Text

Forwards Annotated Rev to FSAR Chapter 12, Radiation Protection, Reflecting Personnel Organization,Corrections, Clarifications & Editorial Changes.Rev Will Be Incorporated Into Future FSAR Amend
	ML20214V073
Person / Time
Site:	South Texas
Issue date:	06/04/1987
From:	Wisenburg M; HOUSTON LIGHTING & POWER CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	ST-HL-AE-2219, NUDOCS 8706110439
	Download: ML20214V073 (74)
	v • d • e

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n, The Light SOE f Ifouston 1.ighting & Power P.O. Ik)x 1700 IIouston. 'lixas 77001 (713) 228-9211 June 4, 1987 ST-HL-AE-2219 File No.: G09.02 10CFR50 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Annotated Revisions to FSAR Chapter 12 " Radiation Protection" Enclosed are annotated revisions to FSAR Chapter 12 concerning Radiation Protection at the South Texas Project Electric Generating Station (STPEGS).

These revisions reflect changes in plant personnel organization, as well as corrections, clarifications, and editorial changes. These revisions will be incorporated into a future FSAR aaiendment and are provided for the staff's immediate use. These changes do not affect the conclusions of the STPEGS Safety Evaluation Report.

If you should have any questions on this matter, please contact Mr.

M. A. McBurnett at (512) 972-8530.

l M. R. Wis nburg Manager, Engineerin and Licensing PLW/ljm

Attachment:

Annotated Revisions to FSAR Chapter 12, " Radiation Protection"

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i L3/NRC/ek k 8706110439 870604 PDR ADOCK 05000498 A PDR

r-Houston Lighting & Power Company ST-HL-AE-2219 File No.: G09.02 Page 2 cc:

Regional Administrator, Region IV M.B. Lee /J.E. Malaski Nuclear Regulatory Commission City of Austin 611 Ryan Plaza Drive, Suite 1000 P.O. Box 1088 Arlington, TX 76011 Austin, TX 78767-8814 N. Prasad Kadambi, Project Manager A. von Rosenberg/M.T. Hardt U.S. Nuclear Regulatory Commission City Public Service Board 7920 Norfolk Avenue P.O. Box 1771 Bethesda, MD 20814 San Antonio, TX 78296 Robert L. Perch, Project Manager Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 1717 H Street Bethesda, MD 20814 Washington, DC 20555 Dan R. Carpenter Senior Resident Inspector / Operations c/o U.S. Nuclear Regulatory Commission P.O. Box 910 Bay City, TX 77414 Claude E. Johnson Senior Resident Inspector / Construction c/o U.S. Nuclear Regulatory Commission P.O. Box 910 Bay City, TX 77414 M.D. Schwarz, Jr. , Esquire Baker & Botts One Shell Plaza Houston, TX 77002 J.R. Newman, Esquire Newman & Holtzinger, P.C.

1615 L Street, N.W.

Washington, DC 20036 T.V. Shockley/R.L. Range Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 Revised 2/3/87 L3/NRC/ek

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12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE (A1 ARA) 12.1.1 Policy Considerations Administrative programs and procedures, in conjunction with facility design, ensure that the occupational. radiation exposure to personnel will be kept as 37 low as is reasonably achievable (A1 ARA). The applicable Regulatory Guide (RG) used.to develop the administrative programs and procedures are referenced in 53 Table'3.12-1.

12.1.1.1 Management Commitment. Houston Lighting &_ Power Company is committed _to maintaining occupational radiation exposures ALARA. In keeping 37 with such a commitment, HIAP will develop a health physics program and provide an environment in which the health physics staff can properly perform its duties.

Policies and commitments are part of written procedures and are reflected in station design features. Instructions to designers, constructors, vendors, and station personnel specifying or reviewing station features, systems, or equipment reflect HL&P's ALARA goals and objectives.

38 Responsibility for ensuring that an effective ALARA program is implemented and I Physics is assigned to the Health xd S:f:ty-S:rci::: Division under the direction of 37lSf

?hys;cs the Health :nd S fety *:rri :: Manager. The responsibilities of the Health

-" S2fet- Serfice: Manager include:

phyiics

1. Aid in establishing a corporate AIARA program that integrates management philosophy and regulatory requirements.

2. Assure that an effective measurement program is established to evaluate l the degree of success achieved by station operations with regard to AIARA goals and objectives.

3. Review measurement results on a periodic basis and take corrective actions when necessary.

4. Provide available resources needed to achieve AIARA goals and objectives.

Responsibilities of the Plant Manager with respect to AIARA include:

1. Ensuring support _from all plant personnel.

2. Participating in the selection of specific goals and objectives of the plant.

Thysic s

3. Supporting the plant Health 24 Safety S:reiree Manager in implementing the plant AIARA program.

PAvsjes The Health and Safety Serfice Manager is independent of station divisions, such as operations, maintenance or technical support and reports directly to 37

?I'Y 8.5 p Manager. The Health and Saf:ty#Serfice Manager-has delegated responsibility for implementation of the plant ALARA program to the

,k"*M ,_._ H lth end S fety Supervisor. Responsibilities of the H: lth 2-d S:fety i TRed,*aiejica L b7EcflW *g g l g ; her(crIM 12.1-1 Amendment 56

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^ Supervisor with respect to the plant ALARA program include: __

l. Identifying locations, operations, and conditions that ha7E" potential for exposure. ,

2. Administering a radiation exposure control program.

3. Participating in training programs related to radiation protection.

4. Supervising the radiation surveillance program.

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5. Supervising the radiation protection staff.

pkge bMobpcod The Health :nd __,s ty Scrri :: Division supports the ::: lth :nd ._fsty Protection Supervisor in his efforts to maintain plant radiation exposures -

ALARA through the S lth r ' S:f ty Support Staff. This support' staff has responsibilities for: ggg

1. Developing plans, procedures, and methods for keeping radiation exposure AIARA.

2. Reviewing and recommending changes to job procedures to maintain exposures ALARA.

. 12.1.1.2 Design and Construction Policies. The ALARA philosophy was applied during the initial design of the plant and implemented _through internal design reviews and documentation. In addition, the design will_be l37 reviewed for ALARA considerations by HL&P personnel. These reviews are-also documented consistent with the recommendations of Regulatory Guide (RG) 8.8.

The plant design will be reviewed, updated, and modified as necessary during the design and construction phases. The plant design will integrate the layout, 37 shielding, ventilation, and monitoring designs with traffic control,-security, access control, and health physics aspects to ensure that the overall design produces a plant which will enable the lowest practicable exposures to be achieved.

[ Piping containing radioactive fluids will be adequately shielded or routed to minimize exposure to personnel. 37 To comply with the ALARA policy, inspection and testing of plant shielding will be conducted during startup to verify that the shielding performs its function of reducing radiation to design levels. During initial power opera-tions, radiation surveys will be conducted to ensure that there are no defects in the shielding that might seriously affect personnel exposures during normal operation and maintenance of the plant.

12.1.1.3 Operation Policies. The STPEGS-health physics program,-estab-lished in plant Radiation Protection procedures,- is the major means of promulgating the operational ALARA_ policy._ This policy is disseminated by 37 training programs, maintenance and operating procedures.

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y It is the responsibility of the ": lth{c$d cal S:f:ty Protection Supervisor and the radiation protection technicians to assure that company employees and contrac-tors are adequately informed of radiation protection practices to comply with 10CFR19, 10CFR20, and the recommendations of RCs 8.10 and 8.13; it is also their responsibility to assure that exposures are maintained AIARA. To ensure M*N. compliance with this policy, the "::lth "'d S:fety Protection Supervisor and the radiation protection technicians are charged with the responsibility of

'MysiC5 - promptly notifying the Health _.._ ....., .. . Manager of any unsafe practices which exceed their authority to correct. They have been delegated the authority to halt any operation which in their judgement is a personnel radiation hazard.

Prior to fuel load, plant personnel will receive training in radiation protec- 37 tion. These personnel also will be tested to verify that they understand how g;gienLLYradiation protection relates to the safe performance of their jobs. Contrac-tors who work in the# restricted area of one of the units after initial fuel loading of that unit will receive instruction in the principles of health physics commensurate with the safe performance of their jobs.

The written maintenance and operating procedures to be used at the plant will be reviewed for radiation protection aspects to verify that the procedures adhere to the AIARA policy. System and plant modifications will be reviewed to verify that the AIARA concept is applied.

In addition to reviews by management, all employees will be encouraged to submit suggestions relating to radiation protection.

12.1.2 Design Considerations South Texas Project design considerations which ensure that occupational radiation exposure will be AIARA are based on the guidance provided by RG 8.8, Revision 1, and the collective experience of the NSSS vendor engineers and designers. This personnel experience resulted from participation in the 37 design and operation of several nuclear power plants. In addition to design 4

requirements specified by the NSSS vendor design, guidance in the form of NRC regulations, RGs, and industry standards is distributed to each design 9331-discipline. Furthermore, each designer has access to radiation protection 9 specialists for discussions and guidance on specific design problems asso-ciated with the reduction of radiation exposure and radioactive releases.

Published accounts of operating experience and results of tests and studies performed by the NSSS vendor are continually reviewed and studied to determine l37 design features which could be incorporated into STP to prevent recurrence of problems. Project procedures ensure that engineering documents, such as [37 drawings, system design descriptions, and specifications that define the components, layout, or operation of systems containing or controlling radioac-tivity, are reviewed to ensure that occupational radiation exposures are AIARA. These reviews are performed and documented to ensure that the design 37 l53 guidance provided by the NSSS vendor and that design features' discussed in RG 8.8, Revision 1, are followed as far as practicable. l37 The studies of man-rem doses associated with normal plant operation and antic-ipated operational occurrences described in Section 12.4-provide a design aid to ensure that occupational radiation exposure will be AIARA. Additional design considerations that have been factored into STP for this purpose are 4 discussed in Section 12.3.

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12.1.2.1 : Facility. The Reactor Containment Building .(RCB), Fuel-Handling Building, (FHB) and Mechanical Auxiliary Building (MAB) are designed to ensure I '

that during routine operations, personnel are shielded from significant ra/dI- {37 ation sources. Every effort is made to route radioactive piping within rafdio-ractive pipe chasas. Where possible, multiple radiation sources are indi-vidually shielded to allow for the maintenance' of one componen't while an adja-cent component remains in operation, without excessive radiation exposure to personnel. Adequate space for ease of maintenance and other operations is provided which permits the tasks to be completed more quickly, thereby reducing the length of exposures. Platforms are provided, where practical, to-avoid the need for temporary staging in radiation areas. Personnel barriers are provided for access control to high-radiation areas. The plant filters and demineralizers are located in individual, shielded compartments clustered in one general area to minimize exposure to personnel during normal operation.

The layout is designed for safe and efficient radioactive filter cartridge l 37 removal and delivery to the waste solidification facility. The layout of the RCB allows safe access for personnel into shielded areas during power oper-ation, and into other areas after shutdown.

12.1.2.2 Equipment. Materials used to fabricate components of the reac-tor coolant system (RCS) and steam generator (SG) tubes have been selected by the NSSS vendor. Specifications for these materials, and other reactor compo-nents, restrict the amount of cobalt contained in the base metal. This restrie- 4 tion serves to reduce the amount of cobalt-60 formed as a corrosion product. 331.

In addition, the materials are selected to minimize corrosion and maintenance requirements.

The SG tubes have been bright-annealed. This process involves annealing of the Inconel tubes while both the inside and outside surf aces are exposed to a hydrogen atmosphere. This reduces the corrosion tendency and minimizes the crud retention properties of the tubes.

The equipment associated with systems containing radiation sources is designed l37 to reduce the need for maintenance and other operations in radiation fields.

Pumps are chosen that have very high quality shaf t seals or, in some cases. l37 canned pumps are being used that eliminate the possibility of leakage. Where possible, instrumentation, pumps, and valves are isolated from high-radiation 137 fields. In accordance with the NSSS vendor's design recommendations, corrosion- 4 and maintenance-free and long-wearing materials are specified for systems B7 Q331.

handling radioactive fluids. 9 Personnel- radiation exposure will be greatly reduced by the provision of remote operation capability and by reducing the time required for work in radiation fields. Many components that are potentially radioactive and require periodic disassembly have attachments designed to disconnect and reconnect quickly.

This consideration is applied to the equipment involved in refueling opera- l 37 tions, inservice inspection, and air and liquid filter replacement, and to the makeup of canned pumps. Remote valve operation is provided in radioactive systems, allowing the operator to remain in a safe area during valve manipula-tion. Similarly, remote inspection techniques are considered for components l 37 that contain radioactive crud or which have induced radioactivity. In either case, the operator performs the actual inspection while isolated from the high-radiation fields.

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, , STP FSAR When maintenance or replacement of radioactive equipment is required, the sys- lg I tems are designed, when possible, so that they may be isolated, drained, and flushed to reduce the contained residual activity. Efficient removal of con-tained crud is enhanced by designing the equipment to minimize the number of crud traps. Systems and techniques are established to reduce the radioactiv- l37 ity in the reactor coolant prior to refueling in order to reduce the airborne releases and radioactive contamination of the refueling cavity water. Reduc-tion of radiation exposure to personnel from airborne contamination is accom-plished by using high-quality seals and by providing continuous evacuation of the air in compartments (i.e., minimum of 2 air changes per hour) where leak-age of radioactive fluids could occur. In addition the flow pattern for these 37 areas is arranged to ensure the flow is from an area of low activity to one of high activity.

12.1.3 Operational Considerations In accordance with Hi4P policy, 10CFR20, and RGs 8.8 and 8.10, the radiation exposure of plant personnel will be kept AIARA by means of the health physics program discussed in Section 12.5. The radiation protection policies and practices contained therein are promulgated through the training program Rade.rs ed discussed in Section 13.2 through the STP Mcc1th 2M S2fety Protection 37 Procedures discussed in Section 12.5, and through operating and maintenance procedures.

Procedures for radiation exposure-related operations (such as maintenance, inservice inspections, radwaste handling, and refueling) that routinely occur at an operating pressurized water reactor (PWR) will be written and approved 137 I

f r both units prior to their initial fuel loadi Radiation-related

' Physics procedures will be reviewed by Health cnd Scfet) g.

_crricec to ascertain that AIARA concepts have been included.

Division personnel l3 57 For unusual or first-time operations that will involve significant radiation gg;eg exposure, procedures are normally prepared by or with the assistance of the group doing the work and then reviewed by the Health cnd Scfet)# S creic : Divi-sion. The Plant Manager has final responsibility at the plant to see that the 57 AIARA concept has been taken into consideration.

Based upon the experience gained during operation, information learned from 37 other utilities and periodic reviews procedures will be reviewed and revised.

