loaded truck will leave the Rad Waste Building (see Figure 1) with the waste containers and will travel approximately 460 m (1500 ft) to the LLRWHF. These containers will have been examined for surface contamination l prior to transport and will be in a condition that would allow for their ship-ment to a permanent disposal site. Depending on the level of radioactivity, the LLRW may be shielded during transport. ~ The loaded truck will enter the LLRWHF in the off-loading area. If the truck is transporting cemented wastes, it will stop in the overhead crane pickup area. All personnel must then either move a safe distance from the container or get behind shielding. The container is lifted off the truck and moved to the approximate storage location., Then the auxiliary hook removes the appropriate shield panel. The container is then moved into proper position and lowered into the storage vault. The removed cover is 'then replaced, where- ~ upon the operation is complete Waste trash loading will take place in a r(milar fashion. The truck with the 0.2-m3 (55-gal) drums or the 2.7-m3 (96-fd) steel boxes on pallets will enter the facility. The truck will stop with the drums adjacent to the trash storage area. They will be unloaded with a forklift. Depending on the dose rate from the containers, the forklift may be equipped wtth shielding for the driver. Removal of the LLRW from the facility will occur generally in the reverse order of these steps. In the event of a fire in which water or other fire fighting materials are introduced into the facility, these items will be considered contaminated until proven otherwise. Prior to off-site shipment of the containers, all containers will be inspected for damage and surveyed for residual surface contamination. In the unlikely event that radioactive contamination is discovered, the container would be transported back to the main plant for decontamination. 13 CU.?G

\\ 3.5 SAFETY AND SECURITY _ The discussion of safety and security will be addressed in the context of five separate topics: ~ security system e

• radiation monitoring system shielding e

fire detection / protection system o communications system. Security System The entire LLRWHF will. be 43 m (140ft) from the security fence that encloses this and other plant buildings. The facility will be designed with Personnel security provisions as an extension of the existing plant system. access doors will be provided for operational requirements, and to satisfy All safety standards; they will be equipped with magnetic card readers. accesses to the facility will be monitored to provide an alarm in the event an unauthorized entrance into the facility should occur. Radiation Monitoring System The radiation monitoring system will be designed to monitor the general area radiation levels at various locations in the trash storage area, the off-loading area, and the LLRW control rocm. The readout will be located in the LLRW control room. Shielding The LLRWHF will contain two types of shielding: 1. fixed shielding for the in-place stored materia,1, transient shielding to protect the operator while the waste is moved " 2. from the vehicle in the off-loading /on-loading area to the storage location. The fixed shielding will consist of concrete vaults for the cemented waste, concrete walls in the storage area for the trash, and concrete wall shielding for the control room. The storage vaults will consist ,1 14 .l M

r j. of reinforced concrete walls and reinforced concrete cover panels. The trash storage,' area walls will consist of reinforced concrete along the north and south walls. The control room will have reinforced concrete along the south and west walls. The transient shielding for the cemented wastes will consist of a portable shielding device attached to the loading crane. This device will protect the operator while the containers are being moved from the trrc.k in the off-loading area to the place of storage. The transient shielding for the DAW will consist of either a shielded forklift or other shielded vehicle to be provided as necessary. Fire Detection / Protection System The fire protection design will be based on a combustible loading of 1790 kg/m2 (1200 lbs/ft ). The facility will be equipped with a fire 2 detection system. The entire structure will be equipped with a dry pipe sprinkler designed to deliver 1.0 x 10-2 3 2 m of. water per m of floor sur-f face (0.25 gal per sq. ft). The sprinkler heads will be rated at 141 C (286 F) which is in accordance with standard practices. Water will be supplied from the existing fire protection system by a 0.25-m (10-in.) mortar-lined, ductile-iron fire protection line. The water 3 supply will be capable of supplying a minimum of 0.1 m /s (1500 gpm) at 6.8atm(100 psi). Fire hydrants will be provided and equally spaced at 91 m (300 ft) intervals around the building perimeter. In addition, the ventilation system will be equipped with instrumentation for the monitoring of smoke, and smoke detectors will also be placed at other locations in the facility. If smoke is detected, the ventilation system will automatical,1y shut down and an annunciator will be actuated in the control rooms of the main plant and the LLRWHF. D 15 l

t. 4 ll* Comunications Systems The communications system will allow two-way conversation and paging between the main plant.and the facility. It will have at least one station for paging and conversation in the off-loading area. It will have enough speakers inside the storage area to insure that paging or alarms can be heard when the facility is at full capacity. It will also have one station for paging and conversation in the facility control room. One telephone with a plant extension will also be provided in the control room. All communica-tions cables will be in rigid steel conduit. 1 3.6 EXPOSURE TO OPERATING PERSONNEL The LLRWHF is designed and will be operated to minimize the exposure to operating personnel while providing sufficient facility access. This will be accomplished by providing the necessary radiation shielding (see previou: q section), by using current design technology and by using appropriate adminis-trative controls to ensure that radiation levels are at or. below applicable limits (10CFR20) for all phases of operation. Exposure of on-site workers and operating personnel will be minimized through the use of shielded waste storage areas, shielded on-site transport vehicles, and shielded remote load-ing and unloading equipment where required. The technical design and operating procedures are designed to maintain occupational doses ALARA, as discussed in Regulatory Guides 8.8 (NRC 1979) and 8.10 (NRC 1977). The loading and unloading procedures will be designed to take advantage of the fixed and transient radiation shielding and remote facility operations to help reduce occupational exposures. The number of operating personnel will be minimized to further eliminate unnecessary radiation exposures. Other administrative procedures will be designed and used to control loitering in the area immediately outside of the facility to prevent unnecessary inadver-tent radiation exposures. The dose equivalent rates at any accessible point outside of the storage facility will not exceed an average of 0.5 mrem /hr as required by 10CFR20. g 16 F.

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4.0 ALTERNATIVES TO THE PROPOSED ACTION ~ t t. This chapter discusses three alternatives to the proposed action. I Lp. -[ 4.1 THE NO ACTION ALTERNATIVE (OFF-SITE DISPOSAL)

1 I

The no action alternative is defined as the use of the Susquehanna _SES [' design-basis, one-month,~ on-site storage capacity for interim storage of LLRW. i .. j i (NRC1981,NUREG0776). Under this alternative no other alternatives, l f including the proposed. action, would be considered. The success of this alternative would depend on the continued availability of off-site com-j mercial LLRW disposal sites. The Susquehanna.SES plant design provided j very limited storage capacity based on this assumption. Any interruption in shipment of LLRW could potentially shut the plant down. l ? The positive aspects o'f the no action alternative would include a savings t. of approximately $23 million in LLRWHF construction costs and $350,000 annual ~ operating and maintenance costs. An additional benefit may include minimizini[ 'SES occupational exposures through prompt off-site shipment of LLRW. 'l ~ In recent years, LLRW disposal has been hampered by the unavailability of shipping casks, transportation problems, and restrictive disposal quotas f' (McArthur 1979). Space for waste disposal is expected to become increasingly scarce in the next few years as restrictions either have been placed or are placed on the amount and type of LLRW the three disposal sites (Barnwell, i " South Carolina; Beatty, Nevada; Hanford, Washington) are willing to accept. Finally, development of new disposal facilities is not expected to begin until 1986(NWPA1980). As a consequence, interruptions in off-site shipments of l radioactive wastes are possible, and operati.on of the station could be severely , limited. Even if the plant were shut down it would continue to generate some amount of radioactive waste requiring storage and ultimate disposal. Therefore, ~ the no action alternative would limit the electric power generating capability of Susquehanna SES and would not resolve the problem of LLRW storage. 17 Y i r, .. e ... ~ , i'g.~B' Z,*

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q,- a Y 4.2 0FF-SITE OPERATION OF A LOW-LEVEL RADI0 ACTIVE WASTE HOLDING FACILITY Off-site storage facilities would consist of the same facilities and would require the purchase of property for a site and also require obtaining addi-tional - permits. The land-use impact from such a site woul'd have to be evalu- -[ 'ated and problems resolved prior to construction. Radiological and other moni-toring programs independent.of the Susquehanna SES would have to be established. - The increased waste handling and transportation requirements-for off-site stor-- age of the waste would add extra costs (in terms.'of both dollars and radiation exposure) above' those for on-site storage. - Off-site interim storage of the LLRW is concluded to be a less desirable alternative to the proposed action because all effects of the proposed actions would result plus those that would _ be specific to a new construction site and waste handling and transportation. a 1 4.3 ON-SITE INTERIM STORAGE IN EXISTING FACILITIES The use of existing structures;on-site for interim storage of the LLRW ' s' a third alternative to the proposed action. This option would potentially i fsave the-estimated $23.million dollars required for construction of an on-site LLRWHF. Several areas were considered as potential sites for interim storage - of the waste. Most areas identified as prospective storage locations would already be ' l~ -in use as equipment laydown, washdown, access, or_ storage areas. In addition, E extensive handling of-the LLRW containers and-special lifting devices would be required so that some locations could be used. Other prospective sites demand j removal of hatches, and evacuation of transfer areas. Some locations, in par. ticular the refueling floor, would require outside transfer of containers. In the event of a forced outage, storage of LLRW on the refueling floor would I hamper work by requiring additional shielding or removal of-waste to permit worker access. -These requirements could extend the duration of the outage. ' Multiple storage-locations would make accountability of the LLRW inventory difficult. Storage of the LLRW in-station would increase the radiation exposure of plant personnel. The overall background radiation levels in the plant would ~) 18 F e So 44 L l

7 .l. 7 increase. Multiple storage locations dictate expanded radiation surveillance which means greater human contact and increased dose. Nonradiation zones could be changed to radiation zones to accommodate the waste. The overall impact of interim in-station storage of LLRW would be to increase the radiation dose to employees..This would not be consistent with the policy of maintaining doses ALARA. t S t'* i- -4 5 19

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1 L I

5.0 DESCRIPTION

OF AFFECTED ENVIRONMENT -I i . The Susquehanna SES site is located (NRC 1981 NUREG 0564) on a 435-ha .(1075 acre) tract of land on the west bank of the Susquehanna River in Salem Township, Luzerne County, Pennsylvania,(Figure 4). It is about 8 km '(5 mi) northeast of Berwick and 32 km (20 mi) southwest of the city of ] Wilkes-Barre. The topography near the site is characterized by moderate-to- 'levations range from steep slopes directed toward the river on both banks. E 151 m (496 ft) above msl at the river to 213 m (700 ft) msl at the proposed ~ LLRWHF'to over 275 m (900 ft) msl in the northern 'section of the site. The waste holding facility site will be approximately 61 m (200 ft) msl above the river level. The area typically has hot humid summers and cold winters with considerable amounts of snow. The average annual air temperature 'is 9 C (48 F) with average temperatures ranging from -3 C to 22 C (0 to 72 F). Annual average precipitation is about 88 cm (35 in.) distributed fairly evenly through-out the year. Prevailing winds are from the W and SW, but during some years this may be reversed (Dames & Moore 1980). Wind direction is influenced.by the generally NE-SW oriented valley near the site. The average wind speed'is about 7.3 km/h (4.5 mph). The calculated tornado frequency at the site is 4.6 x 10~# yr. / Between 1953 and 1974, 35 tornados were reported in the 160-km2(62-sq.mi) area containing the Susquehanna SES; between 1871 and 1977 ten hurricanes passed within 30 lei (50 mi) of the site (NRC 1979). The Susquehanna River the principal source of station cooling water is located about 1220 m (4000 ft) east of the LLRWHF. The river flows 68 km (42 mi) through Luzerne County with an average gradient of 0.18 m per km 3 (0.95 ft per mi). Average annual flow is 38'7 m /s (13,650 cfs). Maximum 3 flows of.9880 m /s (349,000 cfs have been measured at the site and minimum 3 flows of less than 15.6 m /s (550 cfs) have been observed at Wilkes-Barre. River elevations during historic floods at the Susquehanna SES range from 155 'to 157 m (510 to 517 ft) above ms1. This is below the 213 m (700 ft) elevation of the LLRWHF. .g 20 I 8. a

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/ g SERWICK I 6LOCA $8URG ppggggg '\\ ,,tt7 p. e+> ./ LEWISBURG e WEST HAZELTON j E / 'SUNSURY 8 MCA00N / I N \\ $HENAN00AH e FRACKVILLE s [ SAINT CLAIR \\ CATASAUQUA M POTTSVILLE jph SETHLEH r N, i* t/ ALLENTOWN 5 0 10 STATUTE MILIS FIGURE 4. Susquehanna Site and Its Immediate Surroundings Susquehanna River water quality near the Susquehanna SES site is generally acceptable. Acid mine drainage, much of which reaches the Susquehanna by way of the Lackawanna River, tends to produce high concentrations of iron and at times low pH. Iron concentrations in the river near the site at times exceed state water quality standards (1.5 mg/1). The generally high acid mine runoff tends to impair the river ecosystem. The high iron levels are not acutely 95 21 i . Q.

V I l' toxic to most river organisms but they increase turbidity and the precipitation of iron compounds which in turn reduces light penetration and alters the bottom substrate. These changes generally reduce the production of aquatic plants and ~ bottom dwelling animals. The pH of the Susquehanna River varies from 6.0 to l 8.5. Annual river temperatures range from 0*C (32*F) to 29.4*C (85*F) and dissolved _ oxygen concentration ranges from 5.6 to 15 mg/1. q Little use is made of surface water, except for that used by the power station, within 3.2 km (2 mi) of the site. The first municipal water user down' stream from the station is located approximately 45 km (28 mi) away at Danville, Pennsylvania. Fish in the Susquehanna River do not seem to be directly affected by the - high iron concentrations. The most abundant species are.the white sucker, spot-fin shiner, bluegill, white crappie and pottail shiner. None of the fish are on the U.S. Fish and Wildlife Service's Rare and Endangered list, but two ciscos, a species classified as rare by the Pennsylvania Fish Commission have been caught during recent sampling in the river. These fish probably entered the river near Nanticoke by way of Harvey's Creek, the outlet of Harvey's ' Lake. The. Pennsylvania Fish Comission introduced the cisco into Harvey's Lake from 1969 to 1972. Because cisco prefer deeper lake waters, there is little likeli-hood that a population of cisco has been or will be established in the river as a result of movement from Harvey's Lake. Ground water is generally of acceptable quality at the site but may be rather hard (up to 545 mg/l total dissolved solids) in some areas near the station. Estimated ground water travel time to the Susquehanna River is 8.8 years. Depth to the water table is 2.1 to 7.9 m (7 to 26 ft) at the-Susquehanna SES and there are 185 wells with 3.2 km (2 mi) of the site. Esti-3 mated withdrawal of ground water is 212 m3 (7485 ft ) per day within 3.2 km ~ (2 mi) of the station. Twenty-three species of amphibians and reptiles are found in the region. No threatened or endangered species are found near the site. y 22 m e e

j+' i j One-hundred and twenty-eight species of birds have been recorded near the i Susquehanna SES. Most of these are songbirds. The major migratory birds fly, 'l way is located to the east, nearer the Atlantic Ocean. Twenty-six species of mammals live near the site and none are considered threatened or endangered. Rodents are the most abundant group. Larger game and fur-bearers include opossum, cottontail, woodchuck, raccoon, muskrat, 'f and gray squirrel. Muskrats are trapped extensively in the area. Whitetail deer are the most important large game species in the area. The region is relatively free from earthquake activity and seismic hazard. No capable faults exist within 8 km (5 mi) of the station. The maximum expected earthquake intensity would be VI to VII on the Modified Mercali Scale. The site is within Zone 1 seismic risk. Soils in the vicinity of the Susquehanna 3ES are mainly of glacial origin and are used more for grazing and timber production than for farming. The dominant vegetation on the land near the site is made up of maple, birch, cherry and oaks with an understory of spicebrush, blackberries, viburnum, witch hazel, laurel, dogwood and rhodedendron. None of the plant species in the area are classified as threatened or endangered. Land use near the-site is varied. About 228,000 hectares (570,000 acres) or 11 percent of the land in Lurerne County is used for agriculture on about 500 farms. Farming occupied about 0.8 percent of the county's workforce in 1975. Approximately 40 hectares (100 acres) of Susquehanna SES floodplain land is farmed by a tenant farmer. Much of the surrounding area that is not cultivated is covered with woodiands and scrub brush. A number of small industries are located within 8 bn (5 mi) of the site. These i$clude textile and clothing manufacturing, meat and a,nimal productsI'~~ ' ~ ~~ ~ concrete products, manufacturing, and lumber production. Theneardstindustry is,about 2.4 km (1.5 mi) NNE of the site and cmploys approximately 490 persons. Outdoor recreation facilities at the Susquehanna SES includes'a small lake for fishing and boating, native trails and a picnicing area. Also a num-ber of recreational facilities are near the site. The Applicant maintains ';;;c -j 4 u

n i, Riverland's Park near the Susquehanna SES. Within a 16 km (10 mi) radius there is.one county park, two Girl Scout camps and three privately owned camps. l, Recreational fishing is popular in the Susquehanna River along the east bank l of the river near the site. The nearest boat launching facility is about 3.2 km (2 mi) south of the site. No commercial fishing exists within 80 km i (50 mi) of the Susquehanna SES. In Luzerne County, hunting harvest for both ~ I small game mammals (squirrels and rabbits) and deer make up about eight percent of the state total. Waterfowl are not abundant near th' site and are of minor e value to local hunting. l The Susquehanna River has no ccmmercial navigation; transportation routes are mainly by highway, railroad and air. Three Salein Township roads and U.S. Route 11 pass within 790 m (2600 ft) of the center of the Susquehanna SES exclusion area. The Delawa're and Hudson Railroad line passes approximately 2 km (1.25 mi) east of the station and the Conrail line is located about 0.8 km (1/2 mi) east of the center of the site. The nearest operating airports are i the liazleten Municipal Airport and the Wilkes-Barre Scranton Airport located 19 and 45 km (12 and 28 mi), respectively, from the station. The population in the vicinity of Susquehanna SES is low. The steep ' sloping terrain and the-present land use for agriculture limits human habita-tion. In 1976 about 2420 persons were living within the icw population zone (within three miles). This is projected to increase to 4670 by the year 2020, the expected end of operation of Units 1 and 2 of the Susquehanna SES. In ~ 1970 the population within 80 km (50 mi) of the SES was about 1,420,000. The year 2020 population estimate in this area is 1,582,000. Berwick is the largest borough (1970 population of 12,274) within 1,6 km (10 mi) of the site.

Hazleton, about 24.km (15 mi) from the Susquehanna SES had a 1970 population of about.

30,000. No schools, hospitals, and state or municipal parks.are located within the low population zone. g 24 i

I i 6.0 ENVIRONMENTAL CONSE0VENCES Environmental consequences of the operation of the Susquehanna SES LLRWHF are presented and contrasted with the consequences from several alternatives to the proposed action. l 6.1 ENVIRONMENTAL CONSEQUENCES OF OPERATION OF THE LOW-LEVEL RADI0 ACTIVE WASTE HOLDING FACILITY (PROPOSED ACTION) During routine operation, no significant environmental consequences should occur related to the facility. No gases or liquids will be stored in the facility. Therefore, no releases of radioactive gaseous or liquid effluents will occur during routine operation. The only expected radiation exposure pathway for a hypothetical member of the general public is exposure from penetrating radiation originating within the facility either as direct radiation or as sky shine. The facility ha' been designed to limit the whole-body dose equivalent. rate to less than s 5.0 mrem /yr to a hypothetical individual residing continuously at the site boundary. On that basis, the annual off-site dose equivalent to the public from operation.of the LLRWHF would be less than that from operation of the Susquehanna SES. The dose equivalent from naturally occurring sources in this geographical area is about 100 mrem /yr to which the operation of the facility would make no significant contribution. In the event of a waste container rupture, small amounts of radio- ~ active material may be released.into the building. By the nature of.the packaged waste, and the facility design, the contamination would be essen-tially retained within the facility. '~ No known endangered or threatened species as listed by the Department of Interior's list of endangered, threatened wildlife and plants (U.S. Federal Register 1979) are on the LLRWHF site. The plant has'no 'ihteraction with the -~ wet lands aspect of the Susquehanna River flood plain. 4 g 25 t I

j+ 1 1 6.1.1 Irreversible or Irretrievable Commitment of Resources for Operation .i of the Facility The only irreversible or irretrievable connitment of resources for opera-tion of this facility would be fuel, electricity, and manpower. These would I constitute an ' insignificant addition to those already committed for the opera-l tion of the station proper. 6.2 ENVIRONMENTAL CONSEQUENCES OF ALTERNATIVES TO THE PROPOSED ACTION \\ Although none of the previously discussed alternatives to the proposed ll action are believed to be viable, a brief comparative discussion is provided. ll - 6. 2.1 The No Action Alternative While the no action alternative would eliminate the minor operational .p impacts and further reduce the already trivial doses to the hypothetical resi- { ~+ dent at the site boundary from the LLRWHF, the dose to in-plant workers would be increased because of the need to store in-plant until space was ful.ly occupied. If off-site disposal facilities were available, occupational doses [ resulting from placement of wastes in an on-site LLRW facility would be eli-minated for the Applicants (however, similar doses would be incurred by the disposing contractor staff). Assuming that the LLRW will eventually be sent to a waste disposal site, direct off-site shipment would result in less han-dling and also reduce its attendent potential for accidents. ~This alternative is, however, not viable since the plant could not operate more than one month without some ad'ditional storage capability in the event that off-site storage were not available and adequate off-site disposal facilities are not expected to be available when needed for LLRW from the Susquehanna SES. -i i 6.2.2 Operation of an Off-Site LLRWHF The environmental consequences of an Applic' ant owned and operated LLRWH'F off-site would be the same as those for the on-site facility plus the following: Additional-public exposure (however trivial) would be incurred as 'a result of shipment of wastes to the off-site location; the additional exposure would be proportional to the distance traveled. g 26

j

Because of the time needed to obtain the required permits, an off-site facility would probably not' be ready in time to receive wastes as gen-erated, thus increasing in-plant worker exposure because of the need to store waste in-plant. 6.2.3 On-site Storage in Existing In-Plant Facilities The alternative of on-site storage in existing in-plant facilities would merely postpone construction of the LLRWHF given the present uncertainty in off-site disposal. The alternative would result in reduction of the already smal1 doses from the proposed action to the public. This dose reduction, how-ever, would be more than offset by an increase in dose to the station work-force. Because in-plant storage, if feasible, would not permit station opera-l tion beyond a few months, a more detailed discussion of environmental conse-quences is believed unwarranted. l e g,g. 44 m 9 e p. a 4I e e .e eem e -e =e M-t' l l i l L

a 4 7.0 COST-BEllEFIT DISCUSSICN 1 No anticipated significant environmental impacts and costs are associated l with the operation of a LLRWHF; also, there are no significant direct environ-mental benefits deriving from its operation. t l The estimated capital cost of the LLRWHF at the Susquehanna SES site is l' approximately $23 million (1982 dollars). The annual levelized facility cost (e.g., interest, taxes, and depreciation) at an assumed 15.85% annual rate, i is estimated to be $3.6 million, and operating and maintenance costs are esti-mated at 'approximately $350,000. Total annual cost is thus estimated to approxi-mate $4.0 million. I l If an off-site disposal facility were available at which all waste could i be disposed (currently, no candidate sites have been identified), the estimated annual cost to dispose of the low-level wastes would be about $3.0 million (1982 dollars). Since LLRW storage defers but does not eliminate this cost, direct disposal would be the preferred alternative, if it were available. The principal benefit of providing a LLRWHF at Susquehanna SES is to. insure against a possible forced shut down of the station. Without off-site disposal, in the absence of the LLRWHF, shut down would result after approxi-mately one month of continuous operation of Units 1 and 2 unless on-site space in existing facilities could be converted to waste storage. This benefit (i.e., avoided cost) can be quantified in dollar terms. The cost to replace the station power with power generated with higher cost fuel (ultimately borne by the Applicant's customers) would be about $50 million per month. The fixed cost to the Applicant of carrying a non-productive Susquehanna SES investment is estimated to approximate $50 million per month. Also, the non-productive wages of $1.5 - 2.0 million per month (1982 dollars) are an added cost in the event of a shut down. Another benefit to the regional society would be the uninterruption of local, state, and federal taxes estimated to exceed $95 million annually. 7 28 i i !c a y-.