Some of the common dose reduction techniques that will be used when working with systems that contain, collect, store, or transport radioactive gases, i liquids, or solids are discussed in Section 12.5.3. Approved procedures will l4 incorporate these techniques where applicable. In general, these techniques are normally followed unless it is decided that thetotaldosereceivedmaybel37 increased or that the dose reduction may be negligible compared to the effort involved to implement the specific technique. Additional criteria and/or conditions under which techniques are implemented are listed under the discus-sion of the particular techniques or type of job.

4 12.1-5 Amendment 57

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ATTACHMENT STP FSAR ST HL AE. 42 /9 PAGE 4 0F 7f utilizing closure studs modified with breech-block lugs (Roto-Lok) for

/ attachment to the vessel. The system also includes a single-lift upper package which combines missile shield removal, control rod drive mech-anism cooling duct removal, and upper core support structure removal.

The Fuel Handling System is descrited more fully in Section 9.1.4.

8. The radiation protection design features of the STP Gaseous Waste Management Systems are described in Section 11.3.

9. The Solid Radwaste System is designed to perform the solidification and drumming of liquids and spent resin by remote control. The Solid Waste 39 Processing System (SWPS) may also transmit the spent resin to high integrity containers for dewatering and shipment to the burial site.

This feature, described more fully in Section 11.4, ensures that radiation exposures to personnel will be minimized.

10. Process sampling lines leading to the primary and radioactive waste sampling panel are routed through radioactive pipe chases, and local shielding is provided to protect personnel at the sample panel. More detailed information on the Process Sampling System is presented in Section 9.3.2.

11. The Mechanical Auxiliary Building (MAB) is designed with a centrally l39 located radioactive pipe chase occupying a large part of the El. 29-ft level. The systems in the MAB are thus able to transfer radioactive l39 fluids from one shielded cubicle to any other shielded cubicle through pipes that are shielded along the entire route.

12. The Reactor Coolant Pump (RCP) Oil Changing System reduces operator l39 exposure while changing RCP motor oil by eliminating the need for moving oil drums into the Containment and by reducing the time an operator is stationed at each RCP. This is accomplished through feed and drain lines connected to locations outside the Containment and by providing suitable controls for the draining and filling operations.

13. Byproduct material (Ref. 12.3.1-1) in the form of gamma calibration sources is packaged in shielded calibration devices as described in Section 12.5. Special nuclear material (Ref.12.3.1-2) consists of new reactor fuel, which requires no special handling or shielding, cnd Fu-Ec *stAf neutrer eclibrctier ccurecc, which are located in shielded calibration devices as described in Section 12.5. Source material (Ref.12.3.1-3) 3 will be kept onsite in the future for use as calibration sources.

12.3.1.3 Reduction of Radiation Sources (Where Operations Must Be Performed).

1. The production of activation products in the Reactor Coolant System (RCS) is minimized through the use of corrosion-resistant ~ materials (stainless steel, zirconium, and inconel) and by controlling the oxygen and pH in the reactor coolant. Oxygen is controlled during startup and during power operation by the use of hydrazine and dissolved hydrogen, respectively. Control of pH is accomplished with additions of lithium hydroxide to the reactor coolant. Compatibility of the reactor coolant with materials wh!ch are in contact with the coolant is discussed more fully in Section 5.2.3.

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'2. The: distribution 4of activation products;isLreduced.by many methods, a few-of which are described below.

, an. During normal operation, the' Chemical and Volume Control System

-(CVCS) . (see'Section 9.3.4) continuously purifies the reactor coolant letdown stream,by the filtering . demineralizing..and purging of-ra .

diogases. In this way, the activity of the-reactor coolant is con-trollkd, as.is the activity of any leakage. Since essentially all leakage ~is collected and processed by the waste-handling systems (see Chapter 11), which are operated and maintained by plant person-nel, reduction of reactor coolant' activity contributes to minimizing occupational radiation exposures.

b. The spread of activation products, and the resulting occupational ~

radiation exposures during refueling operations, are reduced by decontamination of the reactor coolant. This is discussed in Section 12.3.1.3(4).

c._ The spread of-contamination is also reduced by.providing shielded cubicles with a threshold coaming to contain small spills within'_the

-cubicle, by painting' surfaces-for easeLof decontamination, and by routing of drains to sumps for disposal (see Section 9.3.3). In addition, the tank cubicles described in Section 12.3.1.2(2) are-designed to contain radioactive material in the unlikely event of a component rupture. Each component also has been provided with'an adequate drainage system.

d. The:STP Heating, Ventilating, and Air. Conditioning (HVAC)' Systems are designed to maintain negative pressure in shielded cubicles relative to the surrounding clean areas.in order to' provide air flow-from the clean area to the potentially contaminated area.. The air flowrate was selected to ensure that radioactive concentrations are ALARA and do not exceed the limits indicated in 10CFR20, Appendix B, Table I, Column 1. These exhaust air streams are diluted with air -l39 from the rest of the buildings before being. released to the environ-ment. The primary and radioactive waste grab samples are taken -)

under a chemical fume hood which is connected tolthe Sampling Room HVAC Exhaust System. A constant air velocity is maintained through !

the working face of the sampling station to ensure that airborne contamination will not spread to the room. . Normally. the' exhaust air streams from the sampling room and the radiochemical laboratory ~

are mixed and then diluted with exhaust air from=the rest of the building before being released to the environment. _ .The exhaust air" l39 streams from the two rooms are directed through the sampling room supplementary filters and the radiochemical laboratory supplementary Each of the supplementary filter trains consists of a filters.

prefilter, a high-efficiency particulate air (HEPA) filter, carbon filters, and another HEPA filter. In this~way, radioactive par-ticulates and radiciodine airborne nuclides are removed from the exhaust air spreams before release to the environment. A more,com-plete descrip,/ tion of the Auxiliary and Radwaste Area Ventilation System may b /found in Section 9.4.3.

12.3-4 Amendment 39

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PLANT RADIATION SHIELDING ZONES FOR NORMAL OPERATION AND ANTICIPATED OPERATIONAL OCCURRENCES Max. Dose Rate Zon'e Number (mrem /hr) 11 sting Required Anticipated Access 4 100 Yes, post with " Caution - Restricted and controlled.

Radiation Area" signs. Limited accegs. I hr/wk is permissible.

39 5 100 Yes, post with " Caution - Restricted and control High Radiation Area" signs. Normallyinaccessible.jed.

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2 The column'" Posting Required" refers exclusively'to whether posting with the signs " Caution - Radiation (or High Radiation) Area" is required, not the posting of actual radiation levels. Actual radiation levels are routinely posted at selected portions of Zones ~3, 4, and 5. ' l39 pypnov4 L 5 Access only with rge--Iirir- of Radiation Protection Supervisor or designated representative, with duration!

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g based on: ygh g-4

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h a) Radiation intensity level 6$ m

g. b) Nature of the radiation- . . .

g n c) Past radiation exposure history of entering personnel 7t h z N b ~4 Access.is controlled at'each entrance to a High Radiation Area in accordance with the guidelines contained in

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12.4.1 Estbnate of Annual Exposures to STP Station Personnel The annual exposure that could be received by plant personnel during normal operation and anticipated operational occurrences has been estimated to verify that, with the plant operating continuously under normal radiological condi-tions, personnel exposures would not exceed 1.25 rem / calendar quarter and average personnel exposures will be less than 5 rem /yr. Unexpected mainte-nance and emergency operations are excluded from the annual exposure estimate.

However, expected mechanical problems, based on past pressurized water reactor (PWR) experience, have been incorporated into this analysis. To ensure that occupational exposures are as low as is reasonably achievable (ALARA), the design feature guidances given in Regulatory Guide, (RG) 8.8 are followed as described in Sections 12.1 and 12.3. -

For the purposes of the estimate, normal operation and anticipated operational occurrences shall include:

1. Plant operation

2. Routine patrol

3. Radwaste handling

4. Periodic tests and inspections

5. Scheduled maintenance

6. Refueling Results are tabulated for STP station operation. Unless otherwise noted, annual doses reported in the tables must be divided by 2 in order to reflect doses on a per unit basis, e Table 12.4-1 summarizes the estimated annual radiation zone occupancies and man-rem dose totals by personnel categories, e Table 12.4-2 summarizes annual dose estimates for STP administrative personnel, e Table 12.4-3 summarizes annual dose estimates for STP operating 2

persennel.

e Table 12.4-4 summarizes annual dose estimates for STP technical personnel, e Table 12.4-5 summarizes annual dose estimates for maintenance personnel.

PLaur e Table 12.4-6 itemizes annual dose estimates for STP-Auxfli2ry Operators, e'

Table 12.4-7 itemizes annual dose estimates for STP maintenance 1 personnel. [39

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e Table 12.4-8 itemizes annual dose estimates for STP personnel during -

weekly Containment patrols.

PLaur e Table 12.4-9 itemizes annual dose estimates received by ^- dli$ g Operators and instrumentation' and control (I&C) personnel during monthly Residual Heat Removal System (RH)AfS) checks.

PLANT e Table 12.4-10 itemizes annual dose estimates received by ^r *Ni 7 Operators and I&C personnel during monthly Emergency Core Cooling System (ECCS) checks.

e Table 12.4-11 itemizes dose estimates received by refueling personnel (STP mechanical maintenance crew) during each refueling operation, e Table 12.4-12 itemizes dose estimates received by contract personnel.

e Table 12.4-13 summarizes on a per unit basis annual doses received from special maintenance.

e Table 12.4-14 summarizes annual doses received from inservice inspection.

39 e Table 12.4-15 summarizes annual airborne doses to STP administrative personnel.

e Table 12.4-16 summarizes annual airborne doses to STP operating personnel, e Table 12.4-17 summarizes annual airborne doses to STP technical 331.

personnel.

e Table 12.4-18 summarizes annual airborne doses to STP maintenance personnel.

e Table 12.4-19 summarizes annual airborne doses to contract personnel, e Table 12.4-20 summarizes total Unit 2 construction worker doses.

e Table 12.4-21 summarizes annual average Unit 2 construction worker doses.

The estimated annual man-rem dose from direct radiation received during oper- l2 ation of the STP is 793 man-rem per year. The airborne exposures are 31.35 man-rem to the thyroid and 8.3 man-rem to the whole body. The dose estimates per unit from direct radiation are 396 man-rem, and, from airborne sources, 39 15.7 man-rem to the thyroid and 4.1 man-rem to the whole body. The estimated direct radiation man-rem exposure for both units to the 590 personnel assigned results in an average exposure of 1.34 rem per year per person.

1. During operations in a Zone 5 area (2100 mrem /hr), applicable ALARA l39 techniques are used in order to reduce the radiation level. Such techniques include flushing and draining of tanks, pumps, and fluid lines, installation of temporary shielding, use of remote handling equip-ment etc. Credit for these operations is taken in the dose estimates.

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2. Exposure times are based on estimates of the average times required to l39 perform the designated tasks.

3. Radiation protection personnel exposures are based on the information provided below in item 8 and Table 12.4-4. The resulting doses can be 53 found in Table 12.4-4.

4. It is assumed that techniques for inservice inspections described in l39 WCAP-8872, " Design, Inspection, Operation and Maintenance Aspects of the W NSSS to Maintain Occupational Exposures as Low as Reasonably Achievable" (Ref. 12.4-2), are used. Steam generator inspection is assumed to be unde using the Westinghouse remote positioner fixture.

5. Airborne dc.;e estimates are reported for thyroid and total-body expo-sures. These are based on the plant airborne activity concentrations 39 listed in Table 12.2.2-2,

6. Maintenance operations are assumed to be divided between mechanical, I&C, and electrical personnel as follows: mechanical - 40 percent, I&C - 40 percent, electrical - 20 percent. Components are isolated by ay( Pimf

_ = ilicry Operator, and it is assumed that his assistance is required for

^

1.0 man-hour per task.

7. All personnel located in unrestricted (Zone 1) areas are assumed to be l39 subject to approximately the same average dose rate of 0.04 mrem /hr.

8. The following data are used for determining plant personnel assignments. l39 The operating shift crew of STP Unit 1 and Unit 2 is described in Section 13.1.2.3.

39 e Plant Manager (1) gg The Plant Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends *95 percent of his time in the i plant office and control room area and 5 percent of his time in the l plant area, e Plant Superintendent (1) l39 l

The Plant Superintendent is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days

[7 per week, 50 weeks per year. It is assumed that he spends 95 percent of his time in the plant office and control room area and 5 percent of his time in the plant area.

PL AN Y M An A99R e "f;;ter Operations Cup ? int:nd::t (1) 39 PLnur Mnun The " ::*:r Operations Superih : stand: t is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends approximately 75 percent of his time in the plant office and control room area and 25 percent of his time in the plant.

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1 INSERT for p. 12.4-3 o Technical Services Manager (1)

The Technical Services Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 100 percent of his time in the plant office area, o- Integrated Planning'and Scheduling-Manager.(1)

The Integrated Planning and Scheduling Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 90 percent of his time in the plant office area and 10 percent of his time in the plant.

o Plant Computar Manager (1)

The Plant Computer Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed he spends approximately 35

-percent:of his time in the plant. 'He-may frequent any area _of the plant.

The remaining 65 percent of his time is spent in the plant office area.

L3/NRC/ek

ATTACHMENT

. ST HL AE. 3/9

RbQE M OF 7s*

STP FSAR -- --

lluir HtANAgtA 4 &

e Operations S;;:rrir:r (2) - - -

39 -

tLuir maung e g The# 0 perations S ;:? ic:: is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 75 percent of his time in the plant office and control room area and 25 percent of his time in the plant.

e Shift Supervisor M;;1::: (12) 39 The Shift Supervisor M :12:r is a shift worker, and he routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. It is assumed that he spends 50 percent of his time in the plant office and con-trol room area and 50 percent of his time in the plant, e Unit Supervisor Muel ;r (12)

The Unit Supervisor M :12:r is a shift worker, and he routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. It is assumed that he spends 50 percent of his time in the plant office and con- 39 trol room area and 50 percent of his time in the plant.