r-The environmental impacts, detailed in Chapter v, are insignificant in keeping with the passive character of the LLRWHF. A 73 m x 88 m (240 ft x i. 288 ft) tract of land (already dedicated to activities associated with the I generation. of electricity) will be required for the storage building. No significant ecological impacts or costs have been identified. Radia- ] tion dose to the limited number of LLRW workers (estimated as 2 full-time l worker equivalents) will be will below the applicable limits (10CFR20). Radi- [ ation dose to the general population from LLRW activities will also be far I. below guidelines for normal operations (10CFR50). e ..-............e_.. . $. M e e e ae. W h D g 29 .-.e e e f. e h

r^ e ' 8.,0 COMPLIANCE WITH APPLICABLE LAWS AND REGULATIONS l. The proposed action, operation of a LLRWHF would be implemented to ensure compliance with all applicable Federal, State and local licenses, standards, and permits. The facility design and operati,on will conform to all applicable codes (see Appendix A for details of applicable codes). At present the only permit or license required for,the operation of the LLRWHF is an occupancy, permit from the Pennsylvania Department of Labor and Industry. 9 e 9 'a w e %e 4 .g 30 e m

r g. REFERENCES Dames & Moore. 1980. Susquehanna Steam Electric Station 1979 Meteorological ~ ' Summary. Prepareo for Fennsylvania Power and Lignt Company by Dames & Moore.. Washington, D.C. McArthur, W. C. 1979. "The Status of-Low-level Radioactive Waste Disposal-- How to Plan a Disaster," in Low-Level Radioactive Waste Management. Proceedings of Health Physics Society Twelfth Mid-Year Topical Symposium, February 11-15, 1979,-Williamsburg,.VA. Pennsylvania Power and Light Company. 1978. Susouehanna Steam Electric Station Units 1 and 2 Environmental Report Operating License Stage. Allentown, PA. t. Pennsylvania Power and Light. 1981. Susouehann'a Steam Electric Station Low-Level Radioactive Holding Facility General Design Specification, .j .G-1077-1. Allentown, PA. State Planning Council on Radioactive Waste Management. 1980. Nuclear Wafte Policy Act.. U.'S. Code of Federal Regulations. Title 10, Part 20. U.S. Code of Federal Regulations. Title 10, Par't 50. U.S. Code of Federal Regulations. Title 49, Part 173.397. U.S. Department of the Interior. 1979. " Endangered and Threatened Wildlife and Plants." Federal Register, Vol. 44, pp. 3636-3654. Washington, D.C. U.S. Nuclear Regulatory Commission. 1981. Final Environmental Statement Related to Operation of Susouehanna Steam Electric Station, Units 1 and 2 -Pennsylvania Power and Light Comoany Allegheny Electric Cooperative, Inc., NUREG-0564. Washington, D.C. U.S. Nuclear Regulatory Commission. 1979. Information Relevant to Ensuring that Occupational Excosures at Nuclear Power Stations Will be As Low As Is Reasonably Achievable, Regulatory Guide 8.8, Revision 4. Washington, D.C. ~ U.S. Nuclear Regulatory Commission. 1977. Operating Philosophy for Maintaining ~ Occupational Radiation Exoosures As Lcw As Is Reasonably Achievable, -j~ Regulatory Guioe 8.10,. Revision 1-R. Washington, D.C. 7 U.S. Nuclear Regulatory Commission. 1975. Standard Review Plan for the 2 l .~ Review of Safety Analysis Reports for Nuclear Power Plants--LWR Edition, d NUREG-75/087. Washington, D.C. U.S. Nuclear Regulatory Commission. 1981. Safety Evaluation Report by the-Office of Nuclear Report Regulation in the Matter of Pennsylvania Power ,l and Light Company and Allegheny Electric Cooperative. Inc. Susquehanna Steam Electric Station Units Number 1 and 2_, NUREG-0776. Washington, D.C._ ; i 31 9. e En e-

E~ ; l,- I: APPENDIX A SUSQUEHANNA STEAM ELECTRIC STATION LOW LEVEL RADWASTE HOLDING FACILITY TECHNICAL C0t! CEPT JULY 1981 / .l The following infonnation was transmitted from PP&L to Battelle to be 'I used as baseline data in the development of the Environmental Assessment Report. l i s 4 I r. e I N l A-1

t .~ SUSQUEHANNA STEAM ELE':TRIC STATION LOW LEVEL RADWASTE HOLDING FACILITY TECHNICAL CONCEPT I 1 -- Table of Contents -- g 1.0 Facility Function 2.0 General Description 3.0 General Design Require =ents .4 3.1 Codes and Standsrds 3.2 References l 3.3 Health and Safety Requirements 3.4 Material Being Stored l 3.5 Containers 3.6 Storage Requirement 3.7 ALARA Requirements 3.8 Design Life 3 i 3.9 Architecture .3.10 Security 4.0 Sys, tem Design Requirements { 4.1 Building and Storage Vaults ~ s t 4.2 Floor Drains System 4.3 Loading Systems 4.4 Lighting 4.5 Heating, Ventilation, and Air Conditioning Sys tems 4.6 AC Power System 4.7 Communication Sys tem 4.8 Radiation Monitoring System-4.9 Fire Detection / Protection System 4.10 Security Sys tem l 4.11 Annunciator Sys tem t 4.12 Grounding Sys tem 4.13 Raceway 4.14 Shielding 4.15 Trash Restraining System f. [ 4.16 Shipping Inspection Station i r. f 5.0 Facility Operations 5.1 General 5.2 Loading and Unicading l - l 5.3 ' Fire 6.0 civil Design Criteria j 6.1 Classification of Structure 6.2 Design Loads 'gl A-2 9 e m.a

i r. ~ Table of Contents Page 2-6.2.1 Dead Load 6.2.2 Live Load 6.2.3 Crane Loads 6.2.4 Ground Water Pressure l 6.2.5 Floods 6.2.6 Wind Loads 6.2.7 Seismic Loads 6.2.8 Pressure Loads 6.3 ' Materials and Design Methods 6.3.1 Materials 6.3.2 Design Methods 6.4 Site Information and Site Work j-i 6.4.1 Plant Datum and Orientation i 6.4.2 Design Depth for Frost Protection j 6.4.3 Earthwork Slopes 6.4.4 Rock Slopes D e. Ya s 'i g A-3 O

a-i j 1.0 Facility Function ' The function of the Low Level Radwaste (LLRW) Holding Facility is to ~ provide interim, on-site storage for low level radioactive waste produced at -the Susquehanna Steam Electric Station (SSES) until it can be shipped off-site'to permanent disposal facilities. This storage capability is required whenever shipment off-site is temporarily restricted by unavailability of disposal quota, unavailability of ' l shipping casks, transportation problems or other such problems that 1 have hampered LLRW disposal in recent years. The original plant design provided very limited storage capacity based on the assumption that the waste would be continuously shipped off-site for disposal. Therefore, any interruption in shipment would have the potential to shut down the plant. This facility allows temporary . shipping interruptions to occur without impacting plant operations. This facility also aids in reducing the total man-rem exposure associated with the disposal process by providing the means to allow significant decay before the shipping and burial activities occur. 2.0 General Descriotion l_ i The LLRW Holding Facility.shall be designed to hold all of the dry l solid (trash) and dewatered solidified (cement) low lesel radioactive - wastes that are generated by both units. It shall be designed to house all such vastes inside an uninsulated, sheet metal building with the ' l cement stored in a shielded vault inside this building and the trash stored outside the shielded vault. The primary purpose of the metal building will be to provide weather i protection for all stored wastes and to provide all-weather loading and off loading capability. i The primary purpose of the shielded vault will be to provide radiation shielding around the cemented wastes such that on-site worker doses are as low as reasonably cchievable and the total site boundary dose race is less than the plant operating license allowable. This facility shall be a Non-Seismic Category I facility per the definiE1ons in Section 3.7a of the FSAR. The Safety Classification shall be "other" as defined in Section 3.2.3.4 of the FSAR. Its Quality Group Classification shall be N/A. 3.0 General Design Recuirements 3.1' Codes and Standards. The design of the Low Level Radwaste Holding Facility (LLKW) shall conform to codes, standards, and specifications listed below, except where specifically stated otherwise. In the caselof conflict between the various codes and standards, the more i stringent require =ents shall apply and such conflicts shall be i called to the attention of PP&L. 3 3 .{ When a determination is required as to which code or standard is more stringent, direction and clarification shall be requested from PP&L. A-4 4

'gT 10CFR20, Sr.andards for Protection Against Radiation. a. b. 10CFR30, Rules of General Applicability to Domestic Licensing of By Product Material. I Occupational Safety and Health Standards, Department of c. Labor, Volume 36, No. 105 of Federal Register. .I d. Draft NRC Licensing Position, " Safety Considerations for Temporary On-Site Storage of Low Level Radioactive Waste". Reg. Guide 8.8, Information Relevant to Insuring that Occupational e. Radiation Exposure at Nuclear Power Plant Stations will be as Low as is Reasonably Achievable. g f. Reg. Guide 8.10, Operating Philosophy for Maintaining Occupational i Radiation Exposure as Lcw as is Reasonably Achievable. g. Uniform Building Code (UBC) 1976 and later revisions where applicable.* h. American Institute of' Steel Construction (AISC). " Specification for the Design, Fabrication and Erection of Structural Steel for Buildings" 1969 and later revisions where applicable *. 1. 'American Institute of Steel Construction (AISC). " Manual of Steel Construction"---19 70. j. American Iron and Steel Institute (AISI). " Specification for I the Design of Cold-Formed Steel Structural Me=bers" ---1968. k. ~ American Concrete Institute (ACI). " Building Code Requirements for Reinforced Concrete" (ACI 318-77 and later revisions l where applicable *) and Recommended Practice'for Concrete Formwork---(ACI 347-68). ] 1. American Welding Society (AWS). " Structural Welding Code"--- AWS Dl.1-72 and later revisions where applicable." i Regulations of the Commonwealth of Pennsv1vania as follows: I m. w i 1) Standard specifications of the Depart =ent of Transportation d (PennDOT) for 1970 and later editions where applicable *, with respect to roads and bridges. 'l Latest edition and supplements, if any, current at the ti=e of design shall be listed. 1 .s a A-5 ag S

Li -2) Regulations of the Department of Environmental Resources r: with respect to water supply, sewage, and erosion control. 3) Department of Labor and Industry regulations. Current i ~ t issue for: Construction and Repairs. Plant Railways. Excavation for Construction. Railings, Toeboards, Opensided Floors, Platforms, and Runways. l Ladders. Protection from Fire and Panic. l-Miscellaneous Hazards and Conditions of E=ployment. l Cranes, Booms, and Hoists. 's I 4) Pennsylvania State Police Department, Bureau of Fire Protection, regulations for storage, handling, and use of flac=able and' j, combustible materials. l i-n. Saf e ty and Health Regulations for Construction. Depart =ent of l Labor, Volu=e 36, No. 75 of Federal Register. American Concrete Institute (ACI), Concrete Masonrv Structures o. 8 Design and Construction, ACI 531-70*. American Society for Testing Materials (ASTM), Structural Steel, p. ASTM A 36-74*. American Society for Testing Materials (ASIM), High Strength t l. q. Bolts for Structural Steel Joints Including Suitable Nuts And Plain Hardened Washers, AS'Di A 325-74*. l Metal Building Manufacturers Association (MEMA), Recoc= ended -j r. Design Practices Manual, dated 1974*. t> 1 i .s. 49 CFR 170, Transportation. t. NUREG 75/087--Section 11.4. PP&L Procedure SP-12---Quality Requirements for Fire Protection Ii u. 'b and Bechtel Sys tems. ! t ! i Branch Technical Position 9.5.1 Appendix A -Guidelines for Fire

i-v.

ll Protection for Nuclear Power Plants.

1 w.-

NFPA Standards--Latest Revision. !I Latest edition and supplements, if any, current at the time of design shall be listed. ( -l f A-6 l ,,,--r-

Q 1 h I ~ aa. ANSI C33.98 Electrical Metallic Tubing Safety Standard, i ab. ANSI C80.1 Rigid Steel Conduit, Zine Coated. ac. ANSI CSO.4 Fittings for Rigid Metal Conduit and Electrical Metallic Tubing. ad. ASTM A525-73 Steel, Zine Coated (Galvanized) by. the Hot Dip I-Process. ae. NEMA TC-2 Electrical Plastic Tubing (EPT) and Conduit EPC-40 and EPC-80, af. NEMA TC-6 Plastic Utilities Duct for Underground Installation. I ag. UL-1 Flexible Metal Conduit. ah. UL-6 Rigid, Metal Electrical Conduit. f a1. UL-514 Electrical Outlet Boxes and Fittings. I a (. UL-797 Electrical Metallic Tubing. r a t. 40CFR-190, Environmental Radiation Protection Standards for i Nuclear Power Operations. -f-al. PP&L DWG.E-183152-1. Susquehanna SES LLRW Holding Facility Conceptual Layout. am. PP&L DWG. D-184172, Rev. 0; LLRW Holding Facility, Test Bore j j Holes, Location and Description. an. Factory Mutual Standards. l' J 3.2 References. The following references shall be considered in the' design of the LLRW Holding Facility. None of these are specific requirements for the facility. However, much that is. contained in j these references is pertinent to the design and may be applied if engineering judgment indicates that is is prudent and practicable. Some references are listed simply to provide background infor=ation -for the engineer. [ Reg. Guide 1.69, Concrete Radiation Shields for Nucicar Power [ a. j' Plants. l .i b. Reg. Guide 7.1, Administration Guide for Packaging and Transporting I l-Radioactive Material. [ i - i 10CFR71-Packaging of Radioactive Material for Transport. c. [ d. ANSI /ANS 55.1-1979, Solid Radioactive Waste Processing Systems F for Light Water. Reactor Plants.. s c g Latest edition and supplements, if any, current at the eine of h51Rn shall be listed. A-7

= 10CFR50 Appendix R---Fire Protection Program for Nuclear e. Power Facilities Operating Prior to January 1, 1979. '3.3 Health and Safety Recuirements. The facility shall be designed such that on-site radiation exposure is maintained as low as ~ reasonably achie'vable and the calculated off-site boundary dose contribution from this facility will not exceed 5 mrem per Exposure of on-site workers shall be minimized through the year. l; use of concrete shielding around the scored material, shielded loading equipment, and/or controlled access to the facility. Off-1 site dose rates shall be minimized through the use of concrete or other suitable shielding, distance, and, to the maxi =um extent practicable, the self shielding properties of the stored material. i. Provisions shall be made in the facility design to minimize the detrimental effects of machinery exhaust fumes and excessive temperature. Such provisions shall include a building ventilation system which tends to draw the exhaust fumes away from persons working on the operating floor of the facility and prevents temperatures from becoming excessive in the working areas. I t 3.4 Material Being Stored. The LLRW Holding Facility shall be designed to store low level dewatered solidifed radioactive wastes, and the low level dry trash radioactive vastes. Should the need arise, it may also be used for the temporary storege of large pieces of contaminated-or activated plan't equipment. It will not be used c j for storage of gaseous wastes or wastes containing free liquids as 1 described below. g Solidified waste. is defined as wet dewatered waste (e.g., evaporator i , I bottoms, resins, and sludge) which is solidified and contains less 'than 0.5% free water (by container volu=e) or 1.0 gallon of liquid F (in the container), whichever is less. Low level dry trash is i defined as contaminated material which contains sources of radioactive material that is dispersed in small concentrations throughout [ large volumes of inert material which contain no free water. Generally, this consists of dry material such as paper, trash, air L filters, rags, clothing, small equipment, and other dry material. l This material should_not cause fires from spontaneous chemical reactions, retained heat, etc. I-3.5 containers. The radwaste containers which will be stored in LLRW Holding Facility are designed to preclude or reduce the occurrence of uncontrolled release of radioactive materials due to handling, L transportation, or storage. i i Container material will conform to the requirements established in l' NUREG-75/087 (Section 11). Where corrosive material is being i stored, the container shall be designed to contain such material ( without loss of container integrity until final disposal. The vaste container materials shall not support combustion. 4 I r_ A-8 k.

i ~ In thot,e special cases where large contaminated or activated plant equipment is to be stored in this facility, the requirements for the proper storage container or lack thereof shall be ascertained at the time the need arises. Also, provisions for transportation, } storage, retrieval, shielding,'etc., shall be made as required for these.special cases. All material which is stored in this f.acility will be packaged for eventual shipment and permanent disposal. All containers will be decontaminated for shipping to the standards of 49CFR 173.397 before being brought into this facility. All unpackaged plant equipment will be decontaminated to the extent t' hat there is minimal surface contamination. i .t At the present time, and for the foreseeable future, there is a wide profusion in sizes and shapes of disposal containers in use in the nuclear industry. Each has its own advantages and applications. i It is expected that during the life of the facility it will be required to accommodate several of these different types. The most likely containe'rs which will be stored in the facility are + ' listed below: ( Manufacturer Designation Volume Dimensions United Nuclear 50 C5I. 50 ft.3 48"$ x 53-7/8" High Hittman HN-100 163 ft.3 72-3/8"$ x 72-3/4" High 3 i Hittman HN-600 83 ft.3 72-3/8"$ x 40" High Hittman HN-200 75 ft. 52-3/8"$ x 61-3/8" High Chem. Nuclear 14-195 200 ft.3 76"$ x 79" High 3 Chem. Nuclear 6-80 85 ft.3 58"$ x 57-7/8" High 55 gal. drum 7.35 ft.3 1.95 ft.$ x 2.9' High 4 Container Products B-25 96 ft. 50" High x 46" Deep Corp. x 72" Wide The above listed containers essentially envelop the volumes and dimensions that will be stored in the facility. The facility shall be designed to accommodate all of these containers except the Container Products B-25 in the shielded vault area, and the B-25 and the 55 gallon drum in the storage area. P ~ ' 3. 6 Storage Recuirements. The LLRW Holding Facil1ty sha'll be designed. to store the quantity of solidified and dry low level radioactive wastes generated by the SSES for the equivalent of 8 reactor years based on normal operation with the radwaste equipment provided with the original design. This storage shall be segregated, with l cemented wastes stored in the shielded vault area and compacted - l trash stored in the open storagt area. Wastes stored in the open storage area shall be further segregated with containers having contact readings.<_1 mrem /hr scored on the east face and top layer of containers,' 110 mr/hr stored on the north, south and west faces ^} and containers reading >10 mrem /hr stored within this perimeter to '/ the maximum extent practicable. Similarly, wastes stored within A-9 y ~ b d w w. c ~g y w.->e--4& r-----ne w .,wn,i y.m-7 --e t+--g .-w-yr 7

f the shielded ~ vaults will be arranged with containers with a contact dose race 13 rem /hr stored next to the vault walls and en the top layer and containers'>3 rem /hr inside this perimeter to the max 1=um extent practicable. These measures will take maximum advantage.of the self shielding properties of the waste material. b 3.7 ALARA Requirements. _ This facility shall be designed such that i off-site boundary doses are held within the requirements of 40CFR190 and on-site. worker dose races meet.the requirements of 10CFR'20. In addition, the design should be aimed at maintaining these dose rates as. low as reasonably achievable per Reg. Guides 8.8 and r

8. 10. This can be accomplished through the use of controlled 3

access to_the facility and surrounding area, utilization of the waste material for shielding to the ma:cimum extent practicable, providing shielding for loading equipment and use of remote operating stations. 3.8 Design Life. This facility shall be designed to temporarily store the wastes. generated by SSES for the equivalent of 8 reactor The design life of the acility shall be 40 years. At_the f years. end of.the design life the facility will be either 1) overhauled and maintained in service, 2) deco =missioned and converted to other use, or 3) decommissioned and removed frem use. 3.9 Architecture. The LLRW Holding Facility shall consist of a storage vault within the confines of'an uninsulated steel-framed, metal l sided structure. The purposes of the steel building a're to provide l. weather protection; all-weather loading capability; unified building. . an exterior architectural treatment which will economically meet - { services such as security, radiation monitoring, and lighting; and i the service' life of the structure and also be aesthetically compatible with other similar site structures. .The storage vault shall consist of a rectangular. cross-section as indicated on the-conceptual drawing. The walls of the vault shall be of. reinforced concrete or of concrete block construction. The vault shall be covered with removable, reinforced concrete shield ~ panels to permit the loading and unloading of the vaste containers.

The sizing of these removable panels shall be compatible with the lifting capacity of the handling equipment. The thickness of the roof panels and walls shall be designed to limit the off-site boundary dose and the on-site worker dos'e to levels specified in y

Section 3.3.- The vault shall be designed to minimize streaming uand the off-site and worker dose rate when the roof panels are removed for loading and unloading. The floor of the facility shall be designed to support all of the following: . Load lfrom stacked waste containers a. b. Load from vault walls and. shielding panels Load from handling equipment if carried by floor ji c. d. Load from steel superstructure if carried by floor Load from truck carrying. waste' and shielding e. A-10

+ Before beginning the floor design, the designsr shall evcluate ths advantages of designing the floor for a maximum uniform load throughout. A curb shall be placed around the perimeter of the facility to contain any liquid such as rainwater or fire sprinkler water which may be introduced into the building. The curb shall be of such height as to contain the volume of fire protection water released if all the sprinklers are actuated in the maxi =um credible fire event for a period of one half hour. Ramps shall be provided to facilitate vehicular traffic over the curb. The floor, curbing, sumps, and shield walls of the facility shall be coated with a decontaminable material to a height equivalent to the height of the curbing. t The metal building shall provide a truck unloading area which will afford convenient inside unicading to either the vault area or the unshielded area. Access to the truck bay shall be provided by a rolling door. A loading dock shall also be provided which will allow essentially level access from the trash storage area to an enclosed van or trailer for ease of Icading such a vehicle with a drive-on forklift. Personnel access doors are needed for operational requirements and also to satisfy fire safety standards. The actual number and location of the access doors shall be determined by the designer in accordance with all of the governing reference regulations. , The personnel access doors shall be the hollow metal type. The doors shall be equipped with cardreaders, an electric strike, and a door switch. All facility doors shall be integrated into the plant security system to provide an alarm in the event an ~ unauthorized or abnormal opening into the facility should occur. Louvers shall be provided to permit air intake into the facility for the HVAC system. The size, number, and location of the louvers shall be determined by the design requirements of the HVAC system. The louvers shall be located and/or protected in such a manner as to not become blocked with snow, ice, mud, or any other substance r which may restrict the flow of air into the facility. 3.10 Securitv. The security of this facility will provide for personnel access control and shall be integrated with the existing plant security system. 4.0 System Design Requirements 4.1 Building and Stora2e vaults. The storage vault shall store the higher level wastes, such as the solidified evaporator bottoms and deminerali:er resins, while the open area shall provide storage space for the lower level wastes' such as trash. -g A-ll =

E The designer shall design the metal building to include the following: Primary and secondary structural framing members,' base plates, a. anchor bolts, connection bolts, and other items which are { i applicable b. Metal roof deck and exterior metal siding c. Closures d. Flashing e. Fas teners t f. Sealants g. Gutters and Downspouts h. Louvers

i. Coatings (structural steel)

j. Hatches and roof openings k.

Crane rails and supports The facility should be designed, to the maximum extent practicab'le, to facilitate independent and si=ultaneous construction of the exterior metal building structure and the internal storage structure. The building shall be designed such that additional shield vault storage can be constructed in the entire trash storage area at a later time. 4.2 Floor Drains System. The facility will be designe'd such that under normal conditions there will be no free liquids inside the building. All waste will be either dewatered, solidified waste or ecmpacted dry waste. Therefore, any free liquid that enters the facility will be from an other than normal source. Potential abnormal sources are fire protection water, minute amounts if a cement container were to l be breached in loading or unloading, rainwater or sucv melt from roof leakage, cooling system leakage from equipment inside the facility, snow brought in on vehicles or liquids used for decontamination of containers before shipment,should that ever become necessary. All such. liquids mus t be considered contaminated until verified otherwise. The floor drains system shall be designed to collect any liquids that are spilled on the floor of the facilit, The system shall route all f drains to one or more collection sumps located at the building periphery. Each sump shall be equipped with liquid detection devices which will provide annunciation in the main plant and facility control rooms whenever any liquid enters the sumps.. 4 i l A-12 ee ,w -m---., .-.-e. ~, - - -,

p... Provisions shall bs mada such that sempling of tha cu=ps may be performed from either inside or outside the building. Provisions shall also be made such that the sumps may be pu= ped to portable tanks from either inside or outside the building. There shall be no permanent pumping equipment installed or piping connections to the main plant. The sump (s) shall be provided with a metal container which will catch the initial quantities of water entering from the drains system. The container shall allow for r&moval from the su=p by hand to provide a means for conven'.ent disposal of small quantities of water which enter the su=p. The areas inside the vault shall also be provided with drains to route free liquids to the sumps. 4.3 Loading System. The loading system for this facility shall be capable of unloading, transporting within the facility, placement, retrieval, and reloading of cemented waste. It shall also have the capacity to lift, transport, and replace all movable and temporary shielding devices. Features shall be incorporated to =inimize operator radiation exposure in accordance with ALARA principles. The system shall be designed with features which facilitate its transfer from one area of the building to another as th.e areas are filled. This capability shall also include the trash storage area in the event the vault storage is expanded into this area at a later time. The loading system shall also be capable of retrieving dropped and damaged waste containers for repackaging or other disposition. In selecting the loading systems, consideration should also be given to delivery schedule, cost, maintainability with regard to ALARA, parts availability, operational practicality, and the impact of the systems on the design of the balance of the facility. Loading for the compacted trash shall be by a battery or L.P. gas powered forklift. Shielding for the forklif t operator shall be provided on the vehicle as required to meet ALARA requirements. A battery recharging station for the forklift shall be' provided in n the facility at a location outside the storage areas. 4.4 Lighting. The facility shall be provided with lighting which will normally be in service only during loading or unloading operations. The lighting shall be adequate for safe, efficient handling of the waste containers in the offloading area, the dry trash storage area, and for safe, efficient handling of the shielded vault cover blocks. There will be no permanent lighting installed inside the shielded vaults. Lighting for this area will be provided on the container handling equipment with intensity as required by the 1 CCTV manufacturer. A-13 e w

~ The lighting shall be designed to provide long lighting element life and to afford ease of changing the elements in order.to minimize maintenance ti=e and potential radiatien exposure. The lighting shall be controlled from the facility control room. Yard lighting will also be provided as required for security purposes to maintain a minimum of 2.5' foot-candles via banks supplied from the securief control center source. The wiring shall be 600V, type TE' color coded No.12 AWG minimum solid copper wire; No. 8 AWG conductor and larger shall be stranded All cables shall be ins talled in conduits not smaller than copper. one inch diameter. 4.5 'neating, Ventilation & Air Conditioning Svs tems. The facility shall be provided with an active ventilation sys tem for two basic functions:

1) removing noxious or irritating exhaus: fumes whenever internal combus tion engine pcwered machinery is operating inside the facil10/,

and 2) preventing excessive heat build-up from the roof in the summer. The sys tem shall be designed such that it moves air generally in an upward direction.away from the equipment operators. Air inlets shall be provided such that when the facility is closed, air entering the facilief is evenly dis tributed and flows as described ab ove. They shall be located and/or protected such that snow accumulation cannot significantly res trict the flow of air or be drawn into the l i f acili ty, The ventilation sys tem shall not provide any heating or cooling for the facility. It will also not provide any humidity control. The sys tem shall be provided with thermos tatic controls to auccmatically maintain the facilief temperature below the maxi =um allowed for safe working occupancy. It shall also be provided with an automatic shutdown feature which is activated when smoke is detected by the fire detection sys tem. The controls shall provide for manual s tarting and s topping of the sys tem which shall override the automatic functions described abcve. The sys tem controls shall be located in the facilief control rocm. r. The sys tem shall exhaus c through a damper which shall open when the ~ . fans are in operation and close when the f ans are shut down. The facilief control rocm shall be provided with heating and air conditioning which shall normally be required when the facilief is being loaded or unloaded. 4.6 AC Power Svs tems. The three phase, 480 volt pcwer supply to the building will be provided by owner supplied 500 kVA pad-nounted . transformer and associated fuse cabinet located approximately 20 f eet.from the control / equipment 'rocm. The pcwer will be dis tributed A-14 9 6 O

w at appropriate voltage levels from the facility motor control canter equipped with relay ground fault protection. This will be the only source of electrical. power for all facility loads except for the following: Security equipment will be supplied normally from the Security Control Center scurce which has diesel backup. Fire protection. equipment will-have. battery backup to normal building AC supply specified as part 6f the panel. In addition to permanent loads, power is required for convenience 120 VAC outlets and power / welding 480 VAC receptacles. All electrical equipment including cable contained within the storage ' area shall be capable of performing its normal function under all environmental conditions which shall exis t inside and outside the f acili ty.. Cable shall be of non-PVC insulation /jacke ting and shall comply with IEEE Standard 383-1974 for cons truction and flacmability. 4.7 Communicatiens Svs tem. The communications system vill allcw two way conversation and paging ber;een the =ain plant and the facility. It shall be designed to be compatible with and connected to the exis ting main plant communications sys tem. It will have at leas t one s tation for paging and conversation'in the offloading area. It will have-sufficient speakers inside the storage area to insure that paging or alarm can be heard when the facility is at full capacity. It will also have one s tation for paging and conversation in the facility control room. One telephone with a plant extension,shall also be provided in the LLRW control rocm. All communications, cable shall be in rigid s teel conduit. 4.8,' Radiation. Monitoring Sys tem. The radiation monitoring system shall be designed to monitor the general area radiation levels at various locations in the trash storage area, above the shielded vault area, the offloading area, and the facility control room. Readout shall be in the facility control room. 4.9 Fire Detection / Protection System.. The fire-pgotection design shall be based on a combustible loading of 1200 lbs/f t The facility shall be c. provided with a fire detection system to provide an early warning system. Location and placement of detectors shall consider access to each detector for annual testing. r The entire building shall be provided with a dry pipe sprinkler system designed to deliver.25 gpm per square foot over the hydraulically mos t remote 3000 square foot area. The sys ten shall utilize sprinkler heads rated at 23607. Water will be supplied frem the exis ting fire protection sys tem by a 10" mortar lined ductile iron fire protection line. The water - supply is capable of supplying a minimum of 1500 gpm at 100 psi. Fire hydrants shall be provided and equally spaced at 300 foot

intervals around the building perimeter. Hydrants and hese houses I

shall be identical to exis ting plant equipment. -1 4 A-15 h

- ~ - - All fire protection equipment shall ba Undsrwritars Laboratories listed and approved by Factory Manual. All fire protection and fire detection drawings are subject to PP&L and insurance approvals. This facility shall be designed with security Svstem. 4.10 Security provisions that are an extension of the existing plant security All accesses to the facility shall be =onitored by system. Normal accesses shall be equipped with entry the system. All others control devices such as magnetic card readers. such as the fire exit doors shall initiate an alarm in the plant security system if they are opened. The following occurrences in the facility 4.11 Annunciator Svstem. will activate an annunciator in the main plant control rocm and at the facility: L Detection of fire a. Detection of liquid presence in any of the facility susps. b. Loss of electrical power to the facility. c. The main control roca vill have one common annunciator window which will be activated for any of. the above listed alarms. An annunciator panel will be provided at the facility control room which will have separate windows for each alars. The grounding syste= shall establish a 4.12 Grounding Svstems. building ground grid to connect electrical and mechanical equipment and structures, raceways, duct banks, and ochbr required grounds to the existing exterior station grounding system. The grounding conductors shall be: larger than #8 AWG- ~ Class B, bare, stranded, soft drawn copper wire; #8 AWG and smaller-bare, solid, sof t drawn copper wire. The building ground grid shall include a mini =um of a 250 kemil cable loop connected to every other steel colu=n as a minimum with additional connections as required to establish a r-uniform potential in and about the structure, Any steel columns not tied to the building frame by welding, riveting, or bolting must be tied to the 250 kemil cable loop or jumpered to the building frame which does tie to the 250 kemil loop. The building ground grid shall be connected to the existing exterior station ground system by a mini =um of two connections located on diagonally opposite sides of the building and attached to different sections of the exterior station grounding system. ~ All underground or e= bedded grounding connections shall be made by the exothermic process. A-16

,e In'stch aram containing elsetrical" (quipm nt, thara shall ba access to the grounding system from either structural steel or the ground grid. All stairways, handrails, and grating shall be connected to the grounding system through the structural building steel back to the column grounds. Each motor control center shall be connected to the building ground grid by two 250 kemil equipment grounds. All electrical apparatus supplied from low resistance or solidly grounded alternating current systems operating at greater than 240 volts shall be provided with: One fault current return path grounding conductor unless ~ a. rigid steel conduit is used for the raceway. b. One equipment grounding conductor connected to the nearest point on the building ground grid. The grounding conductor for both the fault current return path and equipment grounding shall be at least the same size as the largest source conductor in the raceway. Duct banks under buildings containing circuits of 240 volts or more shall have one No. 4/0 AWG fault return conductor, embedded as close to,the top of the duct bank as possible. Such conductor shall be connected to the electrical equipment at either end of the duct bank. If such duct banks extend beyond the building, a second No. 4/0 AWG conductor shall be bonded to the first, at a point approximately 3 feet from the wall of the building. Approximately 3 feet of each conductor shall be lef t, coiled and taped at the end of the duct bank if such duct bank will be completed by others. 4.13 Racewav. All raceway-within the storage area shall be rigid steel conduit not less than 1-inch diameter and shall be UL approved. Percentage fill in conduit shall not exceed 40 percent. Raceway shall be marked with black letters on white background. All rigid steel conduit bends shall be cold bends. Conduit runs shall not ~ have more than the equivalent of four 90-degree bends between . pulling points. 3 Embedded conduit shall not be less than 1-inch diameter. A minimum clear space of 1-1/2 times the size of the coarse aggregate or 2 inches, whichever is greater, shall be maintained between embedded conduit and the concrete surface except at the point of stubout and embedded conduit and reinforcing steel. -i i A-17 og l

m 6 When two or more layers of conduit exist, the clear spacing between two adjacent conduits in the vertical plane of mats or slabs and in the plane perpendicular to the plane of the wall shall be at least 1-1/2 times the size of the coarse aggregate, or 2 inches, whichever_is greater. A 1/8 inch nylon pull rope with 8 inches turned back at each end shall be lef t in all conduit in which the cable is not pulled. Conduit for telephone, PA3X, public address, fire detection, and fire signalling systa=s shall be rigid steel, cach conduit shall not exceed 75 feet between pull or junction boxes for 3/4 inch size and 150 feet for 1 inch or larger sizes, and shall not contain more than the equivalent of three 90 degree bends. The A/E shall provide a detailed schedule for controlling the I installation of the raceway system. The schedule should include: a. Raceway Index. l

1) The latest revision nu=ber indicating when'the raceway j.

was added, last changed or deleted j' l' 2) "From" and "To" destination

3) Raceway code

4) Raceway function (P-Pow ar, K-Control, M-Instr 6 ment, C-Communication)

5) Approximate length of raceway

6) Layout drawing nu=ber on which the raceway appears 7)

Included cables

8) Percent fill b.

Raceway Code Description 1) Size r. I

2) Type L

3) Area of the raceway in square inches

4) Estimated footage 4.14 shielding. The shielding for this facility shall consist of two major areas:

1) the fixed shielding for the in-place stored material, and 2) the transient shielding which shields the vaste while being moved from the vehicle in the off-loading area to the storage position.

A-18 G - - " * ~

?. [ iI The fixed' shielding shall consist of the following: The cemented was te s torage vault a. 1) the walls---reinforced concrete h) ' the cover-- reinforced concrete slabs I b. The trash storage area t-1) the north and south walls-- reinforced concrete c. The facility. control room 1) the south and wes t walls--- reinforced concrete The transient shielding shall consis t of the fo11 ewing: For the cemented was tes---a portable shielding device which is a. attached to the loading crane which shields the containers while being =oved from the transporter in the off-loading area to the place of s torage. b. For the trash was tes---shielded forklif t or other loading vehicles will be p ovided by the cune as required. 4.15 Trash Res training Sys tem. The f acility shall have a trash restraining system which shall be designed to prevent any trash containerd from l' being blewn out of the confines of the facility during a tornado having a 300 mile per hour wind velocity. The primary element of the sys tem shall be netting of nylon or other suitable material enclosing the trash s torage area and secured to i anchors in the foundation.and/or floor slab. However, all tornado loading shall be transmitted directly into the anchors. The system shall be designed such that failure of the building structure will not tend to cause failure of the trash restraining system. The sys tem shall be designed such that it will allow ease of movemeEt and placement of the trash to the maximum extent practicable. r. 4.16 Shioning Insoection Station. The f acility shall be equipped with a shipping inspection station where inspections required by 49CFR170 can be performed on the solidified waste containers i= mediately prior to ship =ent. The inspections shall include the following: 1) Visual inspection of the container for deterioration, leakage, or other conditions which might preclude shipment, disposal, or require repackaging. i g A-19 (. c.-, w:r, a

• 2)

A contact radiation dose reading at the area of highes t radiation on the container surface. 3) A ra'diation dose reading at three feet from the outer surface at the area of highest radiation. 4) An outer surface contamination smear. The s tation shall provide shielding for the person performing the inspections and remote operating capability for these functions to The s tation minimize the radiation exposure per ALARA principles. shall be compatible with the loading system of the facility and ~ shall be transf errable between overhead crane service areas. The s tation shall be equipped with the appropriate lighting to allow these inspections. Provisions.shall be made in the facility for electrical pcuer for the station at the locations it will occupy. 5.0 Facility Ooeration 5.1 ' General. The purpose of the operation of this facility will be to temporarily s tore low level radioactive waste generated by the plant until it can be shipped off-site. It is normally an unoccupied facility with occupancy normally occurring only whenever loading and unloading operations are in progress. I Waste will be loaded into the f acility in a controlled manner with the lower activity was tes being s tored around the periphery and, where practicable, on the top layer of each of the s torage areas. This will* maximize utilitation of the self shielding properties of 3 the material and minimize personnel exposure.

5. 2 Loading and Unicading. Loading of the facility will generally proceed as follows for solidified was te.

A truck loaded with a container of the waste will enter the faciliey in the offloading The was te containers will-be inside a shielding device if area. radiation levels so dictate. The truck will s top with the container located in the overhead crane pickup area. Before any other unloading s teps are taken, all personnel mus t either move a safe dis tance from the container or get behind the protection of appropriate shielding. s The container is lifted off the truck and moved to the approximate r storage location.- Then the auxiliary hook removes the appropriate shield panel. The container is then moved into proper position and lowered into the storage vault. The removed cover is then replaced, whereupon the operation is complete. Loading the facility with trash waste will take place in si=ilar fashion. The truck with the 55 gallon drums on pallets will enter the f acility or the loading dock area. The truck will s top with the It is then offloaded material adjacent to the trash s torage area. with a forklif t or other appropriate machine. If required, depending on the dose rate from the containers, the forklif t will be equipped 't ~ with shielding' for the driver. A-20 -w

Unloading the facility will generally occur in the reverse order of the loading steps. However, during the unloading process inspection for shipping may be required. 5.3 Fire., In the event of fire in the facility the fire detection sys tem will annunciate an alarm in the main plant control room and automatically shut dovn the ventilation sys tem. Should the fire continue to propagate, the fire protection sys tem will be automatically actuated in the area of the fire. Any water or other fire fighting materials introduced into the facility should be considered contaminated until proven otherwise. If ' contaminated, they should be disposed of accordingly. 6.0 Civil Design Criteria 6.1 Classification of Strueture. The Low Level Radwaste Holding Facility shall be designated as a Non-Category I s tructure. A Non-Category I structure is one whose failure would not result in the release of significant amounts of radioactivity and is not required for reactor shutdown. 6.2 Design Loads. The following design loads shall apply to the LLRW Holding Facility. Situations not specifically covered by the following shall be evaluated on an individual basis, recorded, and approved by PP&L before i=plementation.

6. 2.1 Dead Load (DL)--includes weight of framing, roof, floors, I

walls, platforms, and all per=anent equipment. I Permanent equipment such as: i l a. HVAC equipment b. Electrical panels and equipment Control panel for overhgad crane c. d. Fire protection equipment r~ A load allowance for piping, electrical trays, and ducts ? of 10 psf shall be taken as dead load in ec=puting structural s member s tresses. This lead allowance may include such items as: a. HVAC ducts b. Lighting c. Sprinkler sys tem d. Fire detection sys tem -g A-21 8. 4

~. 6.2.2 Live Load (LL)---includes all vertical loads excep t DL. ~ Following are minimum live loads to be used in design of the various areas: a.' Roof: The roof live load, including snow loads, shall be 30 psf on the projected horizontal area, or a concentrated load of 200 pounds acting on a 1 foot by 1 foot area at the center of the longes t span, whichever is the more severe. b. Ground Floor. c. Was te Impact: The floor shall be designed to withs tand the impact of a filled liner and shield bell dropped from the maximum lif t of the loading crane without any degredation of the overall structural integrity of the facility. d. Truck Bay: AASHO H20-S16 Special Load Transporter. I e. Forklift Access Areas: ' l) Equipment Room: 250 psf.

2) Control Room:

250 psf. f. Surcharge outside and adjacent to structures: 250 psf; Railroad surcharge per A.R.E.A. specification. Concentrated load on beams and girders'(in addition g. to all other loads): 5 kips to be applied at points of maximum mement and shear. This lead is not cumulative and is not carried to columns. It is not applied in office or access control areas and at equipment access and walkway platforms. h. Concentrated load on slabs (to be considered with dead load only): 5 kips acting over an area of 3 sq. ft. to be applied at points of maximum moment and . shear. This load is not cu=ulative and is not carried to columns. It is not applied in office or access control areas. r-6.2.3 Crane Loads. The designer shall include within the scope of his work the design of the crane rails and supports. Crane and equipment vendor drawings shall be followed for wheel loads,. equipment loads, weigh ts of moving parts, and crane rail deflection requirements. Impact allowance for traveling crane supports and their connections shall be 25%. Lateral force on crane runways shall be 20% of the sum of the weight of the lif ted load and the crane trolley applied at the top of rail, one-half on each side of the runway, and shall be considered as acting in either direction nor=al to the runway rail. The ,i longitudinal force shall be taken as 10% of the maxi =um wheel loads of the crane applied at the top of rail. A-22 4

4 6.2.4 Ground Water Pressure. The ground water level shall be determined by the designer based on site specific information. 6.2.5 Floods. ' The LLRW holding facility need not be designed for the effects of a flood since the proposed site location is well above the flood s tage for the probable maximum flood (PMF). The facility shall be designed for a maximum rainfall intensity of 6 in/hr. 6.2.6 Wind Loads. The structure shall be designed for the basic wind loads tabulated below in accordance with ASCE paper No. 3269. Values are in pounds per square foot unless noted otherwise. L Wind Load on Structures: a. Height 0-50 ft. b. Basic Velocity 80 mph c. Dynamic Pressure with 1.1 Gust Factor q 20 psf

d., all Pressure 0.8q 16 psf W

e. Wall Suction 0.5q 10 psf f. Total Design Pressure 1.3q 26 psf g. Roof Suction 0.6q 12 psf' 6.2.7 Seismic Loads. The LLRW Holding Facility shall be designed in accordance with the Uniform Building Code (U3C) for - g g

• s tructures in Seismic Zone I as defined therein.

j 4

6. 2.8 Pressure Loads. The facility shall be designed to withs tand the pressures generated by the EVAC sys tem.

l i 6.3 Materials and Design Me thods. l 1 6.3.1 Materials. .I a. Concrete design s trengths for the LLRW s tructure l shall be based upon the following table: r-4000 psi ?

1) Precas t concrete panels

2) All other materials 4000 psi

3) Concrete infill for unit masonry 2500 psi walls

4) Mass concrete fill and =ud mat 2000 psi b.

Reinforcing s teel shall conform to ASTM-A615, Grade 60. c. Structural Steel shall conform to ASTM-A36, or other ASTM designations listed in Section 1.4.1.1 of AISC ^- Specification for the design, fabrication, and erection j. cf s tructural s teel for buildings. A-23 -D e e 3 . =

p 31 Q b s d. Masonrv Cons truction ?,. Concrete =asonry units shall conform to either ASIM 1) C90, Type I, grade N for hollow masonry unit or ASTM l C145, Type I, grade S for solid masonry units. Masonry mortar shall conform to AST t C-270, type M 2) having a minimum ccepressive strength of 2500 psi at 28 days. I 3) Masonry grout shall conform to ASri #-4765, minimum ccepressive s trength of 2500 psi, at 28 days. 6.3.2 Design Methods. k All s teel structures shall be designed by a. General. the verking s tress methed. All reinforced concrete s tructures shall be designed by the s trength methed. Any deviation from above is permitted only when approved by PPSL. All masonry blockwalls shall be designed by working s tress design method and in accordance with requirements of Chap ter 24 of U3C. The allevable s tresses shall be as specified in USC, table 24-H for special inspection, or as modified in this section. For multi-wy the block walls, shear s tresses shall be calculated at the interf ace of masenry block and infill caterial. Where the calculaced shear s tresses exceed the allcwable limits specified in "masonrf s tructures" subsection of this section, metal ties (DUR-0-WALL, bent plate, or No. 3 rebar) belveen the two wythes shall be designed to transfer the full f shear value. I In determining the mos t critical loading condition to be used for design, the absence of a lead or loads { shall also be considered, when appropriate. I i Formwork design shall be in accordance with ACE 347 and " Safety and Health Regulations for Cons truction,'" l 75. If any Department of Laber, Volume 36, No. Foundatien-conflict occurs, the latter shall govern. design shall maintain minimum saf ety f actors in accordance with the following criteria: 4 A-24 G - - - - - ~ ~ ~ _ __.

s a. Load Combination: D+H+W D+F b. Overturning 1.5 c. Sliding 1.5 d. Flotation 1.1 b. No tations. I U: Required s trength to resis t design loads, as defined in ACI 318. D: Dead load of s tructure plus,any other per=anent loads contributing s tress, such as hydros tatic loads. L: Live loads expected to be present when the plant is operating, including movable equipment, piping, cables, and lateral earth pressures. V: Seismic load on Non-Category I s tructures as specified in the Uniform Building Code for Seismic Zone 1. W: Wind load, f's: Allowable working.s tress in tension for reinforcing bars (as specified in ACI -318-77). Fy: Yield s trength of reinforef ag s teel. Sm: Allowable s tress for reinforced masonry per UBC, Table 24-H (special inspection) for global wall analysis; or allowable s tress for unreinforced masonry per table 24-B for local wall analysis as a result of attachments. H: Lateral earth pressure. Fs: Allowable s tress,for s tructural s teel (as specified in AISC,1970 edition). r. f: Calculated s tress for s tructural steel. Fy: Yield s trength for steel (as specified in AISC, 1970 edition). F: Buoyaat force duc to ground water pressure. c. Design. Designated as a Non-Category I structure, the Low Level Radwas te Holding Facility shall be i designed using the following load combinations: A-25 )

1) Concrete Structures

a. U = 1.4 D + 1.7 L

b. U =.75 (1.4 D + 1.7 L + 1.7(1.1)V)

c. U =.75 (1.4 D + 1.7 L + 1.7 W)

d. U =.9D + 1.3(1.1)v (Note 1)

e. U =.9D + 1.3 W (Note 1) 2)

Steel Structures

a. D + L

.....s tress li=i t of Fs

b. D + L.+ V

.....s tress limit of 1.33 Fs

c. D + L + W.....s tress limit of 1.33 Fs No te 1: Where overturning forces cause net tension in the absence of live load.

3) Concrete Masonry Structures Normal Conditions:

a. D + L

.....s tress limi ts of f 's, Sm*

b. D + L + V

..... stress 14 its of 1.33 f's,1.33 Sm*

• If the designer chooses to use double wythe valls designed as a composite section, the l

allowable shear or tension s tresses between the masonry block and concrete or grout infill shall be equal to three percent of the co=pressive j s trength of the block. i 6.4 - Site Infor=ation and Site Work. 6.4.1-Pjant Datum and Orientatien. Plant datum corresponds to U. S. Geological Survey a. Mean Sea Level (MSL) datum. b. Plant north corresponds to true north. r-6.4.2 Design Deo th for Fros t Protection. a. Bottoms of all foundations shall be located at a minimum dep th of 4 f t. belcw grade. b. All water piping shall have a mini =um cover of 4-1/2 ft. 6.4.3 Earthwork Slooes. Maximum embankment slope: 1-1/2 hori:. : 1 vert. -g i 6. 4. '+ Rock Slooes. Reco= mended slopes: I hori:.: 4 vert. A-26 507926/saw

~ ATTACHMENT 4 Resume of training and experience for the Radiation Protection Officer, (Michael R. Buring) is included as pages 2, 3 and 4 of this attachment. The resume of training and experience for the Radiation Protection Officers alterna_tes are as follows: Mark W. Granus - included as pages 5 and 6 of this Attachment. F. Peter Jaegar - Included as pages 7 through 10 of this Attachment. 6 z, Page 1 of 10

ATTACHMENT 4 RADIATION PROTECTION OFFICER - TRAINING AND EXPERIENCE Name: Michael R. Buring Education and Training 1970 Ohio State University; B.S. - Zoology Work Experience 1962-1967 U.S. Navy - Enlisted Nuclear Plant Operator, Engineering Lab Technician, Prototype Instructor Duties: Mechanical Operator / Instructor at Naval Nuclear Power Plant Prototype, Health Physics and Water Chemistry Control, both Primary and Secondary. 1967-1970 Batelle Memorial Institute - Safety Technician Duties: Inspection and Auditing of various research projects in progress, for compliance with es.ablished procedures and regulatory requirements. 1970-1973 Virginia Electric and Power Company - Surrey Pcwer Station Health Physicist Duties: Assist station health Physicist in routine and special projects, personnel dosimetry, radwaste, radiochemistry, procedure writing, radiological environmental monitoring. 1973-1979 Metropolitan Edison Company - Corporate Radiation Safety. Duties: Technical Support of TMI station personnel in Health Physics, personnel dosimetry, radwaste, procedure writing and review, radiological environmental monitoring, etc. Supervised personnel dosimetry group during and after accident. l 1979-1981 Pennsylvania Power & Light-Company - Environmental Group Supervisor - Nuclear Duties: Supervise the implementation of radiological and non-radiological environmental monitoring programs. Page 2 of 10

1981-Present - Pennsylvania Power & Light Company - Radiation Protection Officer Duties: Management of Radiation Protection Program controlling all H.P. activities including whole body counting personnel dosimetry,-radwaste, ALARA control, respiratory protection and supervisor of H.P. personnel. Licenses and Certificates None. o Page 3 of 10

~ _ i i. I I l ATTACHMENT 4 Experience With Radiation - Michael R. Buring Isotope Amount Location Duration of Use Type of Use 1 4 [ Mixed Fission, Trace - U. S. Navy 12 years Power and Activation, & Corrosion Kilocurie Surrey Nuclear Sta. Naval Reactor i Products - Byproduc t. Three Mile Island Health Physics l Source and Special Nuclear Station Physics Program Nuclear Material i I t i i i i i f' Y t. f 4* o i nn g We