RtacroA e + Operator Nuci :: (18) nuncron TheMperator N. 1 :: is a shift worker and normally works 40 to 48 APPRoxiMartiY hours per week, 50 weeks per year. He spends *80 percent of his time in the control room or plant office area, and 20 percent of his time in the plant. 39 Pleur e ..^ :ifiery Operator (31)

PLjur RfC The ^. :111 ry Operator (-AO-) is a shif tworker and normally works 40 R PCs g po to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks _per year. Seven ede-are required for each operating shift. Three 44 personnel per unit plus one Ae.+R Po 39 ,

serving as a yard man shall rotate between and patrol the following l areas i

Turbine-Generator Building (TGB) l Mechanical-Electrical Auxiliaries Building (MEAB) '

Fuel-Handling Building (FHB)

Diesel-Generator Building (DGB) 2 Yard area RP,0s' The -AOe responsiblities include participation in RCB patrol, monthly checks of the RHRS and the ECCS, and periodic maintenance tasks (see Tables 12.4-8 through 12.4-11).

e ' Training Manager (3) --

The Training Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per

_. week, 50 weeks per year. It is assumed that he spends 5 percent of 39 his time in the plant office area, 85 percent of his time in the training facility, and 10 percent of his time in the plant. ,

b Amendment 39 12.4-4 t

ATTACHMENT

. ST-HL AE 7.2/9 ,

, , STP FSAR JAAF/5 0F Y .

l e Training Supervisor (5) -

The Training Supervisor is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. .It is, assumed that he spends.5 percent . i of his time in the plant office area, 85 percent'of his time in the

~

39 .

training facility and 10 percent of his time in the plant.

1 e Training Instructor (20) l39 l l

The Training Instructor is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days i per week, 50 weeks per year. It is assumed that he spends 5 percent of his time in the plant office area, 80 percent of his time in the 39 training facility and 15 percent of his time in the plant.

e Reactor b . ff.*f. A Pmoym momme _ . ___ (1)

-~

sg Q.cr=nnce __pervicer is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per The Reactor Pc.ger+ 39 day, 5 days per week, 50 weeks per year. It is assumed that he spends 80 percent of his. time in the plant office and control room area and 20 percent of his time in the, plant.

bbewomc.a.5 e Reactor Engincer (4)9evisoc The ReactorM%Enginccr

% swtso v-is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 70 percent of 39 his time in the plant office and control room area and 30 percent of his time in the plant.

e Management Services Manager (1) 39 The Management Services Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 90 percent of his time in the plant office area and 10 percent of his time in the plant.

e Administrative Supervisor (1)

The Administrative Supervisor is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 100 percent of his time in the plant office area.

e Office Manager (1)

(Same as Administrative Supervisor.)

39 e Administrative Technician (1)

(Same as Administrative Supervisor.) -

e Personnel Assistant (1)

(Same as Administrative Supervisor.)

w 12.4-5 Amendment 39

P ATTACHMENT

. ST HL AE M 4

' * ^

PAGE14 0F 74E STP FSAR o System Administrator (1)

~

f (Same as Document Control Supervisor.)

4 ^

o Emergency Preparedness Coordinator (2)

(Same as Document Control Supervisor.)

39 o Engineering Technician (Administrative) (4)

(Same as Document Control Supervisor.)

o Technicc1 Suppeft Superintendent (1) Pleur EndiuttKING /dd"dS'A J

TheTechnicclS$ppertSuperintendent is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 90 percent of his time in the plant office area and 10 l39 percent of his time in the general plant area.

HE ALr h 'Phy sic s e RadiclogicIl Scrviccc Manager (1)

He Alth Thysics The Radic1ce.cc1 Scrviccc Manager is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per 39 day, 5 days per week, 50 weeks per year. He spends approximately 100 percent of his time in the plant office area.

e Radiation Protection Supervisor (1)

The Radiation Protection Supervisor is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 35 percent of his time in the plant and may frequent any area of the plant. The other 65 percent of his time is spent in the plant office area.

zustar e ALARA Health Physicist.(6)

The ALARA Health Physicist routinely works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. Approximately 60 percent of his time is spent in the plant office area. Approximately 40 percent of his time is spent in direct surveillance of work activities in the health physics office, the calibration room, the FHB, the laundry area, the decontamination room, radwaste processing areas, and general areas within the MEAB and RCB.

e Lead Radiation Protection Technician (12)

The Lead Radiation Protection Technician is a shift worker and normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. He -

spends approximately 85 percent of his time in the lead radiation 39 protection technician office and the other 15 percent performing activities in the calibration room, laundry area, decontamination room, radwaste processing areas, and general areas within the MEAB and RCB.

.l 12.4-8 Amendment 39

r.

ATTACHMENT ST.HL AE 44/9 l

, . PACE /7 0F 75 1 l

I INSERT for p.'12.4-8 o Radiological Support Supervisor (1)

The Radiological Support Supervisor is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed he spends approximately 35 percent of his time in the plant. He may frequent any area of the plant. The remaining 65 percent of his time is spent in the plant office area.

L3/NRC/ek i

r-ATTACFHAENT ST HL AE 4.2/9 STP FSAR

.PAGF W OE 76.'.

- e Senior Radiation Protection Technician (10)'

~

The Senior Radiation Protection Technician is a shift worker and normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per we_ek, 50 weeks per year. He . ..

spends approximately 75 percent of hic time in the radiation protec-tion technicians office and calibration room and the other 25 percent performing surveys, calibrations, and surveillance in 39 various areas of the plant, including the MEAB, the FHB, the radwaste handling area, and the RCB.

e Radiation Protection Technician (6)

The Radiation Protection Technician is a shift worker and normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks-per year. He spends approx-imately 60 percent of his time in the health physics office and cal-ibration room and the other 40 percent performing surveys, cali-bration, and surveillance in various areas of the plant, including the MEAB, the FHB, the radwaste handling area, and the RCB.

e Associate Radiation Protection Technician (6) 39 The Associate Radiation Protection Technician is a shift worker and routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. He spends approximately 70 percent of his time performing various sur-veys throughout the plant. He spends the other 30 percent of his time in the health physics office or labs in the MEAB.

e Junior Radiation Protection Technician (8) 39 The Junior Radiation Protection Technician is a shift worker and routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. He spends approximately 70 percent of his time in local areas of the plant and 30 percent of his time in the health physics office or labs in the MEAB.

e Radiation Protection Aid (4) 39 The Radiation Protection Aid is a shift worker and routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. He spends approximately 70 percent of his time in local areas of the plant and 30 percent of 12 his time in the health physics office or labs in the MEAB, e

t%se.e Systems "erferaanca Cuperciscr (1)

The Systems EEEI9IEnce Cepor,-iser is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 80 percent of his time in the plant office area and control 39 room area and 20 percent of his time in the plant. -

e Systems Engineer (11)

The Systems Engineer normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 70 percent of his time in the plant office area and 30 percent of his time in the plant area.

12.4-9 Amendment 39

ATTACHMENT

. ST.HL AE 42/9

. . STP FSAR PAOC /9 OF Sr _.

e Performance Support Supervisor (1) -

Hansgar (Same as Systems Performance Supervi4or,)

e Test Engineer (4)

The Test Engineer normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 70 percent of his time in the plant office area and 30 percent of his time in the plant, e Fire Protection Engineer (1)

(Same as Test Engineer.) .

e Lead Technician (1)

The Lead Technician normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 60 percent of his time in the plant area and 40 percent of his time in the plant office area.

e Engineering Technician (Technical) (15)

(Same as Lead Technician.)

39 e Technician Trainee (4)

(Same as Lead Technician.)

eben e Chemical Operations and AnalysisH&upe% errintendent- (1)

Mananer The Chemical Operations and Analysis eGupeeIntendent- is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 75 percent of his time in the plant office area and 25 percent of his time in the plant chemistry laboratories and in var-ious areas of the plant, including the TGB, FHB, MAB, and yard.

e Chemical Analysis Supervisor (1)

The Chemical Analysis Supervisor is normally at work 8 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months per day, 5 days per week, 50 weeks per year. He spends +30 percent of his time in the plant chemistry laboratories in the TGB, the MAB, the FHB, and the yard, and may frequent any area of the plant. The other 70 percent of his time is spent on administrative matters, which are performed in the plant office area, o.prueWy I e Chemical Operations Supervisor (1) --

_ The Chemical Operations Supervisor is normally at work 8 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months per day, 5 days per week, 50 weeks per year. He spends +20 percent l of his time in the plant and 80 percent of his time is spent on ad- ,

ministrative matters which are performed in the plant office area. ({j 12.4-10 Amendment 39 L

ATTACHMENT ~

ST HL AE 476 STP FSAR PAGE;70 0F 14r o Associate Chemical Technician / Junior Chemical Technician / Chemical

. Aide (6)

The Associate Chemical Technician / Junior Chemical

~

. Technician / Chemical Aide is a shift worker and routinely works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. Approximately 20 percent of his time is spent inside the Restricted Area and 80 percent of his time is spent in the TGB and other unrestricted areas.

MannGen e Maintenance Superi'Et rdert (1)

M onadeg The Maintenance Superi$t:nd::: normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 90 percent of his time in the plant office area'ahd 10 percent in various areas of the plant, including the MEAB, the TGB, the FHB, the machine shop, and the RCB. 39 Mannsen e Mechanical Maintenance Sr;crficer (1)

MAMA 6eR The Mechanical Maintenance Superviser is a day shift worker and normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. APPRoMAowrty He :reclly spends 530 percent or his time in ene plant ottice area, 10 percent of his time in the machine repair shop, and 10 percent of his time in the MEAB and the RCB, e Mechanical Maintenance Technical Supervisor (4)

Mnunser .

(Same as Mechanical Maintenance Er;:rfierr.)

e Mechanical Foreman (11)

The Mechanical Foreman normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. He spends approximately 50 percent of his time in the plant office area, 45 percent of his time in the MEAB or the TGB, and 5 percent of his time in the RCB and the FHB.

e Journeyman Mechanics (52) 39 The Journeyman Mechanics normally work 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. They spend approximately 80 percent-of their time in the MEAB, the RCB, and the FHB. The remaining 20 percent is spent in the TGB, Machine Shop, intake structures, etc. They are also involved in periodic maintenance jobs and Containment patrol (see Tables.12.4-8 and 12.4-9). Members of the mechanical main-tenance crew are involved in the following operations:

Refueling operations defined in Table 12.4-12 - -

Receiving of new fuel Storage of spent fuel Preparation of steam generators,~NSSS piping, and' reactor for nondestructive testing Leak testing 12.4-12 Amendment 39

ATTACHMENT.

. ST HL AE Em1'

PAGE 4/ OF '/6 STP FSAR -

4 1

e Apprentice Mechanics and Helpers (18) ---

1 The Apprentice Mechanics and Helpers normally work 40 to 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months s-per week, 50 weeks per year. Their. time is spent divided in the -

same percentages as the Journeyman Mechanics'.

e W

Electrical Maintenance Superciccr-(1)

Mape The Electrical Maintenance Supcreicct is a day shift worker and normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year.

.g He nc=c117 spends,80 percent of his time in the plant' office area, 10 percent of his time in the repair shop, and 10 percent of his 39 time in various areas of the plant.

e Electrical Maintenance Technical Supervisor (2)

The Electrical Maintenance Technical Supervisor normally works 8 14 hours per day, 5 days per week, 50 weeks per year. He spendsj80 , <

percent of his time in the plant office area, 10 percent of his time in the plant shop, and 10 percent of his time in various areas of the plant.

e Electrical Foreman (6)

The Electrical Foreman normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 60 percent of his time in the plant office area, 37 percent of his time in the MEAB, the TGB, and the F3B, and 3 percent of his time in the RCB.

e Journeyman Electrician (18) l 39 The Journeyman Electrician normally works 40 to 48. hours per week, 50 weeks per year. He spends approximately 60 percent of his time in.the MEAB, FHB, and TGB, and 3 percent of his time in the RCB, and 37 percent of his time is divided,between shopwork and work in' areas outside the four main buildings. He is also involved in periodic maintenance jobs and RCB patrol (see Tables 12.4-8 and 12.4-9).

e Apprentice Electricians and Helpers (16) 39 The Apprentice Electricians and Helpers normally work 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months '

per week, 50 weeks per year. Their time is spent divided in the same percentages as the Journeyman Electricians'.

%me e I&C Cw.isor (1) .;

The I&C D"Super.iccr normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, l 50 weeks per year. He spends approximately 70 percent of his time in the plant office area and 30 percent of his time in the MEAB, the RCB, the FHB, and the TGB.

e I&C Technical Supervisor (4) ,

(Same as I&C S cer.)

i 12.4-13 hendment 39

m e

ATTACFHAENT

. ST HL AE. 2/9

PAGE J22 Of '75 STP FSAR 39 e I&C Foreman (9) ,

The I&C Foreman normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per

(

~

year. He spends approximately 50 percent of his time in the I&R shop office area and the remaining 50 percent in the MEAB, the FHB, the RCB, and the TCB.

Instrumentation and Control Engineer (5) 39 e

The Instrumentation and Control Engineer is normally at work 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. It is assumed that he spends 80 percent of his time in the plant office area and 20

, , percent of his time in the MEAB, the FHB, the TGB,.and the RCB.

e Journeyman I&C Testers and Apprentices (62) 39 The Journeyman I&C Testers and Apprentices normally work 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 50 weeks per year. Approximately 70 percent of 2 their time is spent in the MEAB and the RCB. The remainder of their time is spent outside these areas. These personnel'also are involved in periodic maintenance jobs, Containment patrol, monthly RHRS checks, and monthly ECCS checks (see Tables 12.4-8, 12.4-9, and 3 12.4-10, and Table 12.4-11).

MANA GE&

e Maintenance Support Superricer (1)

Mau4 Get ~~

The Maintenance Support Sup:rvisor normally-works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeks per year. He spends approximately 80 percent of his time in the plant office area and 20 percent in var-ious areas of the plant, including the MEAB, the TGB, the FHB, the machine shop, and the RCB.

e Lead Maintenance Specialist (3)

Mana6cA (Same as Maintenance Support Supervicer.)

e Maintenance Specialist (8)

The Maintenance Specialist normally works 40 to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week, 39 50 weeks per year. He spends approximately 70 percent of his time in the plant office area and 30 percent of his time in various areas of the plant, including the MEAB, the TGB, the FHB, the RCB, and the shop areas.

e Lead Parts Technician (1)

The Lead Parra Technician normally works 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per day, 5 days per week, 50 weeles per year. He spends approximately 95 percent of his time in the plaat office area and 5 percent of his timecin various areas of the plant, including the HEAB, the TGB, the FHB, the ma-chine shop, and the RCB.

12.4-14 Amendment 39

o A

-r e ' .

Table 12.4-2 (ContinucJ)

Annual Dose Estimates for FTP Administrative Personnel title radiation zone occupancy fraction radiation zone occupancy, man hours -

number hours expected man hr man res per per dose race 1 2 3 4 5 1 2 -3 4 5 pitnt week ~_ (area /br)-

Budget Clerk .04 2,000 .08 1 2,000 -

! 40 P yroll Clerk .04 2,000 .08 1 .- 2,009 l ' ~ 3.m 40 "a"

1 70,000 2.8 70,000 sub totale:

4 The following personnel will remain in the plant office area 80% of their time and in the general plant area for the other 20% of their time. ,

DIcument Control Supervisor .04 1.600 .064 .8 1,600 -

40 1.25 400 .5 .2 400 .'i ' '

1 39 Ricord Analyst .04 3.200 .128 .8 3.200 40 1.25 800 1 .2 800 g2 .04 1.600 .064 .8 1.600 a

., Scheduler 400 .5 .2

'400 4-g 1 40 1.25 f 1,600 .8 1,600 ,

e Cr:phics Technician .04 .064 '"

1 40 1.25 400 .5 .2 400 Racord Processor .04 4.800 .192 .8 ,

4,800 3 40 1.25 1,200 1.5 .2 1,200 R1 cord Clerk .04 4,800 .192 8 4,800 3 40 1.25 1,200 1.5 .2 1,200 Production Support Supervisor .04 1,600 064 .8 .

1,600 1 40 1.25 400 .5 .2 400 -

Work Activity Control Coordinator .04 1,600 064 .8 1.600 1 40 1.25 400 .5 .2 400 Information System Coordinator .04 1.600 064 .8 1,600 '

400 .5- 400 t3 (A

. 1 40 1.25 .2

>W St ff Analyst * .04 1,600 .064 .8 1.600 1 40 , 1.25 400 .5 .2 400 I>0 Development Analyst. .04 6,400 .256~ .8 6 400 4 40 1.25 1.600 2 .2 1 600 g Computer Technician / Operator .04 1,600 .064 .8 1*600 O 400 .5 .2 400 M

,a 1 40 1.25

o. Syrten Administrator .04 1.600 .064 .8 1.600 QM --4 2 1 40 1.25 400 .5 .2 400 %d

'i f, Emergen. Preparedness Coordinator .04 W 6- -re64 6 .8 g g #4 40 1.25 W , .2 er spw- .2ss o, s oo 1, 400 *2* O

1

.~ .~-

s l .

Table 12.4-2 (Continued)

Annual Dose Estimates for STP Administrative Personnel s

title radiation zone occupancy fraction radiation zone occupancy, man hours number hours expected . man hr man rem per per dose rate 1 2 3 4 5' 1 2 3 4 5 plat week (ares /hr)

Ergineering Technician (Admin.) .04 6,400 .256 .8 6,400 4 40 1.25 1,600 2 .2 1,600 sob totals: 52,000 14.664 41,600' 10,400 39 Crand totals: l20.000 !(5.3^^ pe 0 0 0 13 2,o00 si.677 s t o, s oo : ,9 ea U

b '

'3 s .,

g M'ID

., , . n a 9' mb y=

1 O rn M 2

%M k.

t

'E E

M

\

\, , +.

t #

Table 12.4-3 Annus1 Dose Estimates for STp Operating personnel title radiation zone occupancy fraction radiation zone occupancy, man hours number houra **pected man hr man rem per per done rate 1 2 3 4 5 1 2 3 4 5 plant week (wren /hr) pl:nt Superintendent 2,000 .201 .95 .05 1,900 100 ,

1 40 7 plant office area .04 1,900 .076 .95 1,900 gineral plant area 1.25 100 .125 .05 100 a C.,.....;. L..; u w 3g,gg, 2,000 .685 .75 .25 1,500 500 p y .n seeeee operations 1 40 plant office area .04 1.500 .06 .75 1,500 smeral plant area 1.25 500 .625 .25 Soo .

gpW M n uA<,s R.

b Operations E4ir 4,000 1.37 .75 .25 3,000 3,000 2 40 plcnt office area .04 3,000 .12 .75 3,000 g;neral plant area 1.25 1,000 1.25 .25 1,000 Shift Supervisor Isee4ee , 28,800 18.576 .5 .5 .14,400 14,400 39 12 48 pl:nt office area .04 14,400 .576 .5 14,400 gtneral plant area 1.25 14.400 18 .5 14,400 28,800 .5 .5 14,400 14,400 m i U2it Supervisor :_;h-.-- 18.576 0 12 48

.04 14,400 .576 .5 14,400

{

pt:,nt of fice area g1neral plant area -1.25 14,400 18 .5 14,400 Y % Op;rator 5_; h ;r 43,200 12.1824 .8 .2 34,560 8,640 18 48 pirnt office area .04 34,560 1.3824 .8 34,560 gineral plant area 1.25 8,640 10.8 .2 8,640 '

c f/>

. > ~1 >4 -

Plaaf J.,._C;_., Operator 74,400 36.47088 .74 .25564 .00285 55,056 19.019.62 212.04'! hI> CO 31 48 1

>I patrol TCB, DCB, EAB .04 43,896 1.75584 .59 43,896 p trol MAR 1.36 17.112 23.27232 .23 17.112 @E 2-E pstrol FHB rsfueling 1.25 2.5 543.12 1,339.2

.6789 3.348 0073

.018 543.12 1,339.2 mQ h-t

a. patrol yard .04 !!,160 4464 .15 11.160 4s I p2 trol RCB

'E RHRS check 25 25 37.944 25.296

.9486 6324

.00051 00034 37.944 25.296

%4 w ECCS check 1.25 25.296 .03162 .00034 25.296

36 148.8 5.3568 .002 148.8 periodic maintenance o

Grand totals: l0?j:' ?.8 88.06128 ,;;,;g;.;; O 212 J% 0 l9h2" I2 2,914 51, 459.to 2.

]

7

~

P%

f i I

Table 12.4-4 e

Annual Dose Estimates for STP Technical Personnf title radiation zone occupancy fraction radiation zone occupancy, man hours' nuibar hours expected man-hr ear-rem dose rate 1 2 3 4 5 1 2 3 4 5 per per i plant week (nrem/5r) l 6,000 .966 .9 .1 5.400 600 l Training Manager l

3 40 i effice ares & training facility .04 5.400 .216 .9 5.400 1.25 600 .75 .I 600 pitnt Trcining Supervisor 10.000 1.61 .9 .1 9.000 1.000 5 40

.9 9.000 of fice area & trair.ing facility .04 9.000 .36 1.25 .1 1,000 pitnt 1.25 .l.000 16.36 .85 .I .05 34.000 4.000 2,000 Training Instructor 20 40 offica ares & training facility 04 34,000 1.36 .85 34.000 39 1.25 4.000 5 .1 4,000 plent pitnt 5 2.000 10 .05 2.000 l

R3sctor Q L..pr+ L%er

. . - - :: ,_ : -- i r -- 2,000 .564 .R .2 1.600 400 ,

- 1 40 g

.8 1.600 .o F plent ef fice ares .04 1.600 .064 '

.2 400 .=

i giniral plant area 1.25 400 .5 y

0 Ma ny e,__E,.w e..--,p m A.3 g- %: :; sv- >

_- : 2.000 .322 .9 .1 1,800 200 1 40 pitnt effice area .04 1,800 .072 .9 1.800 1.25 200 .25 .1 200 g:niral plant area

%eo4% W

_2i;'.:;i r:ysics 2,000' 08 1 2.000

- " r-ic;; Manager g

1 40 04 ,2,000 08 1 2,000 g y3 pirnt office area >d M v'wunca @ is.c 8,000 6.224 .7 .2 .I 5.600 1.600 800 I k $' y Ratctor "- ;;f----

CO i

4 40 effice area & training facility .04 1.25 5.600 1.600 2

.224 .7

.2 5.600 1.600 i

kDI "E plant plcnt 5 800 4 .I 800 E

--4 Radiction Protection Supervisor 2.000 .927 .65 .35 1.300 700. g

.04 1,300 .052 .65 1.300 I {pitntcfficearea a g1nermi plant area 1.25 700 875 .35 700 .

t h see+1 12,000 6.288 .6 .4 7.200 4.800 l $ ALARA Health Physicist ,

! 6 40 '

plcnt effice area .04 7,200 .288 .6 7.200 6 .4 4,800 l

g:nstal plant area 1.25 4.800 l

I.

INSERT for p. 12.4-22 radiation zone occupancy fraction ~ radiation. zone occupancy, man hours expected man-hr man-rem dose rate 1 2 3 4 5 1 2 3 4 5 (mrem /hr)

Radiological Support Supervisor 2,000 .927 .65 .35 1,300 1 40 700 plant office area .04 1,300 .052 .65 general plant area 1,300 1.25 700 .875 .35 700

> i O'I m >-4 C

k>O o T iC I

Mbm Z D -1 Ns S*

.y-~

l Table 12.4-4 .

Annual Dose Estimates for STP Technical Personnel (Continued) radiation zone occupancy fraction radiation zone occupancy, man hours.

title expected man-hr man-res number hours 1 2 3 4 5 1 2 3 4 5 per dose rate per plant week (ares /hr) 28,800 6.3792 .85 .35 24,480 4,320 Ls:d Radiation Protection Technician 12 48 24,480

.04 24,480 .9792 .85 p1Ent office area 5.4 .15 4,320 gIneral plant area 1.25 4,320 24,000 8.22 .75 .25 18,000- 6,000 S4nior Radiation Protection Tech.

10 48 18,000 04 18,000 .72 .75 plant office area 6,000 7,5 .25 6,000 g1neral plant area 1.25 14,400 7.5456 .6 4 8,640 5.760 R distion Protection Technician 6 48 8,640 04 8,640 .3456 .6 plant office area 7.2 4 5.760 g:neral plant area 1.25 5.760 14,400 12.7728 .3 .7 4,320' 10,080 39 en Associate Radiation Protection Tech. , ' '

O 6 48 '

4,320

.04 4,320 .1728 .3 5.

,. p1:nt office area 10,080 12.6 .7 10,080 J, gineral plant area 1.25 '

w 5,760 13,440 19.200 17.0304 .3 .7 Junior Radiation Protection Tech.

8 48 5,760

.04 5,760 .2304 .3 plant office area 13,440 16.8 .7 13,440 g1neral plant area 1.25 9,600 8.5152 .3 .7 2,880 6,720 Radiation Protection Aid 4 48 2,880

.04 2.880 .1152 .3 plant office aren 6,720 8.4 .7 6,720 g1neral plant area 1.25 Memo. .2 1.600 400 Systema L. .._9 e.. ; n;: ri::: .564 8 2,000

[%%

1 40

.04 1.600 064 .8 1.600 Oig plant office area 1.25 400 .5 .2 400 r- n g:neral plant area >I 14.166- .7 .25 .05' 15,400 5,500- 1,100 mg Systems Engineer 22,000 O m 11 40 15,400 2

k plant office area .04 15,400 .616 .7 M 5.5 .2 4,400

& gineral plant area g g;neral plant area 1.25 2.5 4,400 1,100 2.75 . 05 3,300 g, goo

, @M 5 1,100 5.5 .05

$ gtneral plant area - l y

2,000 .564 .8 .2 1.600 400 '

Parformance Support Supervisor 1 40

.04 1,600 064 8 1.600 plant office area 400 1.25 400 .5 .2 gineral plant area l 1

Table 12.4-4 .

Annual Dose Estimates for STP Technical Personnel (Continued) radiation zone occupancy fraction radiation zone occupancy, man hours title hours expected man-hr man-rem number 2 3 4 5 1 2 3 4 5 dose rate 1 per per plint week (arem/hr) 14,400 9.288 .5 .5 7,200 7,200 Chemical Operations Foreman 6 48 7,200 pt:nt office area .04 7,200 .288 .5 1.25 3,600 4.5 .25 3,600 radwaste control room .25 3,600 cample station 1.25 3,600 4.5 45,600 34.9296 .4 .6 18,240 27,360 Chemical Operator '

19 48 4,560 pimt office area .04 4,560 .1824 .I 1.25 27,360 34.2 .6 27,360 radwaste control room / processing 13,680 TCB and yard .04 13,680 .5472 .3 52.800 46.1472 .6 .2 .2 31,680 10,560 10,560 Chemical Auxiliary operator 22 48 31,680 TCB and yard 04 31,680 1.2672 .6 1.25 10,560 13.2 .2 10,560 radwaste control room 10,560 .2 10,560 radweste processing 3 31.68 t 7,680 11,520 N

19,200 14.7072 .4 .6 ,

h Lead Chemical Technician i 8 48

.04 7,680 .3072 .4 7,680 O plant office area 11,520 ginsral plant area 1.25 11,520 14.4 .6 39 57,600 30.1824 .6 4 '34,560 23,040 Senior Chemical Technicians 24 48

.04 34,

V 1.3824 .6 34,560 plant office area g:neral plant area 1.25 23,0,0 28.8 4 23.040 A1sociate/Juni.or Chemical Techs, 14,400 4.0608 .8 .2 !!,520 2.880 i 6 48

' .04 11,520 .4608 8 11,520 picnt office trea 1.25 2,880 3.6 .2 2,880 *D u) >

g;neral plant area 294,, n o sir,sso ,4,96o "$y" 0 T I zusent I 4r9, yo 298.457

--i"i,.0^ -2%8- ;;;,;;0 gg g I

>g Grand totals: _a O TE

'bm 2 E '

Nbd o

[

4

INSERT for p. 12.4-25 radiation zone occupancy fraction radiation. zone occupancy, man hours expected man-hr man-rem dose rate 1 2 3 4 5 1 2 3 4 (mrem /hr) 5 Technical Services Manager 2,000 .08 .1 1 40 2,000 plant office area .04 2,000 .08 .1 2,000 Integrated Planning and Scheduling Manager 2,000 .322 .90 .10 1 40 1,800 200 plant office area .04 1,800 .072 .90 1,800 general plant area 1.25 200 .250 .10 200 Plant Computer Manager 2,000 .927 .65 .35 1 40 1,300 700 plant office area .04 1,300 .052 .65 1,300 general plant area 1.25 700 .875 .35 700 96 3>

"I hk '* 3

. n G~ cs 1> ac rn a=

C) 65

'1 3E

~

-. .~

Table 12.4-5 ,

Annual Dose Estimates for STP Maintenance Personnel title tsdiation zone occupancy fraction radiation zone occupancy, man hours number hours expected man-hr man-rem per per dose rate 1 2 3 4 5 1 2 3 4 5 plcnt week (ares /hr)

AtauAgeA.

Maintsnince "_,_.. a._ ..; 2.000 .322 .9 .1 1.800 200 1 40 plcnt effice area .04 1.800 .072 .9 1.800 ginsrsi plant area 1.25 200 .25 .1 200:

pA m sen.