• Cs I

6 I

ATTACHMENT 4 HEALTH PHYSICS SPECIALIST Name: Mark W. Granus Education and Training 1978 Purdue University B.S. - Environmental Health & Health Physics Work Experience 10/80 - Present - Health Physics Specialist, PP&L Nuclear Support Group Duties: Assist the Staff Health Physicist in the.following activities: ALARA training, review of health physics procedures, radwaste. 6/78-10/80 Health Physicist, Dresden Nuclear Power Station, Commonwealth Edison Co. Duties: Health Physics related to Dresden Unit 3, station respiratory, bioassay and radwaste programs 9/77-5/78 Health Physics Technician, Radiological Services Dept., Purdue University Duties: Assist Radiation S'afety Officer in leak testing, receipt of radioactive material, laboratory survey and decontamination. Licenses and Certificates None. i Page 5 of 10 .g a f il

6 i t I ATTACHMENT 4 t Experience With Radiation - Mark W. Granus Where 9 Isotope Maximum Amount Experienced Gained Duration Type of Use I MFP* Trace to Kilo Curies Dresden Nuclear 2.5 yrs. Power Reactor i j Power Station Health Physics I j CO-60 7500 Curies Purdue University 3 mos. Irradiation i Facility CS-137 30 Curies Dresden Nuclear 2.5 yrs.__,, Calibration j Power Station Facility CS-137 3 Curies Purdue University 9 mos. Calibration Device CO-60 1500 Curies Purdue University 9 mos. Irradiation I Facility I i l

• Mixed Fission Activation & Corrosion Products-By Product, Source and Special Nuclear Material i

l I i k

• N,[

@g l .i o' i i 6 4 t (

p ATTACHMENT 4 NAME: F. Peter Jaeger WORK EXPERIENCE ~ , NUCLEAR WORK: POSITION: Health Physics Specialist Pennsylvania Power & Light Co. Susquehanna SES DATES: November 1977 to Present LOCATION: 'Susquehanna Steam Electric Station - Berwick, PA DUTIES: Assisted in the development and writing of health physics procedures, based on FSAR and tech spec requirements, for a two unit BWR. (1050 MWE) Responsible for developing our health. physics budget from pre-fuel load through Unit I outage. Procured the bulk of equipment and supplies required for normal operation and outage situations. Supervised 10 Health Physics Monitors for the past year and a half since they were brought into our section. Spent five days (Mar. 28-Apr. 2) at TMI providing health physics support to Met-Ed. This support was in the form of on-site /off-site radiological surveys, aerial surveys, job coverage for any entry to island, etc. Revamped our emergency materials budget as a result of the experience gained at TMI. POSITION: Radiation Protection Man Florida Power & Light Co. Ft. Pierce, FLA DATES: June 76' to June 77' LOCATION: St. Lucie I DUTIES: Radiation Protection Man - Joined the Health Physics Department at St. Lucie Nuclear Unit #1 (850 (MWE'PWR) at start of fuel modification program. This program consisted of removing all the fuel from the reactor and changing faulty poison pins. Provided HP coverage for all phases of this job. This included radiation / contamination surveys, air and gas sampling, writing Radiation Work Permits and providing constant HP coverage for all hot work done in containment building. This project completed after five months and plant went back on line. Routine duties then consisted of conducting required (license) surveys, air samples, instrument calibrations, procedure review, etc. We also coordinated work with operations / maintenance and provided HP coverage where needed. Page 7 of 10

4 POSITION: Lead Shift Tech Nuclear Fuel Services DATES: 1967 to June 1976 LOCATION: West Valley, N.Y. j l DUTIES: Supervisor Technician - Waste Burial Site - Receive and monitor all radioactive waste from outside sources and our own waste. Determine which area of burial grounds to bury waste, oversee operation of burial and supervise six to eight operators. i Maintain radiation and contamination control burial gounds, keep burial records and coordinate shipments. Health Physics Coordinator - Supervised two junior technicians and provided HP coverage during our clean up effort following an incident in our fuel pool storage area. This task consisted of having an average of 10-15 contract personnel per shift who were indoctrinated, suited up and provided health physics coverage while working in highly contaminated areas. Dose rates were routinely-10-50R/hr. Lead Shift Technician Responsible for all aspects of health physics functions during off shifts and weekends at fuel i reprocessing plant. Duties included conducting radiation surveys, air sampling, and personnally entering and inspecting 4 work areas before entry by operations / maintenance / contract personnel. Contract pe,rsonnel averaged 20-30 men per sh'ift. Determine dose rates, working times, shielding if required, respiratory and clothing requirments for work in grossly contaminsted ar,eas. Personnaly monitor all work in these areas to insure there were no overexposures. 4 EDUCATION: Hamburg High School, Hamburg, New York 1957 - 1961 U.S. Army Administration School; Fort Harrison, Indiana '" Personnel Administrative Specialist Course" University of Maryland; extension courses in math and history. Labor Relations; plant level at Nuclear Fuel. Services Red Cross; several advanced first aid courses. l SPECIAL TRAINING / COURSES: Radiation Protection Technology - Rockwell International (1 week) Basic Health Physics - Harvard University (1 week) i Respiratory Protection Course - Los Alamos Lab. (3 days) BWR Systems Course - General Electric (3 weeks) BWR Design Technology - General Electric (3 weeks) Instructors Course - PP&L (1 week) i Instructors Course - American Red Cross (multi-media, CPR) Page 8 of 10 l l t-

PROFESSIONAL SOCIETIES: Delaware Valley Society for Radiation Safety CERTIFICATIONS: - Registered (1978) with the National Registry of Radiation Protection Technologist (NRRPT) as a Radiation Protection Technologist. s 2 i 4 Page 9 of 10 ., 7.

l l' j T l ATTACHMENT 4' Experience with Radiation - P. Jaeger Isotope Amount Location Duration Type of Use Mixed fission, activated Trace to Nuclear Fuel Sys. 9 years Fuel Reprocessing I and corrosion products. kilocurie-West Valley, NY-i Byproduct and Special j nuclear material. Florida Power & Light 1 year Reactor H.P. Program i St. Lucie I l i s f i I I 4 "0 0iS IO en fW I a i l a

ATTACHMENI 5 RADIATION SAFETY TRAINING PROGRAM Individuals working with licensed material will, as a minimum, receive Level I-and Level II Health Physics Training or equivalent. To be qualified in Level I Health Physics an individus1 must demonstrate proficiency in the following areas as evidenced by passing a written exam. All training shall be conducted by Pennsylvania Power & Light personnel with lesson plans and instruction material approved by the Health Physics - Supe rvisoc. Retraining shall be conducted at least once every two years. o Requirements of 10CFR19.12 Radiation / Contamination (examples and controls) o ALARA (Corporate commitments, meaning and individual responsibility) o o Personal Monitoring and Self-Survey Requirements o Radiological Control Signs and Posting Requirements . o Radiological Control Signs and' Posting Requirements o Radiation Exposure Control and Limits o Radiation Emergency Plan and Applicable Procedures Prenatal Radiation Exposure

• o To be qualified in Level II Health Physics an individual must demonstrate proficiency in the following areas as evidenced by passing a written exam.

o All Level I Areas Listed Above o ALARA o Contamination Control and Self-Survey Requirements o Fundamentals of Radioactivity j o Radiation Dose Units and Biological Effects f Radiation and High Radiation Area Survey Techniques ( o Principles of Radiation Safety (time, distance and shielding) o o Radiation Work Permits (RWP) l Use of Protective Clothing / Devices o i u

I I g r + LOW LEVEL RADWASTE HOLDING FACILITY TABLE OF QUALITY ASSURANCE APPLICABILITY s ? 1 System, Equipment Installation or or Structures Testing Engineering Construction Manufacturing i The Building No Yes No N/A Foundations No Yes No N/A i Building Framework No Yes No. No i Building Shell No Yes No No

n.

Floor Pad No Yes No No Internal Shield Walls / Roof No Yes No No i 0bors No Yes No No t The Overhead Crane Yes Yes No Yes Ventilation System Yes Yes Yes* Yes Lighting System Yes Yes No No i Floor Drains System Yes Yes No N/A l I Fire Detection System Yes Yes Yes Yes Fire Protection System Yes Yes Yes Yes l Trash Restraining System N/A Yes Yes No AC Power System Yes Yes No No Radiation Monitoring System Yes Yes Yes Yes Security System Yes Yes No No Annunciator System Yes Yes No No Grounding System Yes Yes No No Communications System Yes Yes No No i e 9

• Auto Shutdown Feature Only, i

4 I 9

s, ; 4 ATTACHMENT 7 OPERATIONAL ACTIVITIES CONTROLLED BY PROCEDURE Operational procedures for facility loading, unloading and inventory shall be developed. Activities such as cask leading and vehicle inspection shall - be perf.ormed in accordance with existing plant procedures. Health Physics procedures for container survey and inspection and vehicle survey will be covered in existing plant procedures. 9 0 m . n -vw .-w ,,r., w.-%,e-,_ o, ,3. w., 1.--.

ATTACHMENT-3 e .o SSES-FSAR 12.5 MEALTH PHISICS_PgggBA3 12s5s1__QRi&513AIIGH 12s5.1.1__ Int;oducti3n The Realth Physics p:3aram at S'Isquehanna SES is developed and isolementel to evaluate and document plant rtdiological coniitions and assura that every reasonable effort is expended ta maintain personnel orcosure as low as reasonably achievsole (ALAR A). The Health Physics organiza. ion is displayed an Figure 12.5-1. 12s5 t ! s2__Re saen-sihiiities The Health Physics Supervisor is responsible to the Superintendent of Plant. The Health Physics Supervisor is charged with the responsibility of providing the Superin tendent of Plant with the information necessary to establish compliance with regulations pertaining to radiation sa f e t y, unif ora enf orcement of Station Health Physics requirements, and that every reasonable effort to minimize personnel exposures has been made. In addition, the Health Physics Supervisor is responsible for i assuring the staff who implement the Health Physics program is trained and retrained in operational Health Physics principles applicaole to Susquehanna SES. The Health Physics Engineer is removed from the line function of day to day Health Physics activities to provide the latitude and time to develop and implement a station ALARA program that is responsive to plant status. The Health Physics Engineer's major responsibility is to provide the Health Physics Supervisor the information necessary to establish that every reasonable effort has been made to sinimize personnel exposures. The Health Physics Specialists assure implementation of the Station Health Physics program by supervision of routine and special survey and evaluation programs required by applicaole regulations and procedures. The Health Physics Specialists' saior responsibility is to provide the Health Physics Supervisor the information necessary to establish that survey and record keeping requiremen ts are properly set and that plant activities receive appropriate Health Physics a ttention. 12.5-1

SSES-FSAR The Health Physics Monitors implement the Health Physics Program by performing routina and special surveys and providing Health Physics surveillance in accordance with Station Health Physics Procedures. 12z5sizl-Latk2LLL1 The Superintendent of Plant, ul tima tely responsible for all station activities including radiation safety, receives direct reports from the Health Physics Supervisor concerning the status of the Health Physics program. To assure uniform enforcement of Health Physics requirements, the Superintendent of Plant delegates his authority with respect to radiation safety to the { Health Physics Supervisor. The Health Physics Supervisor has the authority to cease any work activity when, in his professional iudgment, worker safety is ieopardized, or unnecessary personnel exposures are occurring. The Health Physics Engineer has *.he independence and authority to assure that iobs are accomplished with minimal exposures. Independence f rom routine Health Physics activities allows the obiectivity necessary for selective review and recommendation of work olanning packages such as Radiation Work Permits (R WP), work requests, and special maintenance procedures, in accordance with station procedures. The Health Physics Supervisor delegates authority to the Health Physics Engineer to cease any work activity which is not being perf ormed in accordance with As Low i As Beasonably Achievable ( AL AH A) procedures. The Health Physics ~ Engineer has the authority to conduct informal training and/or discussions with workers and supervisors regarding observed Dractices and ALARA recommendations. The Health Physics specialist has the authority to assure that iobs are conducted in accordance with Health Physics procedures and HWP requirements. The Health Physics 3upervisor delegates the authority to the Health Physics Specialist to cease any work activity which is not being perforaed in accordance with HWP requirements. In the aosence of Health Physics Supervision, the authorities of the above positions say be delegated in accordance with Station Health Physics procedures to snif t supervisors or assistant shift supervisors who have successfully completed Level IV training as described in Subsection 12.5.3.7. A member of Health Physics Supervision, or an individual zeeting the ainimum experience and qualification requirements of one or more of these positions, will be available for consultation regarding Health Physics and ALARA concerns. 12.5-2 9

a SSES-FSAR The Health Physics Ronitors implement Health Physics and HEP requirements under the direction of qualified supervision. 12.5.1.4 Experience and Qualification The Health Physics staff, responsible for the Health Physics progras at Susquehanna, will meet qualification requirements. minimum expe rience and The Health Physics Supervisor will be an experienced professional in applied radiation protection at nuclear power plants or nuclear facilities dealing with radiation protection problems similar to those at nuclear power stations; f amiliar with design features of ' nuclear power stations that the affect the potential for exposures of persons to radiation; in possession of technical competence to establish radiation protection programs and supervisory capability to direct the work of professionals, technicians and journeyman required to implement such programs. The Health Physics Supervisor will have a minimum of nine of experience in applied radiation protection which years five yea rs of professional experience. is to include Four years of the experience requirement a science or engineering subject.may be fulfilled by a bachelor's degree in Three years of the professional experience vill be in a nuclear power plant nuclear f acility dealing with radiological problems similar to or those encountered in nuclear power stations. One year of professional experience may be fulfilled by a master's degree and two years say be fulfilled by a doctor's degree where course rela ted to radiation protection is involved. work The Health Physics Engineer will have a minimum of five experience in a pplied radiation protection in a nuclear power years of plant or a nuclear f acility dealing with radiological problems similar to those encountered in nuclear power stations. four years of the experience requirement Up to ma y be fulfilled by related technical training or academic training in a science or engineering subject. The Health Physics Specialist will have a of experience in applied radiation protection to includesiniaua of four years two REV. 1 8/78 12.5-3

SSES-FSAR { reats of exnerience in a nuclear power plant or a nuclear f acility dealing with radiological problems similar to those encountered in nuclear power stations. A magiaua of two years of t'he e roerience requirement may be f ulfilled by related technical t ra i ta inq or academic training in a science or eagineering subiect. To at all times assure adequate aanpower f or Health Physics supervisory functions, the experience and qualification requirements,of the Health Physics Engineer and Health Physics Specialist positions may be reduced on a temporary basis. The Superintendent of Plant will approve or disapprove such action following review of the Health Physics Supervisor's recoamendations and iustification. The Health Physics Monitor will meet tne qualification requirements of Subsection 12.5.3.7. 12s5s2__ZAGILIII324_30 HIP 5ENT & 13EIRUM][TATIQH 12sSs2s1__Cqattg1_gigustgre_rectiitigg The facilities, shown in Figure 12.5-2, are located *at the central access to the Controlled Zone, elevation 676', for efficiency of operation. Self-survey personnel sonitoring equipment, such'as hand and foot, portal, or Geiger-Mueller (G-M ) type friskers, viil be located at the exit from the central c access control area. Self-su rv ey req u ire men ts will be administratively imposed prior to exiting the Controlled Zone. 12s5s2slzl_.Has11h_EhIEics Facilitigs The Health Physics office and workroom are located along the Central Corridor. Job planning and Radiation Work Permit coordination may be conducted through the pass-thru wind ow of the w or k r oom. PortaDie radiation survey instrumentation as well as air monitoring and sampling equipment, self-reading dosime te rs, and atscellaneous Health Physics supplies will be stored in the Health Physics Office and Workroom area. Healta Physics equipment used for routine counting oc smears and air samples such as end window G-M counters, alpha and Deta scintillation detectors, and/or gas flow proportional counters will be located in the Health Physics Office to prevent cross contamination of chemistry samples and minimize counting room background variations. Health Ph ysics samples requiring gamma isotopic 12.5-4

SSES-FS AR analysis and/or low level counting may be analyzed in the Counting Room. Health Physics use of the Counting Room will be coordinated with tne Chemistry Group. The Health Physics office will be equipped with filing cabinets and bench tops for survey record keeping and RWP preparation. Decontamination facilities at the central access control area consist of a main personnel decontamination area and auxiliary decontamination area. Auxiliary toilets and locker room are also provided. The personnel decontamination areas contain showers, sinks, and decontamination agents. Decontamination area ventilation is filtered through prefilter, High Efficiency Particulate Air (H.E.P.A.), and charcoal filters prior to exhaust through the Turbine Building vent. Sinks and showers drain to the chemical drain tanks for processing through the Liquid Radioactive Waste System. G-M type friskers will be located at these areas for personnel contamination monitoring. Portaole radiation survey instruments and self-reading desi.Teters will normally be calibrated in the instrument calibration room using a calibration apparatus or appropriate neutron, beta and Gamma sources, traceable to the National Bureau of Standards (N.d. S. ). Sources will be stored in locked source containers and storage areas will be locked when not in use. Portable sources used to calibrate the area, process, and effluent radiation monitoring system as well as small solid and liquid sources used to calibrate the counting room instruments may be stored here. The calibration apparatus will utilize sources of varying strength and energy and/or varying thicknesses of shielding to provide a radiation field of known strength for use in calibrating portable radiation survey instruments. P ro visio ns will be available for calibrating instruments in reproducible geometries. An N.B.S. calibrated condenser R-seter will be used to accurately zeasure radiation levels to determine source to detector distances for desired instrument calibration rhdiation levels. Record of calibration and repair for portable radiation detection instruments will be maintained on file. Instrument calibration may be performed by a qualified vendor. Records of such calibrations will be maintained. The laundry room will be equipped with a washer and exhausted dryer to launder contaminated protective clothing / equipment. Facilities include a transfer table and stainless steel sorting table with exhaust hood. Protective clothing, laundered on site, will be selectively monitored for contamination, sorted and stored in the Protective Clothing area or Laundry Storage Room. Laundry detergents for protective clothing laundering, and other appropriate supplies will be stored in this area. The laundry table and dryer exhaust is discharged to the Turbine Building vent. Liquid laundry effluent will be collected in the Laundry 12.5-5

a e SSES-FS AR Drain Tanks for sampling and analysis prior to processing through the Liquid Radioactive Waste System. The first aid room will contain a medical service center and toilet. Adequate supplies will be maintained to administer first aid for iniuries requiring immediate attention. An inventory of first aid supplies will be performed at a frequency specified in station procedures to assure an adequate stock is maintained. Individuals requiring first aid will be checked by Health Physics personnel for wound contamination prior to administering first aid, when applicable. The locker room contains approximately 100 lockers. Controlled zone workers may change f rom street clothing into plant clothing in the locker room. Personnel scheduled to work on Radiation Work Permit jobs may also change into clean protective clothing in the locker room. Adjacent to the locker room is a toilet and washroom, shower room and drying room. Frequently occupied contaminated areas will have local change facilities with appropriate protective clothing supplies to minimize the spread of contamination from work areas. Storage f acilities will be located in the Central Access Control Area for storage of anti-contaminati'n equipment, respiratory o protective equipment, and miscellaneous Health Physics supplies. The Energency Equipment and Laundr'. Storage Room will be used for storage of protective clothing and emergency equipment. 12s5.2 1.2 aidiochtnistry Paciliti21 Radiochemistry facilities consist of a sample room, radiochemistry laboratory, and counting room. The sample room is shielded with 186" concrete walls and contains cabinets with worktops, s ink, wall mounted storage cabinets and a fume hood assembly exhausted through prefilter, H.E.P.A. and charcoal filters to the Turbine Building vent. The radiochemistry laboratory will be utilized for sample preparation and contains filtered fuse hoods with service air connection, refrigerator, utility tables, sinks, cabinets, and drawers. The concrete walls range in thickness from 1' to 3'2". Fuse hoods are exhausted through prefilter, H.E.P. A., and charcoal filters to the Turbine Building vent and the sinks drain to the Chemical Drain Tanks for processing through tae Liquid 12.5-6

SSES-PSAR Radioactive Waste System. An emergency shower is accessible fros both the radiochemistry and chemistry laboratories. The Counting Room is constructed with 1'6" concrete walls to provide a low background environment f or analysis of . radiochemistry samples of station ef fluents and process streams. Instrumentation, such as a gas flow proportional coun ter, liquid scintillation counter, alpha and beta scintillators or crystals, end window G-M, and Germanius, Lithium drifted, Ge (Li) and/or Sodium Iodide (NaI), systems will be utilized for counting a nd/or analysis of radiochemistry samples. 13.522,123_ chemistrI_idontory The chemistry laboratory contains an exhaust hood assembly with service air connection, drawers, worktops, sinxs and laboratory equipment necessary for perforainq chemical analyses on non-radioactive plant aaterials. Station chemist ry procedures will provide administrative control to assure that, under normal conditions, only non-radioactive aaterials are analyzed in the Chemistry Laboratory. The laboratory exhaust hood discharges to the Turbine Building vent and the sinks drain to the neutralization tank for processi*ng through the Liquid Radioactive Waste System. a g 12t5s2s2__Radrasts_aut141as_Easiliains The Radwaste Building elevation 646', 676' and 691'o" facilities are located as shown on Piqures 12.5-3, 12.5.-4, and 12.5-5, respectively. Ventilation is filtered through prefilter and H. E. P. A. filters prior to exhaust to the Turbine Building vent. Drains discharge to the Chemical Drain Tank and Laundry Drain Tank for processing through the Liquid Radioactive Waste System. 12t5t2.2.1__ladvasta_anildina_sigratiga_ gas'o" The f acilities consist of a solid waste packaging, decontamination, and monitoring area, personnel decontamination facility and personnel decontamination facility ad1acent to the laundry drain sample tank. The solid waste packaging area contains an apparatus for remote capoing operations, dater spray nozrles for container 12.5-7

i SSES-PSAR decontamination, and a remote smearing device for monitoring package surface contamination. The two (2) personnel decontamina tion facilities contain showers, sinks and appropriate decontamination agents. 12s5s222s2__gasvasse_Buildina Eleva tion 676 'oa The facilities consist of an instrument repair shop, sample room, repair area including a welding area, personnel decontamination room, controlled zone shop including a washdown area, monitoring and final decontamination area, and storage area. The Instrument Hepair Shop will be equipped with an assortment of tools and equipment necessary for work on contaminated instruments. The sample room provides a central location for sampling various Radwaste Systems. Samples will be analyzed by the Chemistry to determine the final disposition of the effluents being group p rocessed. The Repair Area vill be used for maintenance and welding of contaminated equipment. Appropriate tools and equipment, including velding equipment, will be stored in this area. The personnel decontaminatioa room will be equipped as those described at the central accbss con trol area. It is conveniently located to f acilitate the ra~pid removal of contamination from personnel working in the instrument repair shops, sample room, repair area, or controlled zone shop. The controlled zone shop will be equipped similar to the station machine shop. Repair of contaminated coaponents will be performed in this area. The adioining washdown area vill be used for decontamination of components and equipment to be worked on in the controlled zone shop and is constructed with a 6" curbing. The monitoring and final decontamination area will be used for surveying and decontamination, if necessary, of radwaste Containers prior to Storage. A storage area is available on the 676'0" elevation for storage of anti-contamination equipment, respiratory protective equipment, and miscellane ous Health physics supplies. 12.5-8

l SS ES-FS A R 12sEs2a2t2__Radwaste_ggilding Elevation 691' 63 The Health Physics f acilities consist of a contaminated laundry and storage area, clean laundry and storage a rea, personnel decontamination area, Health Physics area, and janitor's closet. The contaminated laundry area contains two (2) washers and two (2) exhausted dryers, an exhaust hood and sink, aiscellaneous tables and carts, and a storage area for laundry detergents used in orotective clothing laundering, disinfecting agents f or cleaning of respiratory protective equipment, and other supplies. One washer will be labeled and administratively controlled by station procedure for use in cleaning of respiratory protective equipment only. Contamination limits will be specified by station procedure for the respiratory protective equipment washer. A separate area within the laundry f acilities will be used for maintenance and repair of personnel respiratory protective equipment. Equipment will be cleaned in the designated washer, dried, inspected and disinfected, wrapped in olastic or paper bags, and stored in the Energency Equipment and Laundry Storage Room, Badwaste Building Health Physics Area, or other designated area. The laundry effluent will be disquarged to the laundry waste storage tanks for sampling prior to processing through the liquid radioactive vaste system. The clean laundry area contains two (2) washers and two (2) exhausted dryers, a sink, and. miscellaneous tables and carts. The facility will normally be used for laundering of station c lot hing not used as anti-contamination clothing. Laundry drainage will be collected in the laundry drain tanks for sampling prior to processing through the Liquid Radioactive Waste System. The personnel decontamina tion area will be equipped as those at the central access control area. The Health Physics area will serve as an office for Health Physics personnel and storage area for Health Physics supplies and equipment in support of Radwaste activities. Equipment and instrumentation will include portable survey instruments, air sasolers, counting equipment, respiratory protection-equipment, contamination control supplies and other related Health Physics supolies. i l 12.5-9 . -. ~.