Mech;nical Maintenance E ,_ .; m 2.000 .322 .9 .I 1.800 200 1 40 '

pla t effice area .04 1.800 .072 .9 1.800 g:naral plant area 1.25 200 .25 .1 200 Mech. Maintenance Technical Super. 8,000 1.288 .9 .1 7.200 800 4 40 plant effice area .04 7.200 .288 .9 7.200 gen 2rsi plant area 1.25 800 1 .1 800 39 Mechanical Foreman 26.400 18.678 .5 .5 13.200 13.200 8

11 48 '"

pleait affice area .04 13.200 .528 .5 . 13.200 MEAR arsa 1.25 11.880 14.85 45 . 11.880 '

RCB 2.5 1.320 3.3 .05 1.320 Journeyman / Apprentice Mechanics 168,000 154.2068 .784 .19519 .020146 .000101 131.712 32.791.92 3.384.528 16.968 70 48 .

periodic maintenance 25 641.76 16.044 .00382 641.76 RCP #3 teal replacement 100 16.968 1.6968 .000101 16.968 RCB patrol 25 37.968 .9492 .000226 37.968 fuel receiving 1.25 199.92 .2499 .00119 199.92 TCB .04 33.600 1.344 .2 33.600

. rsfueling i 33 2704.8 89.2584 0161 2.704.8 , #_4 1.25 40.74 .194 32.592 1 32.592 ;

pi$

MAB , m-r EAR .04 98.112 3.92448 .584 98.112 A1MA3eR Sy Elsetrical Maintenance t , _ ::r- 2.000 .564 .8 .2 1.600 400 N fut g 1 40 O n

.04 .064 .8 1.600

2 1.600 plant effice area generr.1 plant area 1.25 400 .5 .2 400 9s*

It*

E Electrical Maintenance Tech. Super. 4.000 1.128 8 .2 3.200 800 f

Y E. 2 40 '

I plant affice area .04 3.200 .128 .8 3.200 N g;ner:1 plant area 1.25 800 I .2 800 5

~

)

Table 12.4-5 Annual Dose Estimates for STP Maintenance Personnel (Continued) radiation zone occupancy fraction radiation zone occupancy, man hours title man hr man res expected 2 3 4 5 number hours dose rate 1 2 3 4 5 1 per per pint week (ares /hr)

.4 7,200 4,800 12,000 6.288 6 Electrical Foreman 6 40 6 7,200 04 7,200 .288 4,800 plant office area 1.25 4.800 6 4 general plant area

.37 626 00424 30,192 51,081.6 345.984 Journeyman / Apprentice Electrician 81,600 76.66728 34 . 48 .00397 323.952 25 323.952 8.0988 48,715.2 periodic maintenance 1.25 48,715.2 60.894 .597 NEAB,Fus,Tc8 .029 2,366.4 2.5 2.366.4 5.916 30,392 RC8 1.20768 .37 04 30,192 22.032 thop and yard areas 22.032 .5508 00027 containment patrol 25

.3 1.400 600-Mens AGE A 2,000 806 .7 I6C L;: cirr- cm .

40 1,400 1

04 1,400 056 .7 600 -4 1.25 600 .75 .3 39 m

{ plantgeneral office plantarea area 5,600 2,400 g 8

8,000 3.224 7 .3 t$ IEC Technical Supervisor ,

4 40 .7 5,600 04 5.600 .224 2,400 plant office area 2,400 3.0 .3 general plant area 1.25 6 4 12,960 8,640 21,600 12.6684 IEC Foreman 9 48 10,800

.04 10,800 .432- .5 2,160 16C office and shop 04 2,160 0864 .1 TCB .25 5,400 1.25 5,400 6.75 2,160

T (h >

MEAR 1.25 2,160 2.7 .1 >dd 1,080 FHS RCs) 2.5 1,080 2.7 .05 2,000 i

KIN CO i

.8 .2 8,000 >I 10,000 2.82 1&C Engineer 8,000 or E 40 5

plant office area 04 8,000- .32 .8

.2 2,000 $

general plant ares 1.25 2,000 2.5 81,096 66.985.00 699.2112 24.9984 s-hN 148,800 105.0803 .545 450168 004699 000168 N r, Journeyman IEC Teaters & Apprentices 48 .00435 647.28

{u 62 periodic maintenance 25 647.28 16.182

45. 66,960

1.25 66,960 83.7 24.9984 MAB, FHB .000168 25 24.9984 62496 24.9984

$ monthly RRRS test .031248 .000168 monthly ECCS test 1.25 24.9984 51.9312 1.29828 .000349 RCS patrol 25 51.9312 81,096'

.04 81.096 3.24384 .545 rone I areas

l .

.-~,

I

. Table 12.4-5 Annual Dose Estimates for STP h intenance personnel (Continued) title radiation zone occupancy fraction radiation zone occupancy, man hours l

number houra espected man hr man rem per per done rate 1 2 3 4 5 -1 2 3 4 '5 plant week (mres/hr) l M A#A6d A h irtenance Support !_,- :12:: 2.000 .564 .8 .2 1.600 400 l 1 40

plant office area .04 1.600 .064 .8 1.600 general plant area 1.25 400 .5 .2 400 i

t Lead hintenance Specialtat 6.000 1.692 .8 .2 4.800 1.200 3 40 plant office area .04 4.800 .192 .8 4,g00 general plant area 1.25 1,200 1.5 .2 1.200 h irtenance Specialfat 19.200 7.7376 .7 .3 13.440 -5.760 8 48 plant office area .04 13.440 .5376 .7 33,440 general plant area 1.25 5.760 7.2 .3 5.760 Lead Parta Technician 2.000 .201 .95 .05 1,900 100 39 1 40

.076 .95 1.,900 E plant office area .04 1.900 y general plant area 1.25 100 .125 05 100 $

6.000 .603 .95 05 5,"700 300 Pzrts Technician 'N 3 40

- plant of fice area .04 5.700 .228 .95 5.700 general plant area 1.25 300 .375 .05 , 300 Mates %" y .8 .2 400 Lead ~_ _ g Lab Technician 2.000 .564 1.600 1 40 .

.064 .8 1.600 D (n y plant shop area .04 1.600 .

>-4y general plant area 1.25 400 .5 .2 400 -

I Lab Technician 10.000 .2.82 .8 .2 8.000 2,000 I-5 40 t ,] > I

.04 8.000 .32 .8 8.000 'o @ E plant shop area .

. l general plant area 1.25 2.000 2.5 .2 2.000 mM %4 .

N g 1.ead Tool Control Technician 2,000 .322 .9 .I 1.800 200 s% %

g I 40

' 3 plant shop ares .04 1.800 .072 .9 1.800 general plant area 1.25 200 .25 .1 200 e

J

5 i .

Table 12.4-5 Annual Dose Estimates for STP Maintenance Personnel (Continued) ,

title radiation zone occupancy fraction radiation zone' occupancy, man hours number hours expected man hr man rem per per dose rate 1 2 3 4 5 1 2 3 4 5 plant week (ares /hr)

Tool Control Technician 4.000 .644 .9 .1 3,600 400 39 3 40 plant shop area .04 3,600 .144 .9 3.600 general plant area 1.25 400 .5 .1 400 Crand totals: - M0.%i 399.21 349.400 195.658 0 4,430 42 549,soo a

4 t

.h.D M

- l

. i t $0%.

oi-r

m

. h >T2 >O ANE O res l 1 2 s .

[

M 3

% v --

, .~~,_

r.

l i TABLE 12.4-6 ESTIMATED ANNUAL DOSE ESTIMATES FOR UNIT 1 AND 2 aitlMttt114#T OPERATORS t

Expected Dose Rate Time Frequency Annual Dose (ares /hr) (man-min) (times / shift) (man-ren)

Equipment and/or Route A. Mechanical Auxiliary Building 1.25 30.00 8 5.460

1. Walking distance (8.000 f t) 1.25 10.0 8 1.520

2. local HVAC control panels (E1. 60 f t) 0.455 1.25 10.0 2

3. Containment Purge System (E1. 50.5 ft) 0.455 1.25 10.0 2

4. Supplementary Purge Exhaust System (E1. 50 ft) 1.25 6.0 2 0.273

5. Potentially contaminated cubible return air filters and fans (E1.50.5 ft) 1.25 16.0 2 ,0.728

6. BVAC prefilters, filters supply air fans (Els. 60 ft and 70 ft) 1.25 10.0 8 1.820

7. HVAC control panels (Els. 60 ft and 70 ft) 1.25 2.0 8 0.364

8. Boron Thermal Regeneration System chiller and chiller pumps (E1.10 f t) 3.0 10.0 2 3,092

9. Filter valve operating area (E1. 41 f t) 3.0 10.0 2 1.092

10. Demineralizer valve operating area (E1. 41 f t) 1.25 10.0 8 I.820

11. Radwaste Control Room (E1. 35 ft) 0.364 1.25 2.0 , 8

12. CCW HI (E1. 26 ft) 2.0 0.364 1.25 8 %

13. Boron injection makeup pumps (El. 10 ft) ,

1.25 2.0 '

8 0.364 g

." 14. Sump pumps (E1. 4 ft) 0.364 $

1.25 2.0 8 g 15. HI cubicle exterior (E1. 10 ft) 10.0 2 g,092 3.0

16. 51 valve operating room (El. 19 ft)

1.25 2.0 2 0.091

17. Reactor water makeup pumps (El.10 f t) 1.25 2.0 'l 0.046

18. Refueling water pumps (El. 10 ft) 1.25 220.0 1 5.005

19. Office (E1. 35 ft) .

o m I >.

CO

>I m gig O m m Z 3- N -i a

E. Q9 8

E 3

c

c a

1 i

TABLE 12.4-6 (Continued)

PlowT" ESTTMATED AME!!AL DOSE ESTIMATES FOR tRf!T I AND 2 MD9MaH OPERATORS Expected Dose Rate Time Frequency Annual Dose -

Equipment and/or Route (ares /hr) (man-min *f (once per). (man-ren)

3. Fuel-Randling Building 1.25 10.0 shift 0.228

1. Walking distance (2.000 f t) 1.25 6.0 shift 0.137

, 2. Inspection of operating floor equipment (El. 68 ft) 1.25 6.0 shift 0.137 1

3. Inspection of E1. 48 ft equipment 1.25 6.0 shift' O.137

4. Inspection of E1. 30 ft equipment .l.25 2.0 shift 0.045

5. New fuel laydown (El. 21 ft 11 in.)

Expected Dose Rate occupancy Annual Dose l

(aren/hr) (man-hr/yr) (man-ren)

Equipment and/or Route 4

0.04 44.000 1.76 39

. C. TC3. DCB and EAR 0.04 11.160 .446 O. 'ceneral yard ,

2.5 1.344** 3.360 E. Refueling operations assistance ,

See Table 12.4-9 38 *

.950

(

3 F. Containment entry b9 -

E mi, cn 1

4 g>I AE O m

' Z H

{'s.

1 s

a

I g

g PLAW e 50 wk/yr - 2 wk/yr spent on refueling'g'- tasks (4 personnel)

- During refueling operations. the ^- ; Operators responsible for patrol of the TCB. DCB and EAR shall b. involved in support work.

They shall be involved with system operation required for maintenance and refueling.

1 i

r -

1 i TABLE 12.4-7 CALCULATED EIFOSURES DURINC PERIODIC MAINTENANCE IN THE MECHANICAL AUITLIART 39 BUILDING / fur.L-HANDLING BUILDING / REACTOR CONTAINMENT BUTIDING Expected Dose Time

Annual Dose Rate (ares /hr) (man-hr) Frequency (man-ren)

Equipment and/or Route A. Mechanical Auxiliary Building (MAB) 1.25 17 year 0.021

1. Service boron thermal regeneration chiller pumps Service laundry and hot shower tank pump 1.25 9 year 0.0!!

2.

1.25 57 year 0.071

3. Service sump pumps 2

25.00 17 year 0.425 4 Service sump pumps 1.25 17 year 0.021

5. Service chiller pumps 1.25 25 year 0.031

6. Service RCB If?AC chilled water pumps 1.25 21 year 0.031

7. Service NAB IIVAC chilled water pumps 1.25 17 year 0.021

8. Service reactor makeup water pumps 1.25 17 year -0.021

9. Service HVAC fans 1.25 75 year 0.094

10. Service CCW pumps 1.25 9 year 0.011

11. Service boron injection makeup pump 1.25 9 year 0.011-

.- 12. Service refueling water purification pump sn

13. Service laundry and hot shower tank pump 3.0 9 : year 0.027 4

'p

14. Service CFRW collection tank pump 3.0 9 year 0.027 3 0

N 3.0 17 year 0.051

15. Service boric acid pump 3.0 9 year 0.027

16. Service WPS recycle evaporation feed pumps 3.0 9 year 0.027

17. Service LWPS waste evaporation condensate pumps ,

25.0 9 year .0.203

18. Condensate polishing regeneration vaste collection pump

. 11/2 y

> 4

! O'DI -e m

t C f4

, a kDI m

E A?K 0 m

= ' 2

-1 4 %

gp0

One 40 is required for component isolation. The assumed exposure time is 1 man-hour per task.

. . . . _ . _ _ . - _ . _ . . . - . _ _ _ _ _ . _ _ . . _ . - . ._ ....s . _ . . _ . . _ . . _ _ . _ . . _ . _ . . ... _ _ . _ . .__ . . , . _ _. . m... _ . _ _ . . , , _ , .- -. _ . .

m e f\ 1 e i

l 1

! ! TABI.E 12.4-7 (Continued) .- ,

4 (CAREUTATED EXPOSURES DURINC PERIODIC MAINTENANCE IN THE MECHANYCAL AUXILIARY 39 BUILDING / FUEL-RANDLING BUILDINC/ REACTOR CONTATISEENT SUILDINC Expected Dose Time

Annual Dose Frequency Equipment and/or Route Rate (ares /hr) (man-hr) (man-rem)

19. Service SUPS equipment 50.0 2 week 5.200

20. Service LWPS spent resin transfer pumps 15.0 17 year 0.255

21. Service recycle evaporator feed pumps 15.0 17 year. 0.255

22. Service charging pumps 15.0 150 year 2.250

23. Service LUPS WRT pump 15.0 9 year 0.135

24. Service reactor coolant purification pump 15.0 9 year 0.135 40.0 9 week 18.720

25. Valve maintenance Rapid refueling vacuum pump and compressor 15.0 17 year 0.255 26.

27. Filter cartridge replacement 10.0 81 year. 0.810 I 28. Service boron recycle evaporator 15.0 101 year 1.515

29. Service LWys waste evaporator 15.0 101 year 1.515 j .

i l 3. Fuel-Mandling Building (FWB) g' ,

3.00 17 year 0.063 ,

,~E 1. Service spent fuel pool pumps

2. ' Service skiimer pump 3.00 9 year 0.039 h.

-[" 1.25' 25 year 0.031

3. Service WTAC equipment .

t Walking time (1.351 ft) 1.25- 0.22 4/ year 0.001 4.

FNB crane 1.25 9 year 0.011 5.

1.25 33 a year 0.041-

6. FRS sumps 7 (t) >

~

> -4 i .-

C) i -4 I hwz Cb

' 7mg O m i

. 2.4 1 ..

%N

=

{i . k i o RFo

One te is required for component isolation. The assumed exposure time is I man-hour per task. '

i l

i 4

y i

r..

l 1

TABLE 12.4-7 (Continued)

(CAlfULATED EXPOSURES DURTNG PERIODIC MAINTENANCE IN THE MECHANICAL AURILIART 19 BUILDING / FUEL HANDLING BUILDING / REACTOR CONTAINMENT BUILDING 1

l Annual Dose Expected Dose Time

Rate (ares /hr) (man-hr) Frequency (man-ren)

I Equipment and/or Route C. Reactor Containment Building (RCB) 100 33 year 3.300

1. RCF oil change (4 pumps) 100 17 year 1.700

2. Service RCDT pumps 100 25 year 2.500

3. Service RHES pumps Service HVAC equipment 2 17 year 0.0 34 l2 4.

2 25 year 0.050

5. Service containment sump pumps 100 17**** year 1,700 l3'

6. RCP #3 seal replacement (1 puep per 6 months) 2 9 year 0.018

7. RCB crane .l2 3

in -

Y 4

l I i b T CD

, b -4 O'y mI

. i Co 1 DI 8'

O TE f m m 7

a.

o ND N-

'3 g ro I

One M is required for component isolation. The assumed exposure time is 1 man-hour per task.

- - - Time based on the exposure of two Mechanical personnel. e personnel are not involved.

R PO l

.m

T

,-~ -

7 TABLE 12.4-8 .

ESTIMATED ANNUAL EXPOSURES - VEEKLY CONTAINMENT PATROL

(

Expected Dose Time Frequency Annual Dose Equipment and/or Route Rates (ares /hr) (man-hr) (once per) (man-rea) l Reactsr Containment Building I 1. Valking distance (3.000 ft) 25 1.00 week I.250 2

2. Inspect steam lines. Instruments, etc. 25 0.67 week .833 Q331

3. Inspect steam line penetrations 25 0.67 week .833

. 4. Inspect accumulators, pressurizer relief tank, etc. 25 1.00 week 1.250, l 5. Inspect RCFC. etc. 25 1,67 week 2.083

6. Inspect sumps, etc. 25 0.67 week .'833 l

Total 7.500 I

l P2trst is made by one Shif t Supervisor or one Unit Supervisor, one Head Operator Mee&ees, and a member of the Electrical Maintenance Crew. the Mechanical l39 Maistenance Crew, the Instrumentation and Control Crew, or the Auxiliary Operator Crew. Patrol duties are assumed to be shared as follows: Electrical l personnel 15Z. Mechanical personnel 25%. Isc personnel 35Z. and Auxiliary operator personnel-25Z. Electrical: 22 man-ht; Mechanical: 38 man-hr; I&C: 52 man-hr; 40: 38 man-hr. , g y RPO 'y l3 5

> -4

i MItD n

' $DI

' b sun g O rei

Z

-e l

1 1

i

_J

c. y.

{- ]

t .

TABLE 12.4-9 ,

39 ESTIMATED ANNUAL EXPOSURES - MONTHLY'RilRS CFECK Estimated Dose Time Annual Dose Equipment and/or Route Rates (arem/hr) (man-hr) Frequency (man-ren)

Reactor Containment Building

1. RHRS check 25 0.50 monthly 0.150

2. RHR test run 25 3.0 monthly 0.900

3. RHR pump leak check 25 0.50 monthly 0.150

4. Walking distance (1,200 ft) 25 0.20 monthly 0.060 Total 1.260 gPO ,

w (AG and I&C personnel) t g-m T *

? [

. new p2me E

a ss-5 P,

8

1 .

TABLE 12.4-10 39 ,

ESTIMATED ANNUAL EXPOSURES - MONTHLY ECCS CHECK Estimated Dose Time Annual Dose Equipment and/or Route Rates (arem/hr) (man-hr) Frequency (man-rem)

Fuel-Handling Building

1. ECCS check 1.25 2.00 monthly 0.030

2. ECCS test run 1.25 2.00 monthly 0.030

3. Walking distance (600 ft) 1.25 0.25 monthly 0.003 R FC (Check made by 1 *O and 1 I&C person) m

- 4 f w m

g ,s m; , _.

' CO b

a g

aa

? ~

s rt i

ATTACHMENT

. ST-HL AE #2/9 STP FSAR

. . PAGE 53/ 0F75-

' TABLE 12.4-15

( ANNUAL AIRBORNE DOSES TO STP ADMINISTRATIVE PERSONNEL title number hours man *hr man

rem man

rem {

per per thyroid- whole-plant week .

body:

A Plant Manager 2,000 .00342 .00342 1 -40 plant office area 1,900 general plant area 100 .00342 .00342 Hanagement Services Manager 2,000 .00684 .00684 1 40 plant office area 1,800 general plant area 200 .00684 .00684 The following personnel will remain in the plant office area 80% of plant area for the other 20% of their time. M

&cis r:nt And tu rhe.yaenAL Document Control Supervisor 1 40 400 .01368' .00003892

, Record Analyst i 2 40 800 .02736~ .00007784

. Scheduler 39 1 40 400 .01368 .00003892 Graphics Technician 1 40 400 .01368 .00003892 Record Processor 4 3 40 1,200 .04104 .00011676 Record Clerk 3 40 1,200 .04104 .00011676 Production Support Supervisor 1 40 400 .01368 .00003892 Work Activity Control Coordinator 1 40 400 .01368 .00003892 ,

i Information System Coordinator !

1 40 400 .01368 .00003892 l Staff Analyst 1 40 400 .01368 .00003892 Development Analyst 4 40 1,600 .05472 .00015568 2

Computer Technician / Operator 1 40 400 .01368 .00003892 System' Administrator --

1 40 400 .01368 .00003892 Emergency Preparedness Coordinator /, 4,eo .osv74 .ooortr67 M 40 40& ^1 M .4000WM

Engineering Technician (Admin.)

40 1,600 .05472 .00015568

! (> 4 Grand Totals: 10,700 .46694 .4112?162 l

se,9eo . 4 04.9f . on stref

! , 12.4-43 Amendment 39

. ~ -~ _- - - , ,- .-. .---. . . . - - .. - -.

ATTACHMENT STP FSAR. ST.HL AE Ja/9' PAGE WOF 75 TABLE 12.4-16 ;

4 . _ . .

I' ANNUAL AIRBORNE DOSES TO STP OPERATING PERSONNEL t

! title 4

number hours man *hr- man

rem man

rem j per per thyroid. whole

. plant week .

. body

[PlantSuperintendent 2,000 .00342 .00000973h 1 40 1,900 0 0 l

[ ' plant office area eneral plant area 100

.00342 .00000973 )

i PLner Mnun s sn. ~

j -Reeeeee Operations S;;;;in ;;t;; 2,000 .0171 .00004865 1 40 plant office area 1,500 0 0 j general plant area 500 .0171 .00004865 Mnusess, truir Operations ". ;.1;;; 4,000 .0342 .0000973 2 40 .

} plant office area 3,000 0 0 general plant area 1,000 .0342 .0000973 ,

39

. Shift Supervisor Nuclear 28,800 .49248 .00140112 12 48

, plant office area 14,400 0 0

- general plant area 14,400 .49248 .00140112 I Unit Supervisor Nuclear 28,800 .49248 .00140112

~

12 48 l plant office area 14,400 0 0 general plant area 14,400 .49248 .00140112 ;

Rtur* A Operator ".c1. . 43,200 .295488 .000840672 2 18 48

plant office area 34,560 0 0 general plant area 8,640 .295488 .000840672

}

i PLAM1'

A lii ., Operator 74,400 3.466575 1.622749084 1 31 48 patrol TGB 14,136 .00657324 .001512552 ,

.0016649976 patrol MAB 17.112 .5852304 patrol FHB 543.12 .624588 .40245192 j refueling 1,339.2 1.754352 1.1262672

) patrol yard, EAB, DGB 40,920 0 0 :

J patrol'RCB 37.944 .2769912 - .04325616 l RHRS check 25.296 .1846608 .02883744

! ECCS check 25.296 .0290904 .018744336

-- periodic maintenance 148.8 .00508896 .0000144782 e

Grand Totals: -103,143.0 -4.GG1743 1.020;47070 iN Itl, zoo sj,7s ysst.$ t.4 164/Co376 l

12.4-44 Amendment 39

r ATTACHMENT ST HL AE RNf

'a * 'STP FSAR' PAGEf5 0FfS ,,

Table 12.4-17 --

t Annual Airborne Doses to STP Technical Personnel Title Number Hours Man-Rem per per Man-Rem Whole Plant Week Man-Hr Thyroid Body Training Manager 6,000 .0205 neg.

3 40 office area & training facility 5,400 0 0 plant . 600

.0205 neg.

Training Supervisor 10,000 .0342 neg.

5 40 office area & training facility 9,000 0 0 plant 1,000 .0342 neg.

Training Instructor 40,000 .206 neg.

20 40 office area & training facility 34,000 0 0 plant 4,000 .137 neg.

plant 2,000 .0685 neg. 39 6+ggoc+ %%

Reactor "=sfe.wenc%sce Supervisee- 2,000 .0137 neg.

1 40 plant office area 1,600 0 0 general plant area 400 .0137 neg.

P h t E w p u . g m . m a..-

-Technica. Support Superintendend 2,000 .0195 neg.

1 40 plant office area 1,800 0 0 general plant area 200 .0195 neg.

h% Pk tes Rediclogical-Servieee Manager 2,000 0 0 1 40 plant office area 2,000 0 0 Reactor -En ineeE 8000 0822 neg.

4 40 office area & training facility 5600 0 0 plant 1600 .0548 neg.

plant 800 .0274 neg.

Radiation Protection Supervisor 2000 .0240 neg.

1- 40 plant office area 1300 0 0 general plant area 700 .0240 neg.

Tw e,tr+ l

( I l

l 1

12.4-45 Amendment 40

ATTACHMENT

- ST HL AE. 22/9 PAGEN40E 75 INSERT for p. 12.4-45 Title Number Hours Man-Rem per per Man-Rem Whole Plant Week Man-Hr Thyroid Body Radiological Support Supervisor 2,000 .0240 neg.

1 40 plant office area 1,300 0 0 general plant area 700 .0240 neg.

l L3/NRC/ok I

J

ATTACHMENT

. ST HL.AE.22/9 PAGE V70F '/S STP FSAR Table 12.4-17 (Continued)

Annual Airborne Doses to STP Technical Personnel Title Number Hours -

Man-Rem per per Man-Rem Whole Plant Week Man-Hr Thyroid Body ALARA Health Physicist 12,000 .164 neg.

6 40 plant office area 7,200 0 0 general plant area "4,800 .164 neg.

Lead Radiation Protection Technician 28,800 .148 neg.

12 48 plant office area 24,480 0 0 general plant area 4,320 .148 neg.

Senior Radiation Protection Technician 24,000 .205 001 10 48 plant office area 18,000 0 0 general plant area 6,000 .205 .001 39 Radiation Protection Technician 14,400 .197 .001 6 48 plant office area 8,640 0 0 general plant area 5,760 .197 .001 Associate Radiation Protection Tech. 14,400 .345 .001 6 48 plant office area 4,320 0 0 general plant area 10,080 .345 .001 Junior Radiation Protection Tech. 19,200 460 .001 8 48 plant office area 5,760 0 0 general plant area 13,440 .460 .001 Radiation Protection Aid 9,600 .230 .001 4 48 plant office area 2,880 0 0 general plant area 6,720 .230 .001 Ales Ase rs Systems ......_...... _._,_...__. 2,000 .014 neg.

1 40 plant office area 1,600 0 0 general plant area 400 014 neg.

12.4-46 Amendment 40

ATTACHMENT

. STP FSAR ST.HL-AE- -7.7/9

. PAGE e/f 0F 75 Table 12.4-17 (Continued) ._

, Annual Airborne Doses to STP Technical Personnel Title Number Hours Man-Rem per per -

Man-Rem Whole Plant Week Man-Hr Thyroid Body Chemical Operations & Anal. 4kg>Mada'fR 2,000 .017 neg.

1 40 plant office area 1,500 0 0 general plant area 500

.017 neg.

Chemical Analysis Supervisor 2,500 .026 neg.

1 50 plant office area 1,750 0 0 general plant area 750 .026 neg.

Chemical Operations Supervisor 2,500 .017 neg.

1 50 plant office area 2,000 0 0 general plant area 500 .017 neg.

Chemical Operations Foreman 14,400 .246 neg.

6 48 plant office area 7,200 0 0 radwaste control room 3,600 .123 neg.

sample station 3,600 .123 neg.

i Chemical Operator 45,600 .942 .004

! 19 48 plant office area 4,560 0 0 j radwaste control room / processing 27,360 .936 .003 j TGS and yard 13,680 .006 .001 3

Chemical Auxiliary Operator 52,800 .738 .005 22 48 TGB and yard 31,680 .015 .003 radwaste control room 10,560 .361 .001 radwaste processing 10,560 .361 .001 Lead Chemical Technician 19,200 .394 .001

. 8 48 i plant office area 7,680 0 0 I

general plant area 11,520 .394 .001 i

}

i l

l 12.4-48 Amendment 39

ATTACHMENT ST.HL.AE. r.v9 ;

STP FSAR , FACE 90F 7s ' t, Table 12.4-17 (Continued) .__

Annual Airborne Doses to STP Technical Personnel s Title Number Hours Man-Rem per per Man-Rem Whole 'I Plant Week Man-Hr Thyroid ; Body' Senior Chemical Technicians 57,600 .789 .002 24 48 34,560 0 0 39 plant office area general plant area 23,040 .

.789 .002 '

14,400 .099 neg.

Associate / Junior Chemical Techs.

6 48 15,520 0 0 pit.nt office area general plant area 2,880 .099 neg.

l %Ns r RT ] 404,100 0.5^5 .019 Gr~and totals:

4g9,400 4.664 i.

(

l l 12.4-49 Amendment 39

i L---__--_-_----__--________

37 i"'94 1,

c' . ATTACHMENT-i ST,HL.AE .P.2/9 FAQt30M 75-K INSERT for p. 12.4-49 Title

. Number Hours , . Man-Rem per per .