SS ES-FSAR 12.5.2.3 Beactor Buildino Facilities The Reactor Building elevation 719'18 facilities are located as shown in Figure 12.5-6. Each unit has two (2) energency personnel decontamination stations and a washdown area. The two (2) energency personnel decontamination stations contain showers and sinks, a monitoring station with frisker and protective clothing, and appropriate decontamination agen ts. The washdown area vill be used for equipment decontamination prior to maintenance and is constructed with a six (6) inch curb. Ventilation from these areas is filtered through prefilter, H.E.P.A., and charcoal filters prior to exhaust through the Reactor Building vent. Drains discharge to the Beactor Building Sump, Chemical Drain Tank, and Laundry Drain Tank for processing through the Liquid Radioactive Waste System. _12.5.2.4 Tugbine Buildino Facility ~ The 729' elevation of the Turbine Building contains a washdown area, with 6" curbing for turbine blading and component decontamination prior to maintenance. Ventila tion f rom this area is filtered through prefilter, upstreas H.E.P. A., charcoal, and d ownstreas H. E.P. A. filters prior to exhaust to the Turbine Building vent. Drains discharge to the Turbine Building Chemical Radwaste Susp for processing through the Liquid Radioactive Waste S yst em. 1 5 M __G ugd House Building l The Guard House building serves primarily as the access control .;to the restricted area of the plant. Personnel dosimetry will normally be issued and stored at this area. A portal monitor and/or G-M type f risker will normally be maintained at this location as the final monitoring area prior to lea ving SSEs. 1 REV. 1 8/78

12. 5-10 l

SSES-FSAR 12.5s2=1__dgal th. PhIgigg Ecu ipmens 12.5s2.6sl__Er91ss11Is_Glothins Protective clothing will be worn in contaminated areas to prevent personnel contamination and aid in controlling the spread of surface contamination. Protective clothing available at Susquehanna SBS will include: reusable coveralls and lab coats, disposable coveralls and lab coats, plastic suits, surgeons caps, cloth hoods, plastic hoods, splash shields, cotton glove liners, cloth gloves, rubber gloves, disposable gloves, gauntlet gloves, rubber shoe covers, rubber boots, and disposable shoe covers. Protective clothing will be stored at the Protective Clotning Area, Emergency Equipment and Laundry Storage Room (Figure 12.5-2), plant laundries (Fiqure 12. 5-6), and selected local change areas. After use, protective clothing will oe laundered and socitored, or surveyed, packaged and shipped to an off-site e vendor for laundering, or discarded as radvaste. 12.522sszl__HedEiEA12EI Protective 312iRaval Respiratory protective equipment will be used to miniaire the intake of radioactive material when engineering controls are not practicable. The Respiratory Protection Progras is described in Subsection 12.5.3.5. Respiratory Protective Equipment utilized at Susquehanna SES will consist of National Institute of Occupational Safety and Health /Mine Equipment Safety Administration, (N. I. 0. S. H. /M. E. S. A. ) approved air purifying re spira to rs, self-contained brea thing apparatus (pressure demand), pressure demand air line respirators, constant flow air line respirators, and constant flow air line hoods, welding mas ks a nd plastic suits. A variety of respiratory devices will be available to assure proper fit of the differing facial contours of personnel requiring respiratory protection. Sufficient quantities of respiratory ' protective equipment will'be available to allow for the use, decontamination, maintenance, and repair of equipment. Respiratory Protective Equipaent will be availaDie at the Energency Equipment and Laundry Storage Room (Figure 12.5-2), and Radwaste Building Health Physics Area (Fiq ure 12.5-3, 12.5-4 and

12. 5-5).

Respiratory Protectivo squipment will be a vailable f or energency use at the Energency Control Center and Control Roos. N. l. 0.S. H. /5. E. S. A. approved emergency escape devices will be 12.5-11

SS ES-FS A R placed at locations where the potential exists for an unexpected increase in radioactive or chemical airborne concentrations (such as the water treatment building and radwaste system). Fifteen (15) escape devices will also be located in the control room. If applicable, respiratory protective face pieces will be wrapped in plastic bags and stored individually to prohibit plastic deformation. 12 s 5 s 2ss =3__11t_1Anali ng_Isu i p m en t Air saanling equipment will be available at the Health Physics office (Central Access Control Area, Figure 12.5-2) and the Health Physics Station (Radwaste Building, Figure 12.5-3). Airborne activity levels will be determined by the use of continuous airborne monitors (CAHS), high and low volume portable air samplers, and breathing zone air samplers. Five (5) CANS, five (5) high volume air samplers, five (5) low volume air samplers, and two (2) impactor attachments will be available for use a t Susquehanna SES. The CA5 (s) can be used to measure particulate and gaseous activity. The air samplers can be used to measure particula te and iodine activity using the appropriate filtering medium. Particulate activity and particle size distribution can be determined using an impactor attachment. Volumes necessary for T representative samples will be specified in Station Health Physics procedures. Filt er media such as H. E.P. A. filters and charcoal cartridges will be stored at the Health Physics office and Workroom Area. 12s5s2 1=Jal__.qsatinunaa_ Air _asaiter.s will normally be used to sample selected areas of potential CAMS airborne concentrations. CAM sampling rates will be checked against calibrated rotometers or ver test meters on a quarterly basis and af ter pump replacement or repair. If CAM's are equipped with strip chart recorders or local readout, a base line sampling program will be completed prior to Unit 1 fuel load to allow estination of naturally occurring isotopes' contribution to airborne background. CAM detector response to an appropriate check source will be performed on a quarterly basis. Manufacturer's recossended calibration or voltage plateau procedures will be performed on a quarterly basis. If applicable, operation of local alarms will be verified on a 12.5-12 t

SSES-FS&R guarterly basis. l 12.5.2.6.3.2 Portable Air Samplers shen possible, each portable air sampler will be monitored for flow rate as above. Devices utilizing flow noters will be checked against calibrated rotometers or wet test meters when practicable. Manufacturers' certification of flow rate vill be utilized when physical flow measurements are not possible due to equipment design. 1225.2.6.3.3 Breathino Zone Samplers t Ten (10) battary powered breathing zone samplers will be available for use in evaluating air concentrations that radiation workers may encounter. Personnel breathing zone samplers will be checked for flow rates as above if practicable. If design prevents physical flow measurement, manufacturer's certification of rated flow or accuracy of flow meter will be utilized. 12.5.2.6.3.4 Samolina Media Particulate air concentrations will be sampled with H.E.P. A. sampling media or impactor attachments. Manufacturer's certification of collection efficiency will be utilized in calculations of airborne concentrations. Surveys for radioiodine concentratioas will normally utilize charcoal in a reproducible geometry such as a cartridge. If studies to determine various forms of radioiodine are required, reproducible geometries of materials such as cadmium iodide, 4-iodophenol, and silver zeolite say be used with charcoal in various configurations. If charcoal impregnated filter paper is utilized in equipment such as breathing zone acnitors, manufacturers recommended sampling rates and times will be f ollowed whenever practicable. l REV. 1 8/78

12. 5-13 1

SS ES-FS A R i 1225s2tsi3.5-Specigl_ Air Samplina t s. Water bubblers, dessicant columns, or cold traps will be available for tritium air sampling, and gas sample containers (such as Marinelli containers) will be available for special caseous air sampling. 12.5 t2 ts,.H__EsEanaanl_ Do s i m e t ry The Personnel Dosimetry program is described in Subsection 1 12.5.3.6. Self-reading dosimeters of five different ranges for use at Susquehanna SES are as follows: Haa2g_faR) No r ma l_Qqg________lBabe E_A vaila ble 0-200 Low Dose Accumulating Work 400 0-500 Intermedia te Dose Accu mulating 75 Work 0-1000 High Dose Accumulating Work 50 0-5,000 Radiation Energency Plan Use 25 0-100,000 Radiation Emergency Plan use 25 ). i A total of five (5) dosimeter chargers will be available at the a Central Access Control Area Health Physics office and the Radwaste Building Health Physics Station. Self-Reading 4 Dosimeters will also be a vailable at these locations. Dosiaeters I will be tested for calibration response charging drif t, and leakage prior to initial use, and on a six month frequenc~ thereafter. If vendor service is not utilized, approximately 1500 thermoluminescent dosimeters (TLD) will be available for use as the dosimetry of record. TLD (s) will be used for neutron, b e ta, l and ganna exposure and will normally be evaluated on site. Approximately one hundred (100) extremity TLD devices will be l available for issue when authorized by Health Physics persontsl. If applicable, a TLD reader will be installed and calibrated in accordance with vendor's ins + ructions. Operation will be conducted by qualified ind4-iduals in accordance with approved station procedures. ) :ertornance testing progran will be implemented to assure the TLD reader is properly calibrated and exposure inf orma tion is accurate. 12.5-14 4

SS ES-PS AR Internally deposited radioactive ma terial will be evalua ted with whole body counter sufficiently sensitive to detect in the a thyroid, lungs, or whole body a f raction of the permissible body / organ burden for gamma emitting radionuclides of interest. The whole body counter will be calibrated on a quarterly basis using phantons and standard solutions of various radionuclides such as Co-60, Ce-13 7, and Ba-133. The detectors will ne used in coniunction with a multi-channel analyzer and associa ted readout to obtain a permanent record. A vendor whole body counting system on or off site may be used as an alternative or supplement to a PPSL whole body counter. Teu (10) battery powered personnel alara dosimeters will be available for use when an audio alara at a prese t accumulated exposure or exposure rate may be advantageous. Personnel alara dosimeters will be checked f or accuracy on a quarterly basis and following any repair affecting calioration. 12s5 2s525__5iace11gge2us Eculpagna t The following miscellaneous Health Physics equipment will be stored at various locations in the plant: Contamination control supplies such as glove bags, conta mine nt tents, absorbent wipers, a bsorben t paper, rags, step-off pads, f rope, plastic sheets, plastic bags, tape, contamina tion area signs, and pro tective clothing. Appropriate supplies may be assembled into kits and located throughout the plant to aid in the control of a contaminated spill. Temporary shielding, such as lead bricks, lead sheets, and lead wool blankets, will be available to reduce radiation levels. A trash compactor located on the 676' elevation of the Radwaste Building as shown in Piqure 12.5-4 This location will provide adequate storage and access f or loading at the rear truck access door of the Radwaste Building. The compactor and room will be vented through prefilter, H.E.P.A., and charcoal filters prior to exhaust to the Turbine Building vent. A fittinq dooaratus for quantitative test fitting of individual involved in the Respiratory Protection Program. The apparatus will De a sodium chloride (Nacl) aerosol generator with flame photometer, or equivalent system, to measure airborne conce ntra tions. Irritant smoke and/or isoamyl acetate will also be available to qualitatively test respirator fit. 12.5-15

i SSES-FSAR 1 12=5m2.2__dsallA_Ehrsisa_Inmarnaania112n Instruments for detecting and measuring alpha, ce ta, gamaa and neutron radiation will consist of counting room, and portable radiation survey /aonitoring instruments. All instrumen ts will be subiected to operational chects and calibration to assure the accuracy of seasurements of radioactivity and radia tion le ve ls. Primary and reference standards (utilizing, or prepared from, l standards of Sr-90, An-241, Cs-137, Co-60, H-3, and others, traceaDla to tne National Bureau of Standards) will be used to j maintain required accuracies of measurement. dackaround and efficiency checks of routinely used Health Ph ysics counting equipment will be performed daily and these instruments will be recalibrated whenever their operation appears statistically to be i out of limits specified in Station procedures. Routine calibrations will be perf ormed on counting room instrumentation and radiation survey / monitoring instruments on a quarterly basis and' a f ter repairs affecting calib ra t io n. Efficiency curves for multi-channel analyzer systems will be determined on a semiannual basis using N.B.S. traceable sources for various reproducible geome t ries. Sufficient quantities of instrumentation will be available to allow for use, calib ra tion, maintenance, and repair. The instrumentation descriDed in taese Subsections may be } replaced by equipment providing similar or improved capacilities. \\ 12.5s2.2.1__Gana11ag_B991_ Ins 1Isasala119a t-S Counting Room instruments for radioactivity measurements will include the following: A 4096 channel analyzer, using a 3" x 3", 7% resolution Na I crystal, and a 5 Kev resolution (at 1 Mev energy full width half maximum peak) GE(Li) detector, for identification and measurement of.camma esitting radionuclides in samples of reactor primary t i coolant, process streams, liquid and gaseous effluents, airborne and surface contaminants. one coaouter which can be interfaced with a pulse height i analyzer: aquipped with a teletype machine for entering instructions and printing results, a tape dect for enterinq ) programs and storing data, and an-1-Y plotter for making graphs. A low bacKoround gas flow proportional counter used for gross j alpha and cross beta measurements of prepared samples. 12.5-16 4 5

1 SS ES-FS A R A liquid scintillation beta counter used for seasurement of tritius in reactor primar y coolan t, liquid and gaseous wastes, and cross beta activity other taan tritium. A NaI well crystal with counter-scaler or pulse height analyrer used for gazza analysis of various radionuclides in samples of reactor priaary coolan t, liquid and gaseous wastes, or prepared samples. One beta-gaasa counter-scaler, thin end window (2 aq/sq. ca, 2-Inch diameter G-M) used for gross beta-gazza measurements of reactor primary coolant or prepared samples. One alpha scintillator or semiconductor cryscal used for gross alpha aeasurements of reactor primary coolant an d prepared samples. one beta scintillation counter-scaler used for gross beta measurements of reactor primary coolant and prepared samples. 12 sis 2s221__ Health _EhIsics office _ gad votttoom Instrumentation Health physics instrumentation normally located in the Health physics Office and Workroom will include the following instruments, or equivalent: One (1) automa tic and one (1) aanual beta-gamma counter-scaler, thin end window (2 aq/sq. ca), 2 inch diameter G-M, used for gross beta-canza aeasurements of removable contamination, air samples and nasal swabs. 2 An alpha scintillation or semiconductor counter-scaler used for evaluation of removable contamina tion, air samples and nasal swabs. A low background gas flow proportional counter used for gross alpha and/or beta measurements of removable contamination, air samples and nasal swabs. Ten (10) G-5 beta-gamma survey meters (most sensitive range 0.2 m 3/hr., maximum range 0-2 R/hr., with internal probe) used for detection of radioactive contamination on surfaces and for low level exposure rate seasurements. Ten (10) ionization chamber beta-gaaaa survey meters 0-5 rea/hr. (0-5 area /hr. most sensitive range) used to cover the general rance of dose rate measurements necessary for radiation protection e valuations. 12.5-17

SS ES-FS A R Five (5) wide range ioniration chamoer oeta-gamma survey meters (0-5 mR/hr. aost sensitive range, maximum range 0-50 R/hr.) used for exposure rate measurements. Four (4) remote monitoring (telescoping probe) G-M tune beta, gamma survey meters, 0-1000 R/hr, 0-2 mR/hr most sensitive range used for exposure rate measurements. One (1) cadaium loaded polyethylene sphere, 8F tube, neutron Rea 3 Counters 0-5 rea/hr (0-5 ares /hr most sensitive range). The instrument is used to measure the dose equivalent rate due to thermal, intermediate, and f ast neutron fluxes. Two (2) alpha scintillation survey meters, 0-23 cpm (0-2K cpm most sensitive range) 30% efficiency used for seasurement of alpha surface contamination. One (1) thermal and fast BF 3 tune, paraf fin moderated, neutron detectors, ("Lin-Log" decades of 0-500, 500-5,000, 0-50,000 and 50,000-500,000 cpa which is equivalent to 0-10,000 n/sq.ca/sec. for 1 Mev neutrons). Designed to detect thermal neutrons with detector removed froa moderator and fast neutrons with detector inserted in moderator. An indication on the seter can be correlated with a known neutron flux and a known energy to obtain com/n/sq.ca - sec (flux) which in turn can be converted to aren/hr. s. 122522s2Al__HSallh_2hIgicg_33dwastg_ Build gg_Instruggnia;1og i Health Physics Instrumentation normally located at the Health Physics Station in the Radwaste Building will include the following: One ( 1) thin vindow (2 aq/sq.ca) G-M detector with counter-scaler for gross beta-gamma measurements on smears and prepared samples. Five (5) Ioniza tion cha mber beta-gam aa survey meters 0-5 res/hr., (0-5 area /hr. most sensitive range) used for general survey work. Two (2) G-M beta-gamma survey meters (most sensitive range 0 .2 mR/hr., maximum range 0-2 R/hr., with internal probe) used for detection of radioactive contamination on surfaces and for low level exposure rate measurements. One ( 1) remote monitoring (telescoping Prope) G-M tube Beta, Ganaa survey meter 0-1000 R/hr., 0-2 mR/hr. most sensitive range used for exposure rate measurements. 12.5--18

SSES-PSAR i llzi.2.7.4 Personnel contamination Monitorino_ Instrumentation Personnel monitoring instruments consisting of friskers, port al monitors and a hand and foot monitor described below, will be used at the locations specified in Subsection 12.5.2. 1: Twenty-five (25) beta-gamma geiger count rate meters, 2ag/sq.ca window, 0-50,000 cpa range, adjustable audio and/or visual a la r as. Gamma sensitivity for Co-60 is 3,500 cpa/aR/hr. Beta sen sitiv ity (la diameter source, 2 pi): Sr-90/Yr-90 (E max. 0. 54-2. 2 M ev) = 455 C-14 (E zax. 0.15 Mev) 10% = Used to detect conta mination on personnel, mat eria ls, protective clothing, and equipment. Two (2) portal monitors consisting of eight audio and/or visual alarmed G-M detectors to provide head to foot beta-gassa detection capability. Count rate alara adjustable from 160-7000 cpa; counting time adjustable from 1 to 10 seconds. One (1) audio and/or visual alarmed hand and foot zonitor with ports monitored by G-M detectors for the hands and feet and a n external probe for frisking the body. Personnel contamination monitoring instrumentation will'be calibrated on a quarterly basis or following repair, in addition to monthly source checks, to determine proper response and alara operability.

12. 5. 2. 7. 5__ M i scella ne o us Hea l t h Physics Inst ru men ta t ion One (1) Condensor R-metor used to accurately seasure radiation levels consisting of one (1) low energy chamber (0.025R) and three (3 ) high energy chambers (0.25R,

2. 5R and 2 5R), which have been N.B.S. calibrated.

Other aquipment used for Health Physics rela ted f unctions will be maintained and controlled in accordance with station procedures. Such ewuipment may include: one (1) pulse generator for calibraing pulse counting instruments. One (1) wet test meter, one (1) calibrated flow mete r, one (1) veloseter, and one (1) aagnehelic pressure differential gauge. REV. 1 8/78

12. 5-19

SS ES-FS A R The location of the area, process, and effluent radia tion monitoring systems are described in Sections 11.5 and 12.3. 12.5.3 PROCEDURES The Health Physics Procedure Program, as described in this section, will be implemented by Susquehanna SES Health Ph ysics l Technical, Operating, and As Low As Seasonably Achievable procedures in accordance with Section 13.5. (ALABA) 12.5,3.1 control of Jccess and Star Time in Radia tion Areas Physical and administrative controls will be instituted to assure the philosophy of maintaining personnel exposures as low as reasonably achievable (ALARA), as specified in Section 12.1, is implemented. _12.5.3.1.1 Physical Controls _12.5.3.1.1.1 Security Check Point The security check point at the fence line perimeter will be a continuously manned physical control. Assigned personnel dosimetry devices and identification badges will be stored at this location when not in use. The security force will assure a that all personnel who enter the station are issued appropriate badges and dosimetry in accordance with station procedures. A restricted area access list will be maintained at the security entrance. Any individual not on the access list must be accompanied by a person who is authorized unescorted re stric ted area access. The training, retraining and testing requirements for unescorted access are described in the Susquehanna SES Security Plan. i 12.5.3.1.1.2 Secu ri t y Doors Although not primarily intended to control access to radiation areas, the security interlocked door system will assure only specifically trained and authorized individuals are able to open security entrances to the reactor, turbine, radwaste and diesel generator buildings. Security entrances will be locked or REV. 1 8/78

12. 5-20

SSES-FSAR provided with continual surveillance. Details of security access control are contained in the Susquehanna SES Security Plan. 12.5.3.1.1.3 Posting and Lockino 1 l A thied physical control will be the posting and locking, as appropriate, of radiation and high radiation areas. Radiation areas, as defined in 10CFR20.202 (b), will be posted in accordance with 10C FB 20. 20 3 (b). Plant areas that are routinely accessible will be surveyed in accordance with station proced ures to determine radiation le vels. In addition to recording the results of these surveys in accordance with 10CFR20. 401 (b), the radiation area signs will be updated by surveyors to reflect current conditions. Every reasonable effort will be expended to erect rope or other physical barriers to minimize inadvertent entry in radiation areas. High radiation areas, as defined in 10CFR20.202 (b), will be posted in accordance with 10CFR20.203 (c). These signs will be routinely updated to reflect current conditions. Surveys of high radiation areas will be performed and results recorded as above. Each entrance to a high radiation area vill be equipped with audible and/or visible alarms in accordance with 10CFR 20. 203 (c) (2) (ii) or controlled in accordance with 10CFR20. 203 (c) (2) (i) or (iii). In lieu of the above controls, high radiation a reas in which the 1 intensity of radiation is grea ter than 100 ares /hr. but less than 1000 area /hr. say be barricaded and conspicuously posted as high radiation areas and entries controlled by issuance of a Radiation work permit. In addition, areas in which the inte nsity of radiation is greater than 1000 ares /hr. will be provided with locked doors under the administrative control of the Shif t Supervisor. Controls utilized at entrances will at all times permit egress from high radiation areas. Any individual or g roup of individuals permitted to enter such areas shall be provided with or accompanied by one or acre of the following: A radiation monitoring device which continuously indica tes the radiation dose rate in the area. 1 A radiation monitoring device which continuously integrates the radiation dose rate in the area and alaras when a present integrated dose is received. Entry into such a rea s with this monitoring device may be made af ter the dose rate levels in the area have been established and personnel have been made-knowledgeable of them. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control i REV. 1 8/78

12. 5-21

~ _ _ _. _ _ -.