Man-Rem Whole Plant Week Man-Hr Thyroid Body Technical Services Manager 2,000 0 0 1 40 plant office area 2,000 0 0 Integrated Planning and d Scheduling Manager 2,000 .0195 neg.

1 40 plant office area 1,800 0 0 general plant area- 200 .0195 neg.

),c- c."

Plant *tomputer Manager 2,000 .0240 neg.

1 40 plant office area 1,300 0 0 general plant area 700 .0240 neg.

L3/NRC/ek

ATTACHMENT

. . STP FSAR . ST HL AE A7/9 P. AGE 5 OF 75 Table 12.4-18 .--

Annual Airborne Doses to STP Maintenance Personnel Title Number Hours Man-Rem per per Man-rem Whole Plant Week Man-Hr Thyroid Body Maintenance Supe +4utendent ManaGeri 2,000 .007 neg.

1 40 plant office area 1,800 0 0 general plant area 200

.007 neg.

Maa n ca z.,

Mechanical Maintenance Opc. 1;;r 2,000 .007 neg.

1 40 plant office area 1,800 0 0 genera.1 plant area 200 .007 neg.

Mech. Maintenance Technical Supervisor 8,000 .027 neg.

4 40 plant office area 7,200 0 0 general plant area 800 .027 neg.

Mechanical Foreman 226,400 2.134 1.110 39 11 48

' plant office area 13,200 0 0 MEAB area ,

11,880 .406 .001 RCE 1,320 1.727 1.109 Journeyman / Apprentice Mechanics 168,000 4.800 2.485 70 48 periodic maintenance ,

641.76 .022 neg.

ECP #3 seal replacement 16.968 .022 .014 RCB patrol 37.968 .278 .043 fuel receiving 199.92 .231 .148 TGB 33,600 .016 .003 refueling '-

2,704.8 3.116 2.274 MAB 32,592 1.115 .003 EAB 98,112 0 0 Man sert.

Electrical Maintenance 4 ;;ci;;r 2,000 .014 neg.

1 40 plant office area 1,600 0 0 general plant area -

,424 .014 neg.

, yuoo i

. . .I 4

, t p /

12.4-50 r Amendment 39 3

f

ATTACHMENT ST HL AE #A/9 STP FSAR PAG-- E 540F 6 Table 12.4-18 (Continued) .__

j Annual Airborne Doses to STP Maintenance Personnel

^

Title Number Hours Man-Rem per per - Man-rem Whole Plant Week Man-Hr Thyroid Body Electrical Maintenance Tech. Sup 4,000 .027 neg.

2 40 plant office area 3,200 0 0 general plant area 800 .027 -neg.

Electrical Foreman 12,000 .162 neg.

6 40 plant office area 7,200 0 0 general plant area 4,800 .162 neg.

Journeyman / Apprentice Electric 81,600 4.936 2.019 34 48 .

periodic maintenance 323.952 .011 neg.

MEAB, FHB, TGB 48,715.2 1.667 .005 39 RCB 2,366.4 3.097 1.989 shop and yard areas 30,192 0 0 containment patrol 22.032 .161 .025 Mwn sen.

I & C Sup:rcir:: 2,000 .021 neg.

1 40 plant office area 1,400 0 0 general plant area 600 .021 neg.

I & C Technical Supervisor -2,000 8,c00 r424 .off neg.

24 40 plant office area W 5A ** 0 0 general plant area 40G 23 4 8* rGE+ .o## neg.

I & C Foreman 21,600 4.088 .909 9 48 I&C office and shop 10,800 0 0 TGB 2,160 .001 neg.

MEAB 5400 .185 .001 FHB 2,160 2.489 neg.

RCB 1,080 1.413 .908 I & C ' Engineer 10,000 .068 neg.

5 40 -_

plant office area 8,000 0 0 general plant area 2,000 .068 neg.

l-N.

12.4-51 Amendment 39

- - ATTACHMENT

. ST.HL AE .M/9 STP FSAR PAGES30F 75 Table 12.4-18 (Continued)

Annual Airborne Doses to STP Maintenance Personnel Title Number Hours -

per per Man-Rem Plant Week Man-rem Whole Man-Hr Thyroid Body Journeyman I&C Testers & Apprentices 148,800 62 48 2.905 .113 periodic maintenance MAB,FHB 647. 28 .022 66,960 neg.

monthly RHRS test 2.291 .007 montbiy ECCS test 24.9984 .183 .028 RCB patrol 24.9984 .029 51.9312 .019 zone 1 areas .380 .059 81,096 0 MMA6fR neg.

Maintenance Support-Sup rcisc: 2,000 1

40 .014 neg.

plant office area general plant area 1,620 0 0 500 .014 neg.

Lead Maintenance Specialist 39 3 40 6,000 .041 neg.

' plant office area general plant area 4,800 0 1,200 0

.041 neg.

Maintenance Specialist 8 48 19,200 .197 .0 01 plant office area general plant area 13,440 0 5,760 0

.197 .0 01 Lead 1

Parts Technician 2,000 40 .003 neg.

plant office area general plant area 1,900 0 0 100 .003 neg.

Parts Technician 3 40 6,000 .010 neg.

plant office area t

genera. plant area 5,700 0 0

\ .

300 .010 neg.

l Lead Ect;c ,.cgp Lab Technician 1

40 2,000 .014 neg.

plant ' shop area t

general plant area 1,600 0 -

{ ,

O 400 .014 l neg.

t

ATTACHMENT STP FSAR ST HL-AE #4/9

-

PAGES/OF 75-Table 12.4-18 (Continued)

Annual Airborne Doses to STP Maintenance Personnel

[

Title Number- Hours Man-Rem per per Man-rem Whole Thyroid Plant Week Man-Hr Body aw.g; M;;;r_yc;7 Lab Technician 10,000 .068 neg.

5 40 8,000 0 0 plant shop area general plant area 2,000 .068 neg.

~

Lead Tool Control Technician 2,0b0 .007- neg.

1 40 1,800 0 0 39 plant shop area general plant area 200 .007 neg.

Tool Control Technician 4,000 .014 neg.

2 40 '

plant shop area 3,'600 0 0 general plant arec 400 .014 neg.

t%. 6 42 Grand Totals: r#9,6co ia,;;; 6.637 i

o

~.

l i

12.4-53 Amendment 39 l

l t >

ATTACHMENT

, , STP FSAR . ST-HL AE-44/9 PAGEff0F 75 TABLE 12.4-19 39

j. . ANNUAL AIRBORNE EXPOSURE DOSE ESTIMATES FOR CONTRACT PERSONNEL

. Occupancy Thyroid Total Body Job or Location (Man-Hrs) (man-rem) (man-rem) 39 2

Q331

[ Contract Personnel (Thyroid: man-rem -4r&54

,935" Total Body: man-rem) - r995 Special Maintenance - 234 .306 .197 Inservice Inspection 878 1.149 .738 MAB 2888 .099 neg.

i r

(.. .

l 12.4-54 Amendment 39 j I

ATTACHMENT

. . . ST HL-AEJP&

PAGE d OF ff STP FSAR 12.5 HEALTH PHYSICS PROGRAM 12.5.1 Organization-Physics 12.5.1.1 Program Organization. The HL&P health physics organization is called the Health :nd S fety S:rri::): Division and is part of the Nuclear l53 Plant Operations Department. -The health physics programs at STP :: :11 ::

the he21th phyrier pregr r: et ether MLi? f :ilitier are the responsibility.of this division. These programs include _the Radiological Environmental Moni- 38 toring Program (REMP), the dosimetry and operational ALARA programs and the' Radiological Protection Program. Qualifications of plant personnel are 53 described in Chapter 13.1.2.

Ph9 sic s T*'6 "I p** ' 8 ' " ***

The Health :nd Saf ff Serri :: Manager reports to the-Ptene Manager and is responsible for the overall health physics programs.

The Radiological Laboratory Supervisor (RLS) is responsible for the REMP.which includes sample collection, packaging and transportation, processing, counting, data analysis and report generation.

,gesp)Anyony Pao 7ecr;ed pao 64mn Auciv4e.,

The Radiological Protection Supervisor is responsible for implementing thel >

plant (site) health physics program, which encompasses the handling and mon-itoring of radioactive materials, including special nuclear, source, and by-product materials. He is also responsible for assuring that plant opera-tion meets the radiation protection requirements of federaly-aco;m, ad ivuol regulations which are applicable to the health physics program. He reports to l 38 the -RGH 3 (see Figure 13.1-2a and Section 13.1.2) .

Heat.rh Thysics ht nuA 6gn.

Reporting to the plant Radiological Protection Supervisor are the Lead Radia-38 tion Protection Technicians (LRPTs). There are LRPTs on each shift for each unit at the plant. These individuals have the same basic responsibilities as the plant RPS except that they are concerned with only the unit to which they are assigned.

The radiation protection technicians (RPTs) report to the LRPTs and perform the various surveys and analyses for radiation protection. An RPT is provided for each unit on the backshift.

For a more detailed discussion of the responsibilities and authority of the 38 supervisory positions mentioned above, refer to Sections 13.1.2 and 13.1.3.

12.5.1.2 Health Physics Objectives. The objective of health physics is to ensure that exposure from radiation and radioactive materials to personnel onsite is within the guidelines of 10CFR20 and that such exposure is kept as low as is reasonably achievable (ALARA).

12.5.1.3 Health Physics Program. The STP health physics program will be initiated at Unit 1, and later at Unit 2, when radioactive material licensed to HL&P *s first brought into the respective units, and it will-be in effect continuously thereafter until the units are decommissioned. This program con-sists of rules, practices, and procedures which are used to accomplish the ob-jectives stated above in a practical and safe manner. The program follows the guidance provided in RG 8.2. l53 12.5-1 Amendment 53

ATTACHMENT ST HL AE J.7/9

. . STP FSAR PAGE57 0F 75 l

Specifically, the health physics program is governed by the following documents:

e Health Physics Programs - These programs are used to implement Radiation '

Protection philosophy, which affects radiolog'ical safety, and to esta-blish guidelines for the development of Radiation Protection Procedures. 38

' m pLpgr m %b.eA ab,e GmM bem M b. Ibl%.9by5 Ic5 e a aDonProtectionProcedures-Thesecretheproceduresde::1:p:dfer STP : d Other f acilit-ic :: appropriate, b ham g & &_6dW h9y stes pqvam.

The health physics programs will ensure that:

1. Personnel receive appropriate radiation,, protection training.

2. Appropriate access control techniques and protective clothing are used to limit external contamination.

3. A respiratory protection program is developed and respiratory protection ,

equipment is used as required.

4. Radiation areas are segregated and appropriately posted to limit radia-tion exposure.

5. Instruments and equipment are properly calibra.ted so accurate radiation, contamination, and airborne activity surveys can be performed.

6. Appropriate personnel dosimetry devices are supplied.

7. An internal dose-assessment program (whole-body counting and/or bioassay) is supplied.

8. Receipt and shipment of radioactive material are properly handled. l 38 i 9. Necessary measures are performed to keep exposures ALARA.

A more detailed discussion of the procedures used to implement this program is contained in Section 12.5.3.

12.5.2 Equipment, Instrumentation, and Facilities The health physics facilities, equipment, and instrumentation include:

1. An access control facility, health physics offices, personnel decontami-nation rooms, -etere;;c reem, laundry, health physics laboratories, radia-tion protection counting room, calibratio ::: , : d equip; cat decontami- 38 f nation room,a:nd.eppmw& dac4MwwMm % " *fM ey coo .

2. Protective clothing, respiratory protection equipment, air-sampling

~

equipment, and decontamination equipment.

n d. %he. raa..cN:4y

3. FixedandportableradiationAdetectioninstrumentsandpersonnel dosimetry devices. (-

12.5-2 Amendment 38

ATTACHMENT

. ST HL-AE4b9 PAGE5JOF 75 STP FSAR 12.5.2.1 Facilities Related to Health Physics. All fae health physics-related facilities discussed below, with the exception of the cali-7,gg3p 38 bration-stem and the tool and equipment decontamination room, are located at El. 41.0 ft in the Mechanical-Electrical Auxiliaries Building of each unit, as shown on Figure 1.2-28.

The access control complex consists of the LRPTs office, the RPT's office and l38 work area, the -eenerelled cre entrance and exit corridors, change rooms, per-PMEchvC'"sonnel decontamination rooms,+ clothing end-equi; :nt :::::ge roomp, toilet and shower facilities, and locker rooms.

The LRPTs office and the RPTs office and work area are located at the entrance and exit corridors. te th: centr:ll:d arca. Both offices are entered from the 38 clean corridor. The offices contain desks, file cabinets, and storage cabi-nets to support the various health physics activities that normally occur at or near an access control point.

Personnel decontamination facilities, located off the exit corridors, are equipped with showers, sinks, a storage cabinet (for clean clothing, decon- 38 tamination chemicals, and supplies), and a frisker.

Undressing areas for men and women are located in the exit corridors west of the personnel decontamination facilities.

Separate locker rooms, showers, and toilet facilities are provided for men and women.- At the entrance to 22 F :f these facilities is a storage room -where fi<

clean protective clothing and equipment.1: etered. Using the above concept, the individuals would disrobe at their lockers, change into clean protective E*#,g ~

clothing in their respective el__hing rooms, and proceed through the access l38 control point to the jobsite. Adequate lockers have been provided for permanent and contract personnel. There are approximately 380 mens lockers 53 and 40 womens lockers in each unit.

The laundry is located ir th: ::ntrell:d cr:: near the access control-locker room complex to thus minimize the distance that protective clothing must be 38 transported from the change rooms. Both wet and dry cleaning systems will be used to clean protective clothing and a folding and monitoring table are provided. In ddition to clothing,j/bspiratory equipment is cleaned, sani-tized, and repairedj er The. merp!wemy otwiu3 'Reem.

The radiochemistry laboratory is equipped with fume hoods, sinks, and a refrigerator. The counters are provided with electrical, air, gas, vacuum, and water service. The laboratory equipment includes an atomic absorption spectrophotometer (with vent), gas chromatograph, spectrophotometer, pH meter, conductivity meter, drying oven, muffle furnace, centrifuge, and other stan-dard items normally used in a radiochemistry laboratory. The radiochemistry laboratory, along with the radiochemistry counting room, is designed and 38 equipped so necessary radiochemistry analyses can be performed for primary chemistry samples, secondary chemistry samples and station discharge samples.