SSES-FSAR over the activities within the area and shall perform periodic radiological surveillance at the frequency specified by Health Physics Supervision on the Radiation work permit. Entrances to radiation areas and high radiation areas will be posted to reflect the requirement of a Radiation Work Permit (RUP) in accordance with limits specified in station procedures. s REV. 1 8/78

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i \\ t SS ES-FS A R 12s5sasl.1.4-SutIsillaana When appropriate, surveillance of work activities will oe provided to assure a positive control of access and stay time in radiation areas. Surveillance will be util' zed w hen it is necessary to assure accurate record of working time as an assistance to the work group. In addition, it may be utilized for tasks involving large numbers of workers to assure control at the staging or entry point. Surveillance may also be provided for tasks in areas where conditions are unstable to assure that timely instructions to workers are issued. 12 min.Jsl. 2 adainisitative controis 12zisasl L.1__. Training As specified in Subsection 12.5.3.7 personnel allowed unescorted restricted area access will receive Health Physics and related training in accordance with 10CFR 19.12. During this training, the individual responsibility of utilizing proper Health Physics procedures in radiation areas will be emphasized. The methods I utilized at Susquehanna SES to control access physically and administratively will be reviewed. Supervisory or other personnel responsible for the direction of workers may receive additional Health Physics training that will include guidance on work planning, controlling access, utilizing shielding and distance, and minimizing stay time in radiation a reas. 12sisJsis2=2__Eadiatign_ Work Persil_ The Radiation Work Permit (R W P) systes described in Subsection 12.5. 3.2 will be implemented to administratively control access and stay time in radiation areas. Work in radiation contamination or airborne levels greater than limits specified by station procedure will require the completion and approval of a RWP. For personnel or groups who aust routinely enter specific areas as a necessary part of work duties, a Standing Radiation Work Permit (SRWP) may be issued in accordance with station procedures. Application for the SRWP will specify the need for routine entry, and expected occupancy per day, week or month. The SRWP application will receive a survey, review and appro val process similar to that described in Subsection 12.5.3.2. Approved SRWP's will specify access and record keeping requirements as well as special instructions and mariaua sta y 12.5-22

SSES-FSAR time. An approved SHWP will ne considered in effect until conditions warrant a change and will be sub1ect to immediate cancellation by the Healta Physics Supervisor or designated alternate. Each SHWP will be revieved on a monthly basis by a Health Physics representative. 1215 s)sislzl_ Re port LR1_geauireaegt The individual responsibility to report, through proper chain of command, any violation of Federal Regulations or Station procedures will be emphasized during training sessions. Violation involving potential exposure of personnel to radiation or radioactive material vill be reported through appropriate channels to the Superintendent of Plant or designated alternate. A ppropriate action will be taken to prevent recurrence. Any individual who violates station procedures will be subject to i disciplinary action. 12s5s]2Js2s3__ lad 222EdSat_ggview A member of Health Physics Supervision will periodically observe activities in RWP areas to review the effectiveness of specified precautions. In addition, a member of Health Pnysics supervision may perform independent measupements of radiation levels to assure enat areas are properly posted to indicate accurate readings. During these surveys, the reviewer will assure tnat every reasonable effort has been expended to minimize inadvertent entry in radiation areas. 12,5,3,2,2,i__Erscaducg_ R evigw Health Physics procedures related to control of access and stay time in radiation areas will at all times be subject to review to assure every reasonable administrative effort has been expended to minimize personnel exposure. Recommended changes will be evaluated and, if necessary, a proposed change will be forwarded through appropriate review and approval channels. Approved chances requiring retraining will be forwarded to the Training Supervisor for scheduling and implementation. Health Physics procedures will be reviewed annually. 12.5-23

SS ES-FS AR 12.5.1.2 Assuring that occupational Radiation Exposure (ORE) Wall De As Low As Reasonaclv Achievaolg_JALARAL____ To ef fectively implement the corporate ALARA commitment as stated in Section 12.1, a station ALARA prog ra m will De utilized to assure that activities are performed with the lowest practicable personnel exposure. PP&L considers it necessary to apply tne basic concepts of ALARA to internal and external exposure to assure proper emphasis on both modes of potential exposure. Procedures employed to implement the program described in this section will be subiect to review and revision to assure the ALARA program is responsive to plant conditions. 12.5.3.2.1 ALARA Procedures Common to External and Internal ---.------- Ex29surs--------- 1215s312sizl-12ALDing Individuals allowed unescorted restricted area access will receive Health Physics training as described in Subsection 7 12.5.3.7. The individual responsibility of assuring that unnecessary exposure is to be avoided will be emphasized during Health Physics Training sessions. ), As appropriate, individuals involved in potentially hign dose accumulating iobs will receive pre-job training in exposare reduction techniques and controls applicable to the specific joo. 1225tJz2miz2_ Radiarian Worx Peggit Where radiation dose rates, anticipa ted accumulated exposures, airborne concentrations, or contamination levels exceed limits specified by station procedures, a Radiation Work Permit (a W P) will be initiated, completed and approved prior to commencement i of scheduled work. As a minimum, station procedures will specify that scheduled work in Zone IV or higher (greater than 15 m Re a/hr. ) will require completion of a RWP. Health Physics will evaluate the radiological conditions associated with the work to be performed. Based upon evalua tion of proposed work and surveys, Healta Physics will specify the a ppropriate protective clothing / devices, respiratory protective 12.5-24 )

4 SSES-FSAR equipment, dosimetry, special samples, surveys, procedures, precautions to be taken, and expiration date The RWP will be evaluated to assure the work will be performed from an ALARA approach. As appropriate, the evaluation will include review of proposed special tools, remote handling devices, access and co mmu nications needs, miniaua aanpower requirements, and work which may be performed outside of the RWP to increase. iob efficiency and reduce personnel exposures. area Potential incidents such as fires, spills, and equipment failure will be evaluated and proper response action discussed with radiation workers, when applicable. For high dose accumulating work, ion preplanning will include Man-Rea estimates, c om pa rison with similar iobs, estanlishing exposure goals, and simulated dry run, as appropriate, to increase ion efficiency. Radiological engineering controls will be used, when applicaole, to ainimize personnel exposures and prevent the spread of contamination and/or inhalation /iniestion of radioactive e mate rial. Controls such as flushing of tanks and lines, use of temporacy sh ieldin g, use of proper ventila tion and purging, and properly filtered. temporary exhaust will be considered. In addition, other ef fective methods of reducing aan-rea exposures a nd potential intake of radioactive material will be considered. When airborne concentrations cannot be reduced below station limits, the use of respiratory protective devices will be considered. x The RWP will be approved and signed by the Health Physics Supervisor or designated alternate prior to commencement of work. RWP implementing process will be detailed in Station procedures. A neaber of Health Physics supervision will selectively review j completed and returned RWP's. Selection, on a variety of bases, of those RWP's which should receive a post operation evaluation 1 'will De made. Arrangements will be made, when necessary, to hold a de-briefinq session with t he responsible supervisor and/or w orke rs. De-briefing and RWP review will be conducted when unexpected airDorne concentrations, high ma c-rea exposures or high individual exposures are encoun tered. De-briefing-will i emphasize and analyze problems or difficulties encoun tered during performance of work. Alternative work methods will be discussed and if improvements are practicable, the responsible supervisor will initiate the Leviev, approval and implementation process. 12.5-25 ,_-.= -

SSES-FSAR 32Aiz1t2:ltl_ Work = Gh2d111aS S s Use of the dadiation Work Permit system descrioed in the pre vious section will establish a data case from which supervisory staff will be able to efficiently schedule workers. Health Pnysics will orovide reports to supervisors that will indicate current individual exposure status to assist in work seneduling and assure individual exposures are minimized. 12s5s3z2.1z3__3322rtigg_Roquireggats Activities performed under an approved Radiation Work Perait must De carried out in accordance with the provisions of the RWP. Violation of RWP requirements will be reported to Health Physics and appropriate supervision. RWP violations that cause or threaten to ca use unnecessary personnel exposure may result in disciplinary measures. i 32s5slz2slsi__la12Ingl_Eggaram aevigws In an effort to provide more efficient methods of ~ control, evalu ttion, and reporting, a member of Health Physics supervision will conduct reviews of the RWP program and procedures utilized to minimize personnel exposure. Results of internal reviews will I i be reported to appropriate levels of station management and the T ALARA Review Committee. In addition, the Health Physics group T will perfora special reviews or studies requested by corporate committees to assist management in assuring tha t all aspects of ~ the ALARA program are implemented. 121%x112sisL_Enante Goals 5 On maior dose accuaulatinq job functions, total man-res and/or aan-MPC-hours (man-hours X ratio of aeasured airborne concentration to Mariaus Peraissinle Concentra tion), exposure goals 'ay oe established prior to commencement of scheduled work. A general goal will be based on the lowest dose commitment recorded on iobs of similar _ nature. A general goal of equaling or bettering the lowest total worktiae expended on jobs of similar nature may be utilized when airborne concentrations or dose rates are unpredictable or subiect to va ria tions. These general goals may be zodified if work tasks are not identical or estimated if there is no available historical data. Significant 12.5-26

SSES-PSAR deviations above established goals will be investigated by Health Physics and/or the responsible supervisor. Methods to improve performance on future 1obs will be in vestigated and implemented, if appropriate. 12tizJs2 sis 7 Job _Ess-21anning When applicable, tasAs to be performed under the provisions of a Radiation Work Permit will be pre-planned. The responsible supervisor will assure that individuals.aelected to perform the task are f amiliar with the a ppropriate procedures to De employed. Supervision will also assure that, when applicaole, a tool list to include special tools that will reduce exposures is completed and review.ed. When pract ica ble, the responsible supervisor will observe dry-run procedure performance. This training may be observed by a Health Physics representative to make time study records as an aid in estiaation of exposure or worktime goals. Special emphasis will be placed on job pre-planning for work in high radiation areas to maximize the use of temporary snielding and distance and minimize the work time. 1225 sJ z2 mLJL_19Ekstig_a e co m 3 e n a a t i ans An informal mechanism of soliciting worker's recommendations for improvement of iob efficiency will be utilized to eva.luate alternative work setnods. Supervisors will encourage worxers to present alternatives that will reduce work time in radiation areas and airborne concentrations. Responsible supervisors may consult with Health Ph ysics during or following evaluation of a recommended change to assure that individual and group e Aposures will not be ad versely af f ected. Changes in methods or equipment that are anticipated to improve efficiency and reduce exposure will be reviewed, approved and implemented in accordance with station procedures. 12si Jz2t2__Exigrnai_ALABA 12a5sJz2s2t1__292i2gtet_Evaluationg Each RWP issued to permit work or entry in a radiation field will require each worker to wear at least one pocket dosimeter. Time and oxoosure record log sheets will be posted with the Radia tion Work Permit near the general work location. The dosimeter log 12.5-27

SSES-PS AR sheats will be reviewed and running totals will ne updated. The responsiole individual will assure required data is properly recorded and will forward the final dosimeter log sheets and the completed HWP to Health Physics following vors completion. 12sisJz2s2x2__Galsa2Ei3411on of 1sposuggs_ Exposures incurred on RWP tasks will be categorized by type of worke r (s), work group, and job function. To facilitate collation of data, scheduled work functions will be coded and entered on the Radiation Work Perait, when applicable. In addition, plant system codes will be developed for RWP use. Whene ve r acolicable, the eq uipment component number will also be recorded on the RWP. This system will allow an exposure history data base to be collected by equipment, system, and work function, and tnus perait supervisors and Health Physics personnel access to definitive records when planning 93P tasks. 1225sjz2s2sl__Isrh_Ilag_avaluatiga Recording entry and exit times will allow total man nours spent on particular tasks to be tabulated. Under favorable conditions, a comparison of exposure rate multiplied by man hours expended and seasured dosimeter individual or group totals may be made to assure proper data. entry and verify that no significant exposure i s rate changes occurred. The man hours expended will also be used as a data base to assist supervisory staff in planning worx of p similar nature. 12s5 j2222z3__Saggial_Alaras and_Iastraugnts 2 The use of special alaras and instruments will be evaluated. Alarmed timers may be used to warn workers they are approaching the maximum allowable work time. De installed in the general work area to allowRemote radiation monitors may readouts in lower radiation areas. Portable survey instruments say be placed in the work area to allow workers to monitor changes in exposure Radiation rate seters and integrating devices with audible rate. alacas may be used to warn workers of unexpected ore-set radia tion levels or dose accumulation. 12.5-28 )

SS ES-FS A R 12 sis 2s2s2sE__ISRB2E4EI_ghielding During the planning phase of RWP work, supervision will evaluate the use of temporary shielding. Care will be taken to assure that installation and removal of snielding will not cause larger aan-rea total exposures than expected without i ts u se. E vec y reasonable effort will be made to utilize temporary shielding, such as lead blankets, that can be quickly installed on initial entry and easily removed upon erit. 12s5s3s2s2si__12ggig1_Igols and AREiI&tga Every reasonable effort will be expended to assure special or modified tools are available f or specific tasks. Availaole tools that will significantly reduce stay time in radiation areas and mariaize distance from radioactive sources will be included on iob procedure tool lists. Appropriate supervisors will review tasts to identify procedures that may be improved by modifications or replacement of tools and/or apparatus. 12 sis 3s2 sis 1__ No n-R WE_ Wat k Revigw Health Physics personnel will review radiation surveys to identify areas not normally meeting RWP crit eria. These areas will be studied to locate those of the highest occ u pa nc y frequency and/or duration of stay time. Health Physics may make recommendations pertaining to shielding or occupancy limits. These recommendations will be implemented whenever practicaole to assure that the exposures incurred in low dose rate areas are as low as reasonaoly achievable. 32s5s3s2.2sd__Administrailla_11 alls Administrative limits will be implemented by station procedures to maintain personnel exposures ALARA with respect to Federal Limits. Station exposure limits may be exceeded only after approval of the Health Physics Supervisor, or designated alternate. Unapproved exposure exceeding station limits will be investigated by Health Physics to identif y causes and establish methods to pre vent recurrence. 12.5-29 m

SSES-YS A R las5saz211-IntstaAL_hkhEh 12sS Ja2 3.1__Engineggigo controls t Minimizing airborne concentrations by utilizing practicable engineering or physical controls will assure that occupational exposures are as low as reasonably achievable. Airborne concentrations will be minimized by appropriate use of containment techniques, temporary exhaust aechanisms, and re view of air flow pa tterns and velocities. Control and evaluation of airborne radioactivity is described in Subsection 12.5.3.5. 12s5sls2sJs2__ESERiE412EY Protectigg When engineering controls are not practicable, the use of respirat ory protection will be evaluate &. Respiratory protection be utilized to minimize the intake of radioactive material. may The respiratory ocotection fitting and training program is described in Subsection 12.5.3.5. w I '12s5sla2=3 3__EI1_32;&_ Air Surverg When RWP requests ' indicate that work is required in airborne radioactive material concentrations, appropriate air samples will be taken. These samples will normally be of short-tera, high volume nature in order to obtain representative data in the

7 shortest period of time.

Any area that is posted as an Airborne Radioactivity Area will be sampled and analyzed prior to commencement of scheduled work. Whenever practicable, surve yors will utilize respiratory minimize their exposures. protection and/or remote air samplers to When existing airborne radioactive materials are not specifically identified, the MPC (Maximus Permissible Concentration) for unidentified alpha and/or beta-camma ma terials will be used for scheduling, criteria for respiratory protection, and calculations of anticipated MPC-hours of exposure. 12s5s)s211sS__19tGhah hir Sanoling When applicable, air samples will ne taken with portable breathing zone (BZ) air samplers equipped with appropriate filter media during work in actual or potential airborn: radioactivity 12.5-30 m

SSES-FS AR areas. The data from analyses of taese air samples will be used to assist in future iob planning and demonstrate that exposures to airborne material are as low as reasonably achievable. When nortable BZ samplers are not practicable, temporary air samplers located close to the breathing zone of workers may be utilized. 12z5tlzlslx1 Ro_uging_Ait_1g apling Continuous air monitors will be placed in representative areas to samole those locations where airborne concentrations may be generated. These samplers will be periodically checked to verify oroper function and assure that unexpected airborne concentrations are detected at the ea rliest possible time. The air sampling program is descrioed in Subsection 12.5.3.5. 12z 5 s 3 si slzi__G2E1121.2 f _lhE o r p t io n and Inggstigg When worn is scheduled on equipment or systems that contained or may contain radioactive liquids, every reasonaole effort to orevent skin contact with radioactive solutions will be expended. Items such as plastic suits, tubber gloves and/or gauntlets, high rubber boots, face shields and hoods ma/ be utilized as appropriate to the task to be completed. Incestion of radioactive aaterials will be minimized oy assuring that adequate protective equipment is properly worn, removed, stored, laandered and surveyed. These ph ysical controls in con 1 unction with administrative regairements and training in the areas of self-survey, prohibition of eating and smoking in contamina ted areas and, decontamination techniques will assure that potential ingestion of radioactive material is minimized. 12s5s3s2s3s2__G2 HIE 91_9$_AEea_and_gguipaggt_Cggadginaligg_Levglg Contaminated areas and equipment will be decontaminated to as low a level, as practicaole. Special emphasis will ce placed on items that may be inadvertently touched by personnel and areas sufficiently contamina ted so as to pose the potential for an airborne concentration. Supervisory staff will be responsible for assuring that work areas are maintained in a neat and orderly manner. The housekeepino practices employed will f acilitate clean-up and decontamination efforts and thus atnimize personnel stay trae in radiation / contamination areas. 12.5-31

SSES-FSAR 12s5s}s2s3 Q__Aigbggag_33222SI2 31112ali2B Exoosures to airborne radioactive material will be tabulated to aid in work planning and demonstrate the effectiveness of the internal ALARA program. Air sample results in terms of a fraction or aultiple of the maximum permissible concentration (MPC) for iden tified or u nidentified isotopes multiplied by the work times will permit s running taoulation of individual and group MPC-hour exposures. When respiratory protection is employed, appropriate reductions of intake will be based on . recommended protection factors. Subsection 12.5.3.5 describes the respiratory protection program. 32s5s322xls2__Adaiaii1Eative Liziad To minimize potential intake of radioactive material in excess of Federal limits, station limits will be estaolished. Airborne axposure or in take in excess of these limits may require work restriction, use of respiratory protection, or special in-vivo or bioassay studies. 1325s 4s).._ggdigtiga_Surzgyg The -Health Physics program will utilize a comprehensive system of C-radiation surveys to document plant radiological conditions and 7 identify sources of radiation tna t contribute to occupational radiation exposure. The radiation survey prog ra m '! to evaluation by dealth Physics supervision to assure thatwill be subject ^ necessary data is collected while exposures to sur'reyors are as low as reasonably achievable. 32s5slzlzl__B&diali2a_2MElev ProgIns Cgn&ggig 13ss. as3 slsl__3.esagd_ggrisy A moaDer of Health Physics supervision will review radiation survey records to assure that adequate readings are taken and pro pe rly recorded. If a need for additional data is noted, supervision will assure that such readings or supplemental surveys are taken and recorded. In addition, supervision will review data to assure that unwarranted readings that contribute to time spent in radiation areas are not taken. If a ppropria te, 12.5-32

S S ES-FS A R h Physics supervision will assure tnat proper corrective .es are taken. 1225 s jtj sjz2__Indggggdags_gev iew s To assure proper performance of job duties by surveyors, a member of Health Physics supervision will perform independent reviews which may include physical measurement of radiation levels in areas previously surveyed. Review data vill be compa red with survey records and posting of warning signs. Tne reviewer may accompany surveyors to observe and verif y proper survey techniques. Deviations from approved Health Paysics procedures or discrepancies in radiation measurements will be investigated and results reported to the Health Physics Supervisor or designated alternate. Appropriate corrective seasures will be taken to prevent recurrence. 12a522sJsizl__33EIRIGE_22ae Evalug& ion Every reasonable effort will be expended to assure that occupational radiation exposure to surveyors is maintained as low as reasonably achievable consistent with providing sufficient surve y data required f or ainimizing total plant exposures. Surveyors' radiation exposure will ne tabulated in accordance with the AL ARA progras described in Subsection 12.5.3.2.. Health Physics personnel will be issued appropriate doaimetry to be worn during radiation survey worx. Beginning and ending dosimeter readings will be recorded. Individual exposures incurred during the survey say be reviewed and compared with previous surveyor exposures. This dosimeter data vill be updated to reflect group aan-res exposures incurred during radiation survey work. Analyses of exposures incurred during survey work will allow investigation and implementation of methods to control and minimize radiation exposure of surveyor personnel. 13s5 s 3 sJ sisg __ Sarzsyqc_ggst_astagian Every reasonable effort wi31 be made to assure that surveyor exposare is evenly distributed by work assignment sched uling and rotation of Health Physics personnel. This rotation will allow comparison of surveyor performance, minimize individual exposures, and assure maintenance o f f amiliarity with all areas of the plant. 12.5-33

SSES-PSAR Ja25 J2js123__IEgining Training of -radiation workers will aid in the reduction of aan-hours expended in radiation tields. All station personnel requiring Level II Health Physics training as described in Subsection 12.5.3.7 will receive training in the types of - radiation and methods of detection, self-survey and radiation -rate survey. This training will include high radiation area techniques, data evaluation and special instrument survey o pe r a tion. Retraining of station personnel requiring Level II Health Physics training will include the areas of radiation survey techniques and procedures. Health Physics' personnel will receive formal and on-the-loo training in survey techniques prior to fuel load at S usqueha nna SES. Special emphasis will be directed efficient high-radiation toward assuring that Health Physics personnel. area survey techniques are exercised by Impromptu training sessions will be held as needed to assure state-of-t he-art understanding or improved performance in areas where reviews have indica ted the need for additional training. Training sessions will emphasize the importance of collecting necessary data while exercising the factors of time, distance and . shielding to miniaize occupational exposures. 12sialal Z__BasiAli2a EMEI1Y_ProgEat a na _12 5 ) J 221__JE23ES8921_321221Aga 2 1 . ~~ Health Physics. procedures will describe the' instrument type (s) to be utilized during. radiation survey work. The surveyor will be a required to en ter -instrument descrip tio n (s ) and identification n unne r (s) on survey forms. P rior to_. performing 30 radia tion the surveyor will check the' calibration Status of the

survey, s

portaole instrumen t(s) selected for use to assare aot more than l three months ha ve elapse ~d since the last calibration. The instrument selected will be checked for battery streng th, if fapplicable, and, in a reproduciole geometry, at least on e' sca le 's c response to.known check source (s) will be verified'. Znstruments overdue for calibration will not be used f or radiation'surve y Personnel will be instructed to report instrdment atio n wort. '604 susoected to be malfunctioning. A properly checked replacement or equivalent survey instrument will be utilized'., / 12.5-34 s i )~ 3w y

SS ES-PS A R 12x 5 s ] sj s212_ _3931i ge _ Ha d ia t i o n A ge g_ S u r v gys Each area on site found to produce a radiation dose rate such that an individual could receive 5 area in any one hour or 100 arem in any five consecutive days sill be conspienously posted as a Radiation Area in accordance dith 10CFR20.203. Every reasonable effort will be made to minimize inadvertent entries in such areas. The " Caution Radiation Area" signs posted at tne boundaries vill be updated to reflect the date of the latest s urve y. Whenever practicable, the signs will also reflect the ceneral and maximum radiation levels within the area and any special conditions req uir ed for entry. Routine surlays of radiation areas will normally be ta ken to assure that each area is surveyed once per week. Areas subject to variations in radiation levels or increased time of occupancy may be surveyed e on a more frequent basis, as appropriate. When reactor conditions are operationally stable, survey frequency in radiation areas may be reduced to spot checks at the boundaries to minialze Health physics personnel exposures. 3225 s 3sjz2s1__High_ggdiation A reg _S a rveys 1 E E Each area on site found to produce a radiation dose rate equal to or greater than 100 ares /hr. will be posted as a High Ra dia tion = Area and access will be controlled in accordance vita Subsection g 12.5.3.1. Routine surveys within such areas will not normally be a perf ormed with conventional porta ble survey inst ruments. Every [ reasonable effort will be made to utilize readings from the Area g Radiation Monitoring (ARM) System to identify cnanges of radia tion le vels. Analyses of maximum and general radiation levels within high radiation areas vill normally be performed dith remote probe survey instruments, long reach survey 5 instruments, retrievable TLD's or dosimeters. ihen practicable, [ fin d ing s from these surveys will be correlated to the appropriate ARM readings and reactor operating conditions. Co r rela tion i rea tings and/or perimeter readings sill be taken to assare each high radiation area is surveyed once per week. In addition, radiation surveys will be taken at the entrances to high radia. tion areas on a f requency dependent upon occupancy in the vicinity and variation in radiation levels. Sig ns will be -[ updated to retiect the latest readings. If surveys at entrances or AR1 readings show significant change, additional surveys may g De perf ormed to update the readings within the area. In order to p minimize occupational exposure of surveyors, high radiation area y survey. frequency may be reduced when operating conditions are g sta D i e. F 9 5 12.5-35 k r Ea

SSES-PS AR 12,.5 Jz2t2d_ Non-Egdigtigg_AI21_12EISIS Areas in and around the Controlled Zone not considered potential radiation areas will be selectively surveyed to establish that every reasonable effort has been made to keep seasurable radiation levels as low as reasonanly achievable. instrument Portable surveys will be performed so as to assure a representative number of non-radiation areas are surveyed once per month. Areas subiect be surveyed on a more frequent basis as appropriate.to significant change or va Any area, previously noted, that is found to be a radiation area will not be promptly posted with a " Caution Radiation Area" sign and reported to Health Physics supervision. If the radiation dose rate cannot be eliminated, every reasonable effort will be made to minimize the dose rate and inadvertent entry. The area will be placed on the radiation area survey routine. Areas within Susquehanna SES security fence not covered by portable instrument survey procraas will be selectively monitored by area TLD's to document integrated exposures. Area TLD's will nocaally be changed and evaluated on a monthly basis. L 12s5s322s225__HAdiali9R_ Work Peggia_jggygyg RWP surveyors will wear self-reading dosimeters. will enter the exposure incurred on the RWP requestThe surveyor this exposure category to assure is included in the BWP iob f unction as well as the systen and/or equipment exposure totals, A seaber of Health Physics supervision will screen incoming t requests to assure inclusion of special measurements or RWP considerations. impromptu training performedS pecial instructions may be developed or collected in the ainlaus of time.to assure tha t necessary da ta is 12a52223tlz5__JRREial_EAdia t ion lugzeyg Special radiation surveys will be performed as requested by operating gronos, regulatory agencias, or corporate coaaittees. These survey supervision to assure the need for the surveyrequests will be coordinated b justifies occupational exposure of surveyors. A meaner of Health Physics supervision ma y draf t special instructions for performance of the survey and/or perfora Emphasis will be placed on assuringimpromptu training sessions with surveyors. that necessary data is 1 12.5-3o ) l - ~ ~ ~

SSES-FSAR collected in the minimum of time. Individual and man-rea exposure incurred during special surveys will ne logged by job f unction, equipment and/or system, 12s5.2z2x2.7 Unit 2_Geastructioa_Eatzsys During the start-up/ operation phase of Unit 1 and the construction phase of Unit 2, routinely occupied areas in the proximity of Unit 1 will be surveyed on a weekly basis with portable instrumentation. Any area found to contain a dose rate such that if an individual were continuously present he would receive a dose in excess of 100 area in any seven consecutive days due to the operation of Unit 1 will be reported to Health Physics supervision. Special shielding, narricading or access control say be employed to eliminate or minimize the potential for personnel exposure. If such areas are identified, portable instrument survey frequency may be increased depending on potential for occupancy and degree of access control exercised. In addition to portable inst rumen t surveys a program of area TLD aonitors will be used to supplement and verif y instrument findings. These TLD8 s will be placed in representa tive loca tions of. routinely occupied arcas near Unit 1 and will normally be changed on a w eekly basis. An investigation will be performed if, af tef natural background subtraction, administrative limits have been exceeded. Bealth Physics supervision will assure that areas monitored are representative of construction activities in progress. 1225xlz12123 Radiatigg_lurvey RESEE $E Radiation surveys perf ormed at Susquehanna SES will be documented in accordance with approved station procedures. A member of Health Physics supervision will review the record (s) completed by surveyors to assure proper data entry. The reviewer will initial and date the record and forward it for permanent filing. 1 12sS Jsg__G2ataliBati93_ Survey Pggcgd3 Egg _ t A system of contamination evaluation will be utilized to miniaire the spread of radioactive material. Evaluation of personnel, equipment and surf ace contamination will also be made to demonstrate the efficiency of engineering and procedural controls. In addition, the contamination survey programs will be 12.5-37 l

SSES-PSAR evaluated to assure that surveyor exposures are as low as reasonably achievable. 12252]s!.1 _Eersonnel_ggntamination_SggvgIg Evaluation of exposures due to personnel contamination will be conducted in accordance with subsection 12.5.3.6. 1225 ]andal__PriskeE_ Survey 2 G-M personnel friskers will be placed in strategic loca tions within the controlled zone. Every effort will be made to locate these instruments in as low a radiation background area as possible in order to maximize sensitivity. Personnel will be trained in the use of the instrumen t (s) and interpretation of the readings. In the event of frisker malfunction, personnel will be required to notif y Health Physics. Audible or visible alarar-will be pre-set at a suitable point above backqcound to minimize spurious alaras and maximize sensitivity. Limits will be conspicuously posted for instrume' ts without automatic alaras. n Personnel rontamination causing f risker alarm will require notification of Health Ph ysics. Health Physics will take appropriate actions to minimize f urther spread of contamination, and direct appropriate decontamination of affected areas and personnel. When personnel contamination is noted, a Health Physics investigation appropriate to the incident will be performed. A contamination incident found to have caused an intake of radioactive saterial will be promptly reported to appropriate supe r vision. When applicable, recossended methods to prevent recurrence will be forwarded to the Superintendent of Plant for concurrence and implementation by his directive. 1245mliailz2_ Nasal gggb Nasal swabbinq procedures will be implemented as requested b y Health Physics or when contamination exceeding station limits is detected on f acial areas to qualitatively determine if inhalation of radioactive material occurred. Health Physics personnel will evaluate the swab as soon as practicable. Findings in excess of

12. 5-38

5 4 SSES-FSAR station limits will require massi clearance, s hower and scrub-down, a whole body count and/or bioassay, and a documented investigation and evaluation. 12.5.3.4 3 Incestion Procedures If contamination is detected in or on the south, a shower and scrubdown and a whole body count will be performed. Fecal and/or urine collection may be initiated to more accurately determine ingested amounts. All cases o f ingestion will be in vestigated evaluated, documented and reported to appropria te supervision and the Superintendent of Plant, and appropriate corrective measures will be taken. 12.5.3.4.1.4 voand, cut. Abrasion Surveys To control inadvertent entry of radioactive material in wounds, cuts or abrasions, individuals will be responsible f er bringing such matters to the attention of supervisors and/or Health Physics prior to work commencemen t. Supervisory personnel will assure that reported skin breaks are brought to the attention of the Health Physics group during job planning or RWP re q ue s t. Health Physics will be responsible for assuring that skin breaks are properly protected prior to work commencement. Open wounds that cannot be. adequately sealed will be sufficient grounds to restrict the worker from contamination work. j Any injury that may have caused contamination of a wound will require the worker to immediately exit the work area and report the incident to Health Physics and appropriate supervision. The wound will be flushed and surveyed with portable instrumentation. If contamination is detected in the wound, the Shift Su pe rviso r may initiate the Susquehanna SES Energency Plan in accordance with written Energency Plan Implementing Procedures. If injury is sufficient to prevent the worker from moving or exiting the area, the Shift Supervisor will be insediately notified and the Energency Plan will be initiated, if appropriate. Approp riat e whole body counts and/or bioassays will be taken f ollowing any needed medical treatment. 4 REV. 1 8/78

12. 5-39

~ - -m .s--~< em

SSES-FSAR 12s5shh2 _EauiRR18t_ Con tamination Surweig i 12x523.4.2.1 Contamination Zone Eagipment SurigIg 4 Movement of equipment from a contamination zone will require notification of Health Ph ysics personnel. Fixed and renovable contamination levels will be evaluated as appropriate and a clearance for removal vill be issued in accordance with station procedures. Routinely used tools may be permanently marked to indicate they are contaminated and will normally be stored inside well marked contamination areas. Repair or use outside contamination zones will require Health Physics approval. Permanently marked tools will be surveyed by Health Physics personnel as necessary and at the request of the appropriate supervisor. Contaminated items that cannot practicably be decontaminated will be covered with plastic or other material and appropriately posted. 12a5s M z2t2 _ESIa25Al Iten Surverg Change-out procedures will require that individuals leaving a contamination zone perform surveys of personal items that ma y have become contaminated during work. Items such as dosimeters, TLD or badge holders, pens and pencils, will be scanned with a G-M frisker. Contamination noted on such items will be reported to - Health Physics personnel. Additional surveys will be performed and the items decontaminated or discarded as radioactive vaste as appropriate. JL5s M.2.3 ProtectiIg Clothinq 23I7922 Beusable protective clothing and shoe covers used in contamination zones will be collected in recepticles at step-off areas and sent f or laundering / decontamination. If clothing is ~ cleaned at Station laundry facilities it will be removed from containers, sorted in an exhausted area of the laundry and scanned with a G-M detector to locate highly contaminated items that aar require separate decontamination or disposal. Following washing and dryin;, clothing vill be re-surveyed to assure that items are within station limits. Records of the range of survey results before and after laundering will be maintained. Every reasonable effort will be expended to assure tnat clothing ts maintained at as low a contamination level as practicable. 12.5-40 o

SSES-FSAR Protective clothing that is shipped off site for laundering will be prepared for shipment and labeled in accordance with applicable U.S. Department of Transportation (USDOT) regulations. Items returned from vendors will be spot checked with survey instruments to assure that residual contamination levels are less than applicable station limits. be maintained for each shipment. Records of survey results will 122222 4.2.4 R esDira to ry Prot ection Device Surveys Respiratory protect' 7e masks will be checked f or contamination prior to cleaning aLd disinfection. Following decontamination and cleaning, masks will be checked for removable and fixed contamination levels prior to disinf ection, storage and/or reissue. Survey results will be recorded. Exterior surfaces of other protective devices, air hoods and suits, self contained breathing appa ra tus andsuch as supplied hoses, will be checked for contamination levels following job completion. Items other than face pieces that reused in contamination zones may be bagged and labeledwill routinely be reflect the latest survey findings. to 12.5.3.4.2.5 Fixed Equipment surveys Routinely accessible plant equipment tha t may become inadvertently contaminated will be spot checked to assure items are less than appropriate station limits. Fixed equipment of this category found to exceed removable contamination limits will be wiped down and resurveyed. If decontamination efforts are not successf ul or if the iten is prone to recurrent 4 co n t amina tion it will be posted as " Con taminated". An equipment contamina tion l list will be tabulated to assure items in this category are resurveyed. If an item is found not to be a recurrent . contamination problem it will be removed from the survey list. A representative number of smears will be taken on items such as door knobs and stair railings, to assure that other controls exercised are-minimizing the spread of contamination. i REV. 1 8/78

12. 5-41

SSES-FSAR 12.5.3.4.2.6 Surveys Involving Receipt / Shipment of Radioactive Hat erial The security staff will be instructed to notify the Health Physics Supervisor or designated alternate upon arrival of shipments in excess of " Type &" quantities at the site. Shipping containers will be monitored for radiation and/or contamination in accordance with 10CFR20.205. Whenever practicable, the container will be monitored prior to removal from the vehicle. If removable contamination or radiation levels are found to exceed the limits of 10CFR20.205, the Superintendent of Plant or designated alternate vill notify the final delivering carrier and the Nuclear Regulatory Commission (NBC) Inspection and Enforcement Regional Office. When applicable, Health Physics Supervision will assure that, prior to leaving the site, exclusive use transport vehicle surf ace contamination and radiation levels are within limits specified in 49CFR173. Station procedures will specif y special procedures and precautions to be taken when opening packages containing licensed material, including instructions pertaining to specific types of shipments normally received at Susquehanna SES. Radi'oactive material will be shipped in accordance with USDOT and M RC regulations. Station procedures will implement the ) applicable regulations with regard to proper packaging and labeling requirements. Appropriate renovable contamination and d ose rate surveys will be taken, records completed, and shipments labeled accordingly. Rr7. 1 8/78 12.5-42 )

SSES-FSAR 12 isJma=1__sgrface Gentamination_sgrysys 12aS 3s3sJsl__E9A1I21124 Access Arges s A smear survey program will be developed and implemented to assure that a representative number of routinely accessible surface areas within the controlled zone are checked for { removable contamination. Special emphasis will be placed on i survey of the clean side of estanlished contamination zone step-off areas. Smears will be analyzed on appropria te counting equipment and records of results will be maintained in disintegrations per minute (d pa) pe r 100 sq.ca. If results indicate removable contamination exceeds station limits, the area vill be posted as a contamination zone. The area vill be decontaminated and resurveyed as soon as practicable. Area signs and barriers will be removed when surveys indicate that renovanle ' contamination is below station limits. In representative areas where gamma background permits, surveys will be performed with portable detectors to establish the level of fixed contamination on normally occupied controlled zone surfaces. A fixed contamination survey will be performed prior to any sanding, chipping, welding, grinding and saving, of . potentially contaminated controlled Zone surf aces. 12.5slanzlz2_ Non-qqgagolled Zone AEtas ~ x Occupied plant areas outside the controlled zone will be surveyed 4 to assure that a representative number of floor surfaces are checked f or removable con tamination. The exit a rea s f rom th e controlled zone will receive special emphasis to ainimize the scread of contamination. Smear survey, analyses and record keeping techniques will be as described above. Non-controlled zone areas found tus have renovable contamination levels exceeding station lialts will ne decontaminated and resurveyed. 12.5 3sHzJs3__spagial_ Area survers 2 Lunch room facilities and vending machine areas frequented by controlled zone workers will be checked for removable contamination. Stoves, benches, taale tops, and floor surfaces will be representatively smeared to assure minimal contamina tion in ' eating areas. Remo vable contamination in excess of non-controlled zone limits will be reported to Health Physics or t

12. 5-43

SSES-FSAR Shif t Supervision and the area vill be restricted from further use until decontaminated. Special emphasis will be placed on eating or cooking surfaces to assure that these items are as far below non-controlled zone limits as reasonably achievanie. Other specific areas will be checked for removanle contamina tion to demonstrate the eff ectiveness of the contamination controls exercised within controlled zone areas. These areas include: (1) Entrances to the control room and the Control Structure. (2) The Guard House at the site perimeter. (3) General floor areas of sho wer and locker room facilities. Floor surfaces in areas that offer a repeated potential for contamination may be maintained as contamination zones to assure positive contamination control. In addition to the routine check outside step-off areas, a general survey of contamina tion le vels inside the areas will be performed whenever practicable. Dose rates within the areas, f requency of occupancy, past survey results, and actual need for such surveyn will be evaluated by Health Physics supervision when selecting established contsaination zones to be surveyed. When area dose rates permit, every reasonable effort will be expended to minimize ~ contamination levels. / 12.523xazata__laaltasalation, aevieym.aod_ata9I11as_ Eras 11ssa Contamination limits, general survey locations and survey frequencies will be specified in station Health Physics Procedures. Procedures will be subject to review by Health Physics Supervision to assure contamination st.rvey implementation is responsive to plant status. A seaber of Health Physics supervision will review records of contamination survey results to assure proper completion and adequate survey. In the event of contamination in excess of station limits, a member of Health Physics Supervision will be responsible for assuring that corrective seasures are implemented and that further reports through appropriate channels are initiated if required. 12.5-44 i ( i i i

SSES-FSAR 12.5.3.5 Airborne Radioactive Material Every reasonable effort will be expended to assure that material released as airborne concentrations within the plant is minimized. A sampling and analysis program will be utilized to determine airborne concentrations in representative numbers of routinely occupied areas. These routine seasurements as well as special surveys, respiratory protection procedures and administrative procedures will be implemented to minimize airborne contamination and the potential intake of radioactive m ate rial. 12.5.3.5.1 Phlgical Controls 12.5.3.5.1.1__ Air Flow Patterns A survey program for determining air flow pa tterns within the controlled zone will be implemented prior to Unit 1 fuel load. Af ter Unit 1 fuel load these surveys will be periodically performed to demonstrate that air flow patterns are toward areas of higher actual, or expected, airborne concentrations. Affected areas will be re-surveyed following ventilation modifications to assure proper air movemen t. Appropriate measures will be tak en if flow patterns are found to be unacceptable. 12.5.3.5.1.2 Contamination Confinement Contaminated items will be properly confined to prevent inadvertent airborne contamination. Such items will be sealed in appropriate material or stored in ventilated areas whenever practicable. When necessary, alternatives such as temporary tents or enclosures, storage in rocas or areas where air movement is away from occupied areas, or wetting of_the iten may be utilized to minimize airborne concentrations. C;ntaminated trash will be sealed in, plastic prior to disposal wherever practicable. Every reasonable effort will be made to assure tha t contamina ted trash recepticals are closed when not in use. 4 REY. 1 8/78

12. 5-45

W SSES-FSAR 12.5.3.5.1.3 Air Exhaust Exhaust of areas or items where airborne concentra tions may be generated will be employed whenever practicable. Contaminated laundry sorting areas, trash compactors, f ume hoods, and sampling stations are typical locations where air exhaust will be utilized. Exhaust flow rates or face velocities on such l equipment will be verified periodically and after ventilation modifications to assure proper function. Items that ma y contain highly contaminated materials such as trash compactors or high level fume hoods will be equipped with a visual indicator or alara to warn individuals upon loss of exhaust flow. Portable exhaust f ans will be directly discharged to building exhaust whenever practicable. When discharge to building exhaust is not practicable the portable exhaust fan will be filtered to minimize airborne concentrations. 12.5.3.5.1.4 Postino and Lockinq Accessible areas containing airborne concentrations exceeding the limits specified in 10CFR20.203 vill be posted with a " Caution - ~ Airborne ~ Radioactivity Area sign. Whenever practicable, access a points to such areas will be locked or barricaded to reduce the risk of inadvertent entry. 1215. 3. 5. 2 _ &d ainistr ative controls w 12.5.3.5.2.1 Health Physics Review All posted airborne radioactivity areas will be reviewed by a member Health Physics supervision on a quarterly basis. 5e th od s to reduce existing airborne concentrations will be forwarded through appropriate channels for review, approval, and implementation. During the review, Health Physics Supervision will assure that every reasonable effort has been expended to reduce the risk of inadvertent entry in airborne radioactivity areas. 1225.3.5.2.2 Health Physics InveStication When an occurrence produces unusually high airborne concentrations in occupied areas, Health Physics Supervision will assure tha t an investigation appropriate to the incident is REV. 1 8/78

12. 5-46

SSES-FSAR completed. The first priori ty wil'l be evaluation and follow-up of personnel intake of radioactive material if applicable. The i second portion of investigation will emphasize determination of the events leading to the release. Recommendations to prevent recurrence will be forwarded through appropriate channels for implementation. 1245x3x522.3 RWP PrqqgdHIRE Radiation Work Permit procedures, as described in Subsection 12.5.3.2, will be a primary administrative control of exposure to airoorne radioactive material. Health Physics review prior to approval will assure that every reasonable effort is expended to minimize the production of, or reduce existing, airbo rne concentrations before work commencement. 1225.2.51J__ Air saanliaa Eauionent A description of the use, calibration methods and frequencies of specific air sampling equipment utilized at Susquehanna SES is contained in Subsection 12.5.2. 12x5s3 5,.a .Airb9sns_Gensaa1Ia119a_su211as 12s5s2siz!.z1__32 stint _su.nlins Routine sampling in selected areas of potential airborne concentrations will be accomplished.with continuous air monitors (CA3) or portable air monitors. CAM sa mpling media and detec tor will be selected as appropriate to the intended use of the device. CAM's will be routinely checked for proper operation. Abnormal readings or equipment aalf unction will be reported through appropriate channels for investigation and/or repair. Alaras, if applicable, will be checked for operability during source checx and calibration procedures. Fixed filter devices will be changed on a frequency specified by Health Physics procedures to assure optimum sampling time, meaningful results, and proper equipment o pe ration. 12.5-47

SSES-FS A R 122523s524 2__Sascigl_Aig_jasoling s Records will be maintained to reflect the reason for the special surveys, device (s) and sampling media used and final results. The maiority of special air samples will be taken as result of Radiation Work Permit requests and pertinent results will be recorded thereon. 1225 sail 25 ain_samale_3raination 12a 5 s3s5xlal__EAI119H 14t e I n i t ia l_g v a l u ali2a A data sheet will be completed to reflect sample location, date, starting flow rate, starting time, sampler and collection media used, and collectics efficiency. At completion of sampling, the date, time, and ending flow rate will be recorded. Air sample filters will be counted as soon as practicable following collection. Results will be recorded on an analysis form to reflect counter used, efficiency, counting time, background count rate, cross sample count rate, net sample count rate, and sample disintegrations per ainute beta, and/or beta gamaa, and/or alpha. Sample disintegrations per minute divided by collection efficiency of the media, the number of disintegrations per minute a per microcurie and the total volume of air sampled will yield the initial estima te of airborne concen tration. Prior to Unit 1 fuel load an air sa mpling program will be implemented to obtain a base line of information concerning naturally occurring radioactive concentrations. This data will enable development of an average beta to alpha ratio of naturally occurring airborne esitters. This "First Count Factor" may be utilized as an initiaJ evaluation technique f or lov level - particulate air samples. 1245 alz 525t2_ S u b 3221tal_EAI112MA. A12_3I312 A11933 Every effort will be made to initially evaluate air samples as soon as practicable following collection. In instances wher e time delay before analysis in conjunction with suspected short lived isotopes is significant, repeated counts may be performed to obtain a decay curve. Extrapolation and subtraction techniques may be used to determine initial amounts and half lives of com ponent isotopes. I 12.5-48 4 w-

SSES-FS A R Wnen statistically possi ble, fixed filter samples may be gamma scanned vita a NaI or Ge (Li) detector to identif y gamma emit ting isot opes. dhen this or other specific analyses are not oracticaole, tne MPC for unidentified beta-gamma emitters will be used f or exposure evaluation and procedural controls. Other evalua tions that may be utillied are beta aosorption counting, radiochemical separations and analysis, and liquid scintillation counting. 1225 s325xixl__9Aseggg_3v a lu a tigns Airoorne radioiodine samples vill normally be collected on charcoal canister or cartridges, and analyzed on a NaI or Ge (Li) detector. Appropriate st andard sources in re producible geometries sill oe used to obtain e f ficiency curves for analysis equipment. Photopeak areas, counting efficiency and bra nching ratios f or the identified isotope will be utilized to calrulate the amount of-deposit. Collection efficiency and total volume of samoled air will be incorporated to calculate airborne ConcentCations. Airborne tritium samples will normally be collected in water bubolors or dessicant columns. Collection and counting eff tciencies and total air volume vill be verified and used to calculate airborne concentrations. If analyses of restricted area air for noble gases are required, sample chambers may be analyzed witn NaI or de (Li) de tec tors to identify isotopes. 12 tit 3zizk__E132iE11REI_EE21ecti2n The respiratory protection program will assure that personnel intake of radioactive saterial is minimized. The respiratory protection program will not be used in place of practicable engineerinq controls and prudent radiation safety practices. Every reasonable effort will be expended to prevent potential, and minimize existing, dirborne concen trations. When controis are not practicable, or conditions unpredictacle, respiratory protective devices may oe utilized to minimize potential intake of airborne radioactive material. The Susquenanna SES Respiratory Protection Program will ensure that the following miniaua criteria are met: written standard operating procedures; proper selection of equipment, based on the 12.5-43

SS ES-FS A R hazard; proper training and instruction of users; proper fitting, use, cleaning, storage, inspection, quality assurance, and saintenance of equipment; appropria te surveillance of worn area conditions, consideration of the degree of employee exposure to stress; regula r inspection and evalua tiou to determine tne continued program effectiveness; program responsibility vested in one qualified individual and an adequate medical surveillance program for respirator users. 12x5sliisszl__Itaining_and Pitting The trainlug and fitt ing program is described in Subsection 12.5.3.7. 12sisJziz5s2__3Ii112B_EE292dures the Respira cry Protection Procram and program respon sioilit y will oe isolemented by Health Physics procedures. Applicable Health Phystes Procedures will include as a minimum: de scri ption of equipment; information regatling issuance, maintenance, selection, use, and return of equipment; and training techniques. Inf ormation regarding air sampling and bioassay programs will be referenced. x / 12sisJshsszl__E21SGli2a_2f_Iquipagat r 2 The need for respiratory protection will be determined by Health Physics personnel af ter evaluation of aporopriate engineering controls. Airborne concentrations will be determined o y air sampling methods described in this section. fue hazard dill be evaluated and applicaule respiratory protection prescrioed in accordance with the RWP evaluation, review, approval and implementation process.as described in Sunsection 12.5.3.2. 32s5r.)sisssd__Isagg_and_ Msg For normal dock situations, respirators sill ce issued after approval of a Radiation Work Pe rmit. Individuals' I. D. cards or qualification list will be utilized to assure only tne specific models approved for the worker are issued. Af ter issuance, the sorter will be responsible for propor use and storage of the levice. Approved Health Physics procedures for use, storage and 12.5-50

SS CS-?S AR return of respirators will be revieved during qualifica tion training sessions. 12x5slzizaz1__G9Elaainaligg_Surveli Whenever practicable, respirators will be scanned with a G-d detactor during final change-out procedures upon completion of assigned work. Detectacle radiation levels on inside surraces of the device will require notification of Healt a Physics. The inside surf aces will then be monitored for removable contamination and/or a nasal swab will oe taken. Based upon findings and s:Ispected isotopes, further evaluations say be required in accordance with Subsection 12.5.3.6. l 12.5.3.5.6.6 Cleaning, D econt amina tion, Inspection, Maintenance, ___...________21sinfggli2D_and Stoggge Station procedures will soecity cleaning, decontamination, s u rv e y, inspection, maintenance, disinfection and storage requirements. Respirators will notaally be used no more than one day (shif t) prior to return for cleaning survey, inspection, maintenance if needed, and disinfection. In no case will a respirator be issued to another individual prior to cleaning survey, inspection and disinfection. Respiratory face pieces will be washed, dried, surveyed for removable and fixed contamination levels, inspected, disinfected and stored in accordance with approved Health Physics procedures. Inspection of masks will emphasize defects at critical points, proper function of attached fittings and valves, and proper shape of face-piece. Simple maintenance and repair will be performed as necessary. Maintenance and repair of regulators will be perf ormed only by specially trained and qualified individuals. Masks ready for reissue will be stored in plastic or paper bags in caoinets or containers. Every effort will De made to assure proper storage of masks to prevent deformation of face piece parts. 3226s)s5s5s2__Q3al111_E9a11912_ Inspection and testing of new equipment will ne implemented by writton station procedures to detect instances of human error or defective aaterials in the manufacture and assembly of the devices. Procedures will specify the components of each device to be inspected and the acceptance criteria wnen applicaole. 12.5-51

SSES-PS AR Respidatory protection devices will be routinely inspected and testel after cleaning and maintenance. The inspection will be oerformed to detect any damage or defects caused by cleaning or wear. Testing will normally consist of a positive or negative oressure leak detection test or exposure to a challenge atmosphere. Er accordance with station procedures periodic checks of items in storace will be performed to ensure that the facepiece rubber is not taking a set, ruboer parts are not hardening or deteriorating, sorbent canisters ha ve not exceeded tueir shelf life, and crea thing air or oxygen cylinders contain sufficient Dressure. 12s5s)25s5sS__SME2sillancs_9f WoI5_ Area conditigns For vorX conditions in volving resptratory protection, air aamplina surveillance will provide an estimate of the potential inta ka or airborne radioactive materials and resulting exposure of tne individual worser, indica te the continuing ef fectiveness of existing controls, and warn of the deterioration of control equipment or operating procedures. The periods of time respirators are worn continuously and the overall durations of use will be kept to a minimum by procedural controls and work surveillance. Workers will be instructed of provisions to leave areas where respirator use is required f or ) relief in case or equipment malfunction, undue physical or osychological distress, procedural or communication failure, significant deterioration of operational conditions, or any other condition that might require such relief. 12s52Jziza22__IIaluali9n_si praagaa_Iffgesizgnssa Respirator failures, evidence of respirator leakage, and equipment problems encountered will be investigated by Health Physics. Problems will be solicited f rom respira tor use rs d uring activities such as plant sa f ety meetings and training sessions. Proposed changes to prevent recurrence or improve efticiency of tne program will be forwarded tntough appropriate channels f or revie=, approval and isolementation. Respiratory protection will be evaluated oy bioassay results corrolated with air sampling results as descrioed in suosection 12.5.1.6. dvidence of a rise in exposure levels attrioutacle to inhalation will be investigated. 12.5-52 r

SSES-FSAR 12s5.255 6.10 Medical _Surveillangg Prior to participation in the Susquehanna SES Respira tory Protection Program, individuals will be evaluated by competent medical personnel to ensure they are physically and mentally able to wear respirators under anticipated working conditions. Individuals involved in the respiratory protection program will also be re-evaluated as part of their routine company physical with respect respirator use.to physiological and psychological factors affecting Details of the medical surveillance Station Health Physics Procedures. program will be specified in 12sS aziz2__Handlina_2f Radioactive Material s 12sSs3.5s2sl__2nstalsd_5aterial Radioactive material in liquid form will be stored in sealed or vented / exhausted containers whenever practicable. When - containers are opened to atmosphere and generation of airborne concentrations is possible, 4 exhausted areas, or in locations where airthey will be opened in fume hoods, movement is away fros workers' breathing zones. Whenever practicable, liquid radioactive material will be transported in unbreakable containers or in a secondary container to collect material in ' case of breakage. Gr.seous radioactive aatorial will be similarly stored and opened. Transport of gaseous samples will be done in sealed, gas tight containers. Solid articles that are sufficiently contaminated with particulate and/or volatile material so as to pose a potential airborne hazard will be handled and stored as described in Subsection 12.5.3.5.1.2. Protective clothing, r es piratory protection, and special i orecautions will be specified by Health Physics procedures and/or Radiation Work Permit for handliaq unsealed material. l l l l 12.5-53 I ( 1 l i

SSES-FS&R 12.5.3.5.7.2 Sealed Materials Sources will be stored in appropriate shielded containers when not in use. Containers and storage locations will be posted to reflect contents and radiation levels. Sources will be locked inside containers or containers will be locked in a storage loca tion when not in use. When sources produce a whole body or contact radiation dose cate greater than limits established by station procedure, a Radiation Work Permit will be completed and approved prior to use. Remote devices such as forceps, tongs or manipulators will be used whenever practicable or required by Radiation Work Derait. I Licensed sealed sources will be monitored for leakage to assure that storage or use is not causing the spread of contamination or airborne radioactive material. When monitoring of the source capsule is not practicable, removable contamination surve ys will be performed at places on the container or source holder where contamination might be expected to accumula te if the source were lea king. Samples will be analyzed on counting equipment appropriate to the source material and records of results maintained. Frequency, materials to be tested and record keeping requirements of' NRC license or Technical Specifications will be implemented by Station Health Physics Procedures. Sealed sources found to be leaking vill be sealed f rom atmosphere whenever practicable.and/or stored in ventilated areas until disposal or repair. O 12.5.3.6 Personagl Monitorinq 12.5.3.6.1 External Personnel Monitoring Personnel monitoring devices will be used at Susquehanna SES to evaluate external occupational erposure to radiation sources. l Exposure informa tion will be used for work function exposure evaluation, job planning, reporting requirements, incident analysis, and an indication of the effectiveness of AL AR A practices.

12. 5. 3. 6,1,1__Pgrson n e l Dosi m et r y Eva lua t ion 3

Routinely used personnel dosimetry will include self-reading dosimeters, ther moluminescen t do simete rs (TLD), and/or film badges. Individuals requiring personnel dosimetry will be REV. 1 8/78

12. 5-54

.n.-

SSES-FS&R instructed la the purpose.and use of the devic s, station administrative exposure limits, and interpreta tion of self-reading dosimeter readings. Appropriate dosimetry devices will be issued in accordance with station procedures implementing 10CFR20,202, 1 0:.steetry will normally be worn on tae front of the ncay between the ueck and the vaist in a clearly visible location. When appropriate, dosimetry will be issued and worn on the extremities. Dosimetry say be wrapped in plastic to prevent contasiaation of personnel nomitoring devices when entering the contaminated areas. as described in Subsection 12.5.3.2, self-reading a owA.e ter results will be used for specific LLARA job exposure evaluation as well as to indicate current individual exposure status. Dosimeters of appropriate ranges will be available f or use during work in radiation and high radiation areas. Radiation workers will be responsible for checking their dosimeter readings when working in 2HP areas. The frequency of dosimeter checking will depend upon the nature of the job and whole body done will be discussed with the radietion wochers during MiP pre-job ra tes, and planning. Of f-scale or mal"unctioning dosimeters wiJl be reported to Health Physics. Realth Physics personnel will evaluate the occurrence, issue a replacement dosine.er and the suspect dosimeter for response and leakage. te s t Posimeters will be removed from service if the calibra tion response, 24 hour leakage, or changing drift test results excecd acceptance criteria specified in the St.ation Realth Ph ysics proced ures. beir-reading dosimeters will normally be used to ec.aitor ganna exposure only. They may be used to determine neutron dose equivalent in a mixed radiation field provided the neutron dose equ'. valent rate and ganaa exposare rate at the point of personnel exposure are known f rom separately made determinations; the neutron-to gamma ratio is essentially constan t duriug the period of personnel exposure; and the degree of response ot the doaineter to the neutron flux density is known. ne thods of evaluation of dosimeter readings to determine neutron dose equivalent will be specified in Station Health Physics procedures. When neutron dose equivalent is determined from sel f-reading dosimeters, it dose equivalent. will be added to the whole body ganaa TLD devices will normally be used as the dosimetry of record. Personnel TLD (s) will normally be evaluated on a monthly basis or i more frequently as determined by Health Physics Supervision. Th e data obtained from TLD's will be evaluated to determine doso equivalents. Ganaa TLD chip readings indicate the dose equivalent to be attributed to whole body. A pprop;1a te REV. 1 8M8

12. 5-55

53ES-F51R correction and quality factors will be applied to neutron chip readings to determine the neutros dose oquivalent. Neutron and gaans doses will morat117 be added together to yield the whole body dose equivalent. Appropriate correction f actors will be applied to the Beta TLD chip readings to determine the beta dose. The beta dose will normally be added to the skele body dose equi va le nt to determine the skia dose squivalent. When appropciate, the skin of who. e body dose equivalent will be added to the gassa dose equivalent, determined by issued extremity monitoring devices, to detera lne total extremities' dose equivalent. For individuals rho do not utilize extremities devices during a calendar quarter, the skin of whole body dose equi valent will be assigned as extremities ' dose equivalent. If film badges are used as the dosimetry of record, the sarvice will be purchased from an outside vendor and evaluated by the vendor on a monthly basis or as specified by Health Physics Supervision. A program will be implenested to verif y film badge accuracy. Pila badge results will be evaluated and categorized according to whole body, skin of the whole body, and extremity dose equivalent. Fila badges may be used to determine neutron dose equivalent when tha eff ects of image fading, low sensitivity, and masking in high gamma fields sre not critical. Personnel exposures will be accumulated and evaluated against applicable station and federal limits by Health Physics person ne l. 1225.3.6.1.2 idsinistrative Exposure Coutgol l Administrative exposure limits will be established and implemented by Health Physics procedures to assure t he limits of 10CF220.101 are not exceeded and personnel occupational exposures are maintained ALARA. 12,5.3.6.1.3 Metnocs of Recordino and beoortioa

• Designated supervisors will receive reports of their em ployees' accumulated exposures for use in RWP job planning and scheduling.

Updates of exposure totals will be compiled f rom self-reading dosimeter readings. Unapproved exposures exceeding station limits will be reported to the Superintendent of Pla nt and appropria te supervision, and investigated by Health Physics to identif y causes and establish methods to prevent recurrence. REv. 1 s/78

12. 5-Se

j SS ES-FS A R occuoational radiation ex posure received during previous emoloyment will be used in preparation of individuals' Forms NdC-4, or equivalent. Wh en an individual's occu pational exposure history cannot be obtained, tne values specified in 10CFa20.102 (c) (1) will be used. Records used in preparing f orm NRC-4, o r equi valent, will be retained and preserved un 11 ene NRC authorizes disposition. Records of the radiation exposure of all individuals issued oersonnal dosimetry in accordance wit h 10CFR20.202 will be maintained on Fora NRC-5, or equiva lent. Exposures will ce tabulated for periods not ex ceed ing one calendar quarter. A separite record will be completed when it is necessary to enter information - for exposure to the extremities or skin of the whole body. Records of radiat ion exposure received during employment at Susquehanna SES will be maintained indefinitely or until NBC authorizes disposal. aeports of exposure to radiation or radioactive materials will be made to individuals as specified in 10CFR19.13. When reports of individual exposure to radiation or radioactive material are made to the NRC, the in dividu al(s) concerned will also be notified. This notice will be f orwarded to tne individaal(s) at a time no later than the transmittal to tne Commission and will comply with 10CFR19.13. A report of the individual's exposure to radiation or radioactive material incurred while employed or working at Susquehanna 3ES will De f urnished to the NRC in accordance with 10CFR20.408 and to the individual upon termination of employment or nors a94ignaent at Susquehanna SES. + A personnel monitoring in f orma tion report will De suositted, in accordance with 10CFR20.407, w ith in the first quarter of each calendar year. As par t of a routine annual operating report, personnel exposure information sill be submitted within tne first quarter of each calendar year. It will include a tabulation of the number of station, utility, and other personnel (including cont racto rs) receivtna exposures greater than 100 mrom/yr. and j assaciated aan-rea exposure according to wors and 1ob functions. It will also include f or each outage or f orced reduction in power of over 20 oercent of design power level, wnere the teduction exton is f or ureater than four hours, a report of radiation i exposu re associated with the outa ge which accounts for mo:e tnan l 10 percent of the allowable annual values. In the event of an exposure in excess of 10CPH20.101 limits, i Healt a Paysics Super visio n will investigat e t he event and document the description "of the occurrence; conditions under which the exposure occurred; names of personnel involved and 3

12. d-3 7 4

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SSEd-FS AR amount of exposure received; action ta xen a t time of occurrence; I recommendations for corr ective measures and means of implementation to prevent a similar occurrence. In the event of an unauthorized exposure in excess of station administrative limits, !!ealth' Physics Supervision will investigate the event to determine the cause (s). Recommunaa tions for corrective measures will be forwarded for review, approval, dnd iSplcmenta tion in ACCordance with station procedures. Reports of overexposures at Susquehanna SES will be submitted to the NaC and the in dividu a l (s) involved in accordance with 10CFR19.13 and 10CFR20.405. Re po rt s will also De f orwarded to appropriate committees for review and recommenda tion for follow-uo action. llu5sjso s 2_._ In tgggal_ g gdia11gg_Iggggggg_ Agggggg e n t When engineering controls are impracticaolo and airborne concentrations exceed sta tion lia tts, trained individ uals will be equipped'with properly fitted respirators. Internal exposure evaluation will De utilized to. determine the effectiveness of the Respiratory Protection Program and evaluate suspected intake of radioictive material. Th e Respirato ry Protection P rogra m is lescribed in Subsection 12.5.3.6. dhole body counting and/or bioassay techniques will De used to compare the quantity of '\\ ^ radio.ictive aa terial -present in the body to

v. hat quantity which would result f rom inha la tion for 40 hours per week for 13 weeks at uniform airDorne concentrations specified in Appendix B,

Table 1, Column 1, 10CPR20. m-12xisjzis221__aistasar_5einada whole body counting vill be used to qualitatively and a va n tita tive ly identif y radionuclides deposited in the body which =eait' penetrating radiations. Depending upon the physical construction and geometry of the wnol> Dody counter, sensitivit y of the detector (s), and biological factors, concentra tions of radionuclides ~ aay be detected in the. whole body, thyrold, lung, or wounds. The whole body counter will be set up and caliDrated and/or utiltzed in accordance with Subsection 12.5.2. Urine analysis may be conducted to identify the presence or pure alpha or beta emitters in extracellular body fluids. Under favorable circumstances, w it h a full 24-hour sam ple and further

12. 5-5 d

9.: T ES-FS A R analyses, tne a mount of radiot, riides may be qualitatively a nd quantitatively determined. Be.;its may be utilired to substantiate in vivo analyses findings. Pecal analysis will normally be used to evaluate intake of non-transoortaole (i.e. insoluble) saterial and provide evidence of the clearance of such material from the lungs. When it is suspected that a nontransportable radionuclide nas been inh a led, the total aaount excreted in feces during the succeeding few days may be used to estimate t he amount initially deposited in the lunas. Standard lung models recommended by Interna tional Commission on Radiological Protection (ICH P) say nen be used to -evaluate the amount in ha led. Dose cosaitzent for internal deposits may be estimated oy calcu la ting the amount of airoorne radioactive material inhaled, based on airborne radioactive material seasureeents, exposure time s, standard lung models and breathing rates. 12s%s3s6 sis 2__142iAiELEa1112_E2H1E212 Records, approved station procedures, prog ra m reviews, and investigation will assure proper administrative control over the internal personnel monitoring program. Reviews of the internal personnel sonitoring program and investigations of individual cases of saspected or known intakes will be performed and documented by Health Physics Supervision and reported to appropriate committees. 12s % s j s k. 2 s l__ CIltsgig.19I_EAI11g124119n_ gI_22129119B Selection of personnel and frequency of routine whole body counting-and bioassay analyses will be isolemented ' by Health Physics Procedures. The f ollowing is a guideline for participation in special wh ole cody couating and/or oioassay analyses: (1) Personnel evaluated oy means of a nasal swao as having contamination in the nasal passages in excess of 1Amits specified in Health Physics Procedures. (2) Personnel saspected to nave ingested a detectacle level of radioactive material, or absorbed i detectacle level of radioactive material through a sound or creak in the skin. t 12.5-59

n O SSES-FSAR (3) Personnel physically present without res pira tor y protection, or those-experiencing respirator f a11are, in C a Concentration Cesulting in greater than 40 MPC-Hours exoosure in any seven consecutive days may oe counted. An evaluation will be perrormed in accordance with 10CFR20.103 and whole body, lung, or thyroid coanting will be performed if calculations snow potential de posit of greater than the Minimum Detectable Activity (M. D. A. ) of the counter for long lived isotopes. The following is a guideline for selection of personnel for special, non-routine urine analysis: (1) When there is suspicion of an intake of a beta or alpha emitter only. (2) In coniunction with non-routine fecal analyais. In addition to the abo ve criteria, personnel may be required to submit urine samples to evaluate clearance rates of radioactive material identified by s pecial or ro utine wnole body counts, or as directed by Health Physics Supervision. Fecal sampling and analysis will no rmally be done on a non-routine oasis as designated by Health Physics Supervision. Fecal analysis may be done as a follow up on whole body or lung counts. J 1225232622z1__32AlMaki9a_da.4_22a2Ellas j Identifiable deposits will be evaluated against the criteria of 10CFR20.103 assuming conservative conditions and time frames with resoect to the time of intake. Reports will be generated vnen internal deposits indicate greater than 40.1PC-riours exposute in any seven consecutive days. The re ports will De reviewed by appropriate supervision and maintained on filo sub ject to NdC inspection. Reports of o verexposure will be completed and submitted to the NRC when it is determined a quantity greater than specified in 10CFR20.10 3 nas oeen inhaled. Whole bcdy dose commitment resulting from int ernal deposits exceedlac station limits will be calculated a nd included on the ' individual's Fora NRC-5 or equivalent. Specific organ counting may be performed if appropriate. Oc yan content say be assigned using whole body measurements and ICRP-2 recommended fractions and clearance times, vnen organ counting is not possible. Dose commitment to olood forming organs, gonads, 12.5-o0

pi & 9 97 [*4g,// / IMAGE EVAL.UATION k/f77;\\? g?/q+/ %g'g[$;4 / TEST TARGET (MT-3) s 1.0 lf M M '; M HL24 1.1 [" b "' l.25 1.4 1.6 i, 150mm 6"

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SSES-FSAR whole body or eyes resulting from deposits in other organs may be calculated using Medical Internal Radiation Dose Committee (MIR D) equations. Whole body dose coazitaent resulting from internal deposits exceeding station limits will be calculated and included on the individual's Form NBC-5. 12s 5 sla2-_d2Alth_EhIfi gg_J r a i n i n g_EI2g ra m s Health Physics Training Programs will assure that personnel, who have unescorted access to the restricted a rea, possess an adequate understanding of radiation protection to maintain occupational radiation exposures as low as reasonably achievaole. Special training / retraining will be administered upon recommendation of tne Superintenden t of Plant or Health Physics Supervisor. Record keeping and training seneduling will be perf ormed by the Training Su pervisor or designated alternate. 5 12A.sjs2 1 Ptooraa_GE M E211 12s5 322s 1.1 gggggggggs=_R ev iew 2 Management will formally review Health Physics Training Programs once every three (3) years. Consideration will be given to workers' suqqestions and instructors ' comments. Management will evaluate the program's influence on maintaining radiation exposurea as low as reasonably achievable. The revie w will be documented and comments / changes will be recorded and incorporated into the training prog ra m when a pplicable. 1225 322xlz2__Haalth_EhrsisE_IIaining Prggras_agrisw 2 Health Pnysics Training Programs will be reviewed by Health Physics Supervision and pertinent committees to assure implementation of ALARA philosophy. Recommendations for improvements to training programs will be f or warded t hrough appropriate channels f or review, approval, and implementation. 12s5s js22J2]__ Accefg_CgatI21 An access control list will be complied and maintained. The list will specify personnel qualified for unescorted access to the

12. 5-61

SSCS-FSAR Restricted Area by having met the recuirements of Level I Health Physics Training and appropriate plans and procedures. A listing soecifying individuals' retraining dates will be maintained. A copy of the access list will be saintained at the security guard house. During a ppropriate training sessions, individuals whose tob duties do not require entry in radiation, contamination, or RWP areas will be informed of the reasons they are denied access to such areas. 12miz3s2._1.4 Rettaiakag/3eplacesent_ Training To assure individual proficiency in Radiation Protection practices, retesting will be performed on a yearly basis. Retraining vill be performed every two (2) years or as reconsended by the Superintendent of Plant. Scheduling, records, and test results will be maintained by' the Training Supervisor or ~ designated alternate. Individuals changing iob classifi-ca tion will receive training of the level required by their new-job classification. Training /retra ining will be administered, under the direction of the Training Supervisor o r designated alternate, to candidates for Nuclear Regulatory Commission (NRC) operating licentes and those holding NBC licenses. The Training Supervisor or designated alternate may request the Health Physics Supervisor to provide instruction on selected Health Physics topics. 12sS az2z2__IEaining_Et99taas t 1225taz2x221__Lszel_I_Itaiains All persons allowed unescorted access to the restricted area will, as a ainimua, receive Level I Health Physics training. To be qualified in Level I Health Physics an individual will demonstrate proficiency in the following areas as evidenced by passing 4 written examina tion: Requirements of 10CFR 19.12 Radiation / Contamination (examples and control) ALARA (Corporate comnitments, meaning and individuni re spo n sibilit y) 12.5-62

9 o SSES-FSAR Personnel Monitoring and Self-Survey Requirements Radiological Control Sions and Posting Requirements Radiation Exposure Control and Limits Radiation Emergency Plan and Applicable Procedures Prendral Radiation Exposure 1215tJzalzL_LedII Trainino 7 Level II dealth Physics Training will normally be administered to individuals who have successf ully completed Level I and require access to Radiation Work Permit Areas. The need for such training will be evaluated and scheduled by the Training Supervisor, or designated alternate. Level II training will be administered to provide radiation workers with an adequate knowledge to effectively cope with job situa tions while maintaining radiation exposures as low as reasonably achievable. The individual will demonstrate proficiency in the following areas as evidenced by passing a written examination: ALARA (applicable procedures) Contamination Control and Self-Survey Requirements Pundamentals of Radioactivity Radiation Dose Units and Biological Ef fects Radiation and Bich Radiation Area Survey Techniques Principles of Radiation Safety (Time, Distance and Shielding) Radiation Work Permits (RWP) Use of protective clothing / devices 122islz2z2sL_ LevgLIILTnin inq Level III training will emphasize special applications of AL ARA practices and will normally be directed at supervisors of radiation workers. ALARA training in the planning of radia tion work permit iobs will include man-ran reviewing techniques, sethods for reducinq personnel exposures, and other areas 12.5-63

a ~ SSES-FS A R recosaended by the ALARA devied Comaittee and Health Physics supervision. In addition, effective methods of improving work w efficiency, such as sock-up situa tions, dry-runs, and amintenance orie nted photographs f or job planning will ne discussed. 12.5sas222.1-Leve1 lY_Iths Level I7 train ing will emphasize ALARA and dealth Physics aspects of the RWP review process discussed in Subsection 12.5.3.2. The training vill be directed at qualifying seabers of Shift Supervision for. RWP revie w and approval autnority in the ausence of Health Pnysics Supervision. .12s5sls2s2sk__EREEiEA12IY Protecti2a_IIainiag_Pgggggg Individuals and their su pervisors requiring access to areas where respiratory protection will be utilized will complete tne Respiratory Protection Training Program. The instructor will be a qualified individual with a thorough knowledge and considerable experience regarding the application and use of respiratory orotective equipment and the hazards associated with radioactive airborne contaminants. x Training will include lectures, demonstrations, discussions of certinent station procedures, and actual wearing of respirators to become familiar with the various devices utilized at Susquehanna SES. The program will include as a ainiaua: discussion of the airborne contaminants against which the wearer is to be protected,- including their physical properties, MPC's, ohysiological action, toxicity, and means of detection; discussion of the construction, operating principles, and limitations of the respirator and the reasons tne respirator is the proper type for the particula r purpose; discussion of the reasons for using the respirators and an explanation of why more positive control is not insediately feasible, including recognition that every reasonable ef fort is ceing made to reduce or oliainate the need for respirators; instruction in proced ures for ensuring that the respirator is in proper working condition; instruction in fitting the respirator properly and checxing adequacy of fit; instruction in t he proper use and maintenance of the respirator; discussion of the application of va rious cartridges and canisters available for air-purifying respirators; instruction in energency action to De taken in the event of salfunction of the respiratory orotective devices; review of radiation and contamination hazards, including the use of other protective eauipment that may be used with respirators; classroom 12.5-64

f SSES-PSAR and field training to recognize and cope vita emergency situations; and other special training as needed for special use. Individuals will be required to don the device (s) that may be used, perform appropriate pressure tests for leak detection, and be exposed ta a challenge atmosphere. If a quan titative test device is available, it will be utilized to quantitatively seasure and record leakage. If leasage exceeds the devices rated protection factor and retests confira this, the individual will not be a pproved to use the device. If quantitative testing is n ot practicaole or unavailable, qualitative tests such as irritant smoke or isoaayl acetate aay be used as a challenge ataosohere. Detection of odor will be considered a fitting failure. After successful completion of training and fitting programs, appropriate records will be saintained to assure individuals are issued only the approved type and model of protective device (s). These records will reflect expiration dates. Individuals will receive retraining and reconfirmation of respirator fit on an annual basis. Related records will be maintained or the Training Supervisor or designated alternate. 12 d a hhhi__linhh_ ElutliSE_32ah2 E_laili ALIEliala2_E E2S E42 & Health Physics Training Program will be administered to applicants for the position of Health Physics Monitor under the direction of the Health Physics Supervisor or designated alternate. The content of instruction will depend upon the experience and qualifications of the applicant 'with course content outlined in approved station procedures. Applicants with Health Physics experience may be waived froa participation in part or all of the initial monitor training program. All acolicants aust demonstrate their proficiency by successf ull y conoleting the Monitor Qualification Examination. The initial training program will cover a period of approximately one (1) year for the applicant lacking Health Physics experience. The f ormal training may include ins truction by outside consultants, and participation at operating reactor f acilities in addition to on the iob training, in-house instruction and examinations. The following is an outline of the Initial Monitor Training Program: Introduction to Health Physics, (General topics: Mathematical computations, Basic Atomic and Nuclear Physics, Radiation and Radioactive Decay, Isotope production and disposal, Reactor Fundamentals). 12.5-65

\\ ~ SSES-FS A R Health Physics Course (General topics: Radiation and Contamination Surveys and Control, Posting Requirements, ALARA Applications, Respiratory Protection, Protective Clothing, Health Physics Procedures, Decontamination of Personnel and Equipment, Air Monitor Operation and Results Inte rpre ta tion, Health Physics Record Keeping, Appropria te Station Plans and Procedures, Applicable Regulations and Limits, Radiological Emergency Monitoring P rog ra m, Radia tion Work Permits (RWP), Health Phys tes Job Coverage, Personnel ' Monitoring) BWR dealth Physics (General Topics: BdR Systems, BWR Outage / Refueling, BWR Operational Health Pnysics) Review and Monitor Qualifying Examination Health Physics Supervision will review the applicant's proficiency as displayed dering the training programs, erazinations and the monitor qualifica tion eraaination. The successf ul candidate will be assign ed the responsibilities of Health Physics Monitor. 12s5.s]z221sl__Heglih_Ehraigs Moni12g_Hetggigigg EE2SEAa All Health Physics Monitors will receive a retraining revie. on an annual Dasis. Tae purpose of the review will be to strengthen the monitor's qnderstanding of Health Physics a pplica tions a nd state of the art Health Physics tecnnology. Review will consist of formal and/or informal training sessions that will include topics similar to those described in the Healta Physics course above. One method of evaluating tne monitor's competence in several areas say be the presentation of a hypothetical vorK situation problem requiring demonstration of Health Ph ysics knowledge in a logical progression. Areas not covered by the probles solving process will be evaluated by means of written and/or oral examinations. Records of training sessions and examinations will be-forwarded to the Training Supervisor. An evaluation will be performed to identif y areas where supplementary retraining 24y be necessary. Inforsal sessions will be held with the monitor by a member of Healta Physics Supervision to discuss areas of individual concern and additional retraining needs. dealth Physics Monitors will be suolect to all or any portion of the retraining process when deemed necessary by the Health Physics Supervisor or designated alternate based on job merformance. Monitors may also request additional traiaing in 12.5-66

SSES-FSAR areas of individual interest. A member of Health Physics Supervision will evaluate such requests and, if appropriate, administer special.'. zed informal training to suit individ ual need s. In this case, the sonitor's oerforaance will not be subiect to formal, documented evalua tion. i 12.5-67

i Superintendent of Plant Health Physics Supervisor Health Physics Engineer 1 Health Physics (2) Specialists 5 Health Physics (8) Monitors Note: Numbers in parenthesis are the conbined Unit 1 and Unit 2 staffing. REV. 1 8/78 SUSQUEHANNA STEAM ELECTRIC STATION i UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT HEALTH PHYSICS ORGANIZATION FIGURE 12.5-1

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