1 1

A shielded sampling area containing hoods opens into the. radiochemistry j laboratory. Sample lines from various radioactive process streams in the unit 1

l 1

12.5-3 Amendment 53

ATTACHMENT ST-HL AE &/p PAGE JPOF 75 STP FSAR terminate in the hoods. Samples are collected in the hoods and either ana-lyzed there or taken into the radiochemistry laboratory for analysis, thus reducing possible contamination of the general plant due to accidental spil- ~

lage of samples during transportation. -

The radiochemistry counting room is a shielded room containing storage cabi- l38 nets, benches, and sufficient floor space for the various detector shields and radiation detection instruments necessary to analyze the numerous samples. l38 The instruments are discussed in the fixed radiation detection instru- I3 mentation portions of Section 12.5.2.2.

The radiation protection instrument calibration room is located outside the l38 Mechanical-Electrical Auxiliaries Building (MEAB). A shielded instrument calibrator that can provide gamma exposure rates from approximately 2 mR/hr to 500 R/hr is used to calibrate most ranges of the portable gamma and beta-gamma survey instruments listed in the portable instrument section. The dose rate gg%

outside the calibrator is less than 5 mrem /hr. Additional smaller alpha, p.ng beta, and gamma sources can be used as necessary to calibrate or check the ed dh lower ranges of the various portable instruments. A neutron source is used to "EM "

calibrate the neutron-monitoring instrumentsf Dosimeters may be calibrated in this room using the calibrator or other smaller sources, depending upon the l38 range of the dosimeters. The sources used for calibration are traceable to the National Bureau of Standards (NBS) or another standards laboratory.

Normally, radiation protection sources are stored here except for smaller in-strument check sources and laboratory instrument calibration sources, which are usually stored in the general vicinity of the instrument with which they are to be used. Plant radiaoactive sources may also be stored in other ap- l38 proved areas.

For major decontamination of tools and eqt.ipment, a well-equipred decon-tamination room is provided at El. 60.0 ft. The facility contains a double-bowl sink with counter for decontamination of small hand tools. For larger tools and medium-size valves , -mops-sinks are provided. For larger valves and pieces of equipment, 48-in.-deep [tanksareprovided.

I swu *3)

An ultrasonic cleaner is provided to obtain the agitation necessary for various chemicals to remove the radioactive corrosion products. -A-

-high-pressure-spray-booth--that-can b^ used-with-high-pressure-wat+r-sprey-or,

-steam is used to remove-loose-crud-and/or-oi1- Eiims-from-these items,- For-

-cleaning-and-disassembly, a large-stainless-steel-pan-with-a 64n -curb-is-provided. The facility is served by a monorail to aid in moving large pieces of equipment. Items are kept wet, or enclosures and ventilation systems are used, to prevent or remove airborne activity during decontamination. -Chapter-

-7A . I II . D-h-3-desc ribe s-HL&Ps-compl-iance-wi th-NUREG-0737 , -Item-IIhDrb-h 53 12.5.2.2 Radiation Protection Instrumentation. The instrumentation used by radiation protection personnel can be divided into five categories: fixed l38 radiation-counting instruments (laboratory type), portable radiation detection instruments, personnel-monitoring instruments, area radiation monitoring in-struments, and airborne radiation sampling and monitoring instruments. In-strumentation is normally repaired by the Instrumentation and Control (I&C) groups or by vendors. Maintenance may be performed in place (for fixed in-struments), in the I6C facilities, or at the vendor facilities, if necessary.

12.5-4 Amendment 53

)

ATTACFHAENT

- ST.HL-AE. 4:u9

. . PAGE 400F 7f STP FSAR

1. Fixed Radiation-Counting Instrumentation The bulk of the fixed radiation-counting equipment, which can be used for analysis of various air, water, and smear samples, will be located in the 38 radiation protection counting room of each unit. One or more beta counters may be used at the access control point or elsewhere for such things as counting smears to determine contamination levels of floors, tools, and equipment.

The criteria for selection of these various counters were that they could provide the necessary low backgrounds and sensitivities required by NRC RG 1.21, the plant operating and environmental technical specifications, or good operating practice.

These instruments are calibrated with laboratory standards prepared from mate- l38 rials traceable to NBS or other recognized standards laboratories. The stan-dards are counted in various geometries and/or sample positions that normally are used to count the different types of plant samples.

The laboratory counting equipment available in.each unit may change period-ically since improvements or new types of equipment may become available or plant requirements may change. The counting equipment in each unit will be utilized to perform the following types of analysis:

a. Isotopic identification and analysis on air samples and water samples. 38

b. Personnel protection level alpha and beta determination on air samples, water samples, and smears.

c. Low-energy beta analysis.

d. Gross beta counting for smears and air samples.

This equipment in the counting rooms includes:

1 Beta detector in either the counting room or access control point, 1 Gamma spectrometer (intrinsic germanium), and, 53 1 Alpha, Beta detector for low background counting.

This is in addition to e44 the offsite environmental counting equipment.

2. Portable Radiation Detection Instrumentation The portable radiation detection instruments include all portable instruments used to perform alpha, beta, gamma, or neutron surveys for radiation or con- l38 tamination control.

The criteria for selection of these instruments are that they be rugged, ac-curate, reliable, and easily serviced, and that they will cover the entire spectrum of radiation measurements expected to be made at the plant during normal operation, shutdowns, and accident conditions.

I 12.5-5 Amendment 53

ATTACHMENT ST HL AE 42/9 STP'FSAR PAGE 4/ OF 75 lhuwl These' instruments are properly calibrated, when in use. The calibration nor- l38 r mally is performed in the calibration-coedusing the calibrator (previously 4_2 idiscussed in Section 12.5.2.1) and/or other smaller sources. Prior to use, l38' the instrument response is' checked with an internal or external source to ver-ify that the instrument is functioning propetrIy.

Sufficient quantities of each type of instrument will be obtained to permit calibration, maintenance, and repair without diminishing the radiation protection supplied. The types of portable survey instruments, planned for STP include: (1) portable count rate survey meters; (2) ion chambers; (3) high-range gamma dose rate meters; (4) neutron dose rate meters; and (5) alpha survey meters. These may be changed since improvements in instruments may occur or plant requirements may change.

3. Personnel-Monitoring Instruments (and Services)

Personnel-monitoring instrumentation is provided to measure the radiation dose received by personnel and to determine external and internal contamination levels . { Phy.u.s }

The goal in' selecting' dose-measuring devices-was to.have one (thermo-lu-minescen dosimeter (TLD)] that could be wichl; and accurately evaluated by .

Health ...._ ___.., _ .... ...._ .. or other personnel and another type (di- 38 rect-reading dosimeter) that could be read easily by the individual. The goal in selecting external personnel contamination-measuring equipment was to have devices (friskers) available at checkpoints and other areas that could be used to determine the location of contamination, and to have devices (portal mon-itors) at all normal exits from the ::ntrolled area that do not require any t

action by personnel being checked .The goal in selecting the whole-body "

counting system was to have a s tem readily available which could p'M iy supply information concerning ersonnel internal contamination levels.

l*WI The personnel monitoring devices utilized will be obtained in sufficient quantities to permit calibration,. maintenance and repair without diminishing.

the radiation protection supplied. Quantities may fluctuate as plant needs are determined. The. type of personnel monitoring devices to be utilized are as follows:

a. Friskers and portal monitors for detection of external contamination. 38

b. Direct-reading dosimeters of various ranges for daily exposure control. ,

c. TLD badges to determine whole body doses and extremity doses.

d. Equipment necessary to support the external dose control' program,

e. Wholebodycountersandexcretfcontainersrequiredtosupporta bioassay program.

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4. Area Radiation Monitoring System The Area Radiation Monitoring System detectors were installed in areas where the radiation level could change significantly and/or which have a high oc-cupancy rate. The system reads out and alarms locally as well as in the con-trol room. For more details see Section 12.3.4.

l3

5. Air Sampling and Monitoring Instrumentation Air sampling and monitoring instrumentation is used to determine the levels of radioactivity in airborne effluents and to determine the levels of radioactiv-ity in plant areas where personnel are likely to be exposed. h/, g%

The decisions reached in selecting the farious types of equipment are:

e To install fixed constant air monitors (CAMS) on the effluent paths with alarms in the control room so that automatic or operator action could be used to immediately 4^ r::t abnormal situations.

StesPohd To e To install fixed CAMS,.for in-plant determinations, in areas where airborne activity was expected to occur or where it had to be determined during an emergency.

e To use portable CAMS, for in-plant determinations, to monitor critical work areas where airborne activity levels are likely to be high.

e To use portable air samplers for evaluation of airborne activity at some job sites during maintenance and throughout the unit during normal oper-ation (to establish normal levels).

The monitors, including the portable CAMS which are used for locations not covered by the RMS air monitors or to supplement the monitoring by the RMS, l6t are calibrated every 18 months using appropriate sources. Portable air sample 57 flowrates are also checked and adjusted, as necessary, at least quarterly. l6(

Typical air sampling and monitoring instrumentation is listed.below.

a. Fixed and nortable CAMS, which are part of the Radiation Monitoring 38 A#g System (RMS),4used to monitor the normally accessible portions of the rent Mlled ::: . These CAMS sample the ventilation ducts from pgg gu/ Ac6 various areas to determine particulate, iodine, or gaseous activity (or combinations thereof) depending upon the equipment and sources of airborne activity located in the area. They read out and alarm in the control room. For more information on the system, see Section 12.3.4.

b. Portable CAMS can be relocated to monitor room air for special conditions, to monitor locations not covered by. the RMS air mon-itors, or to supplement the monitoring of the RMS. 38

c. High-volume variable-flow air samplers, which can be used to sample j for particulate and iodine activity. They can be used to obtain '

quick grab samples at the beginning of a job or during activities that could significantly increase the airborne activity level.

Section 7. A.117. 2. 3. B des enibes ML iPs conpliuct with NUREW 0737,

.T ren H . 'h . 3.3.

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d. Constant-flow, low-volume air samplers, which can be.used to sample (

for particulate and iodine activity. These units can be used to ,

evaluate airborne activity over a long period of time. -

l 12.5.2.3 Radiation' Protection Equipment. Equipment is supplied for the l protection of personnel as discussed in the following sections.

1. Respiratory Protection Equipment -

The types of respiratory protection equipment to be,provided are listed below.

All respiratory equipment will meet the requirem,ents of ANSI Z88.2-1969 and will have. National Institute of Occupational Safety and Health (NIOSH) approv-al for use in atmospheres containing radioactive materials.

a. Pressure / demand, full-facepiece SCBAs.

.,4cas e -Nw

b. Pressure /demanjaAfull-facepieceairlinemasks.

c. Full-facepiece filter masks.

d. -Two-piece,h$asticsuitswithconstantairflow.

i e. A respirato fitting test booth which uses sodium chlcrid : 38 44hes approved particulate aerosols.

d 2. Protective Clothing Various types of protective clothing are stocked at the plant to protect against contamination. Typical clothing includes:

a. Body Protection Lab coats Coveralls Plastic suits

b. Head Protection Surgeons caps Cloth hoods Plastic hoods

c. Hand Protection Disposable gloves Surgeons' gloves Rubber gloves Gauntlet gloves Glove liners

d. Foot Protection Plastic shoe covers Cloth boot covers -

Rubber overshoes Boots 1

L

~_-

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3. Contamination Control Equipment Contamination control equipment is used to prevent or limit the spread of radioactive contamination and to assist in its removal. The equipment is stored et th: :: tr:1 ;: int: : d in or near echee-areas where it is usually used (such as the decontamination areas). The equipment may include such 38 items as:

A floor scrubbing machine Vacuum cleaners with absolute filters Mops and wringer buckets Polyethylene sheeting

~ Rolls of absorbent paper Plastic bags of assorted sizes l

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Faching tape Barricade posts with magenta- and yellow-colored rope Radiation and contamination signs 12.5.3 Procedures Strict adherence to the plant radiation protection procedures will ensure that l 38 personnel radiation exposures are within the limits of 10CFR20 and are ALARA.

A discussion of the procedures implemented to minimize personnel exposures is provided in Section 13.5.

Policy and operational considerations for radiation protection are set forth in Sections 12.1.1 and 12.1.3. A general-discussion of radiation protection practices to be followed is given in this section.

12.5.3.1 Radiation and Contamination Surveys. Health physics personnel perform routine radiation and contamination surveys of all accessible areas of the plant. Survey areas and frequencies are determined in accordance with plant radiation protection procedures and are based upon the probability of l 38 contamination and radiation levels changing and upon personnel occupancy.

These surveys consist of radiation measurements and/or smears as appropriate

/4AB Rc84*df4Bf r the specific area. Air samples also are routinely taken in normally cessible portions of the cen:#'Iled ran using long-term (low volume) air samplers. This information is supplementary to that continuously obtained by the fixed CAMS which read out in the control room, as discussed in Section 12.5.2.2. Additional surveys related to specific operations and maintenance activities are performed. These surveys, performed prior to, during, or after the activity, or any combination thereof, are based upon the necessity for obtaining information required for protection of personnel and the necessity for keeping exposures (including those of health physics personnel) ALARA.

Short-term (high volume) air samplers usually are used for evaluation of airborne activity prior to a job or during specific phases, while CAMS or long-term air samplers usually are used for determinations for the duration'of a j ob .

12.5.3.2 Procedures and Methods to Maintain Exposures ALARA.

Procedures and methods to maintain exposures ALARA are not exclusively health physics procedures but include many operating and maintenance procedures.

Examples of the various types of procedures and methods that are to maintain exposures ALARA for various operational categories are discussed below.

l

1. Improved refueling Many of the improved refueling features of the Westinghouse Electric Corporation (Westinghouse) design can considerably reduce the time required to perform refueling operations. These features include a Pressure Vessel Head Closure System, cable tray, and one-lift concept, in which the missile shield, l reactor vessel head, Control Rod Drive Mechanism Cooling System, and lifting rig may be removed as a single unit. l 38 The Pressure Vessel Head Closure System is designed to reduce the time required to tension and detension the reactor vessel studs and to remove and 1

Amendment 38 12.5-9

ATTACHMENT ST-HL-AE J#9 STP FSAR PAGE 4 OF 75 insert the studs into the vessel flange. The system includes quick discon- ,

nect/ connect stud tensioners which have split, quick-acting, stud gripper '

devices to eliminate the need for threading tensioners onto the studs. The system also includes pneumatic tools for remoyJng/ inserting studs into the vessel flange. 'I~

A cable tray permits easy disconnect / connect and convenient storage of elec-trical cable when the reactor vessel head is removed, thereby reducing the time spent in making and verifying electrical connections following refueling.

These developments will significantly reduce personnel exposure during 38 refueling operations.

2. Inservice Inspection Another example of a method for reducing exposures is the use of remote exami-nation equipment. A remote controlled examination tool will be employed for 38 examining the reactor vessel welds. This tool is inserted in the open reactor vessel after removal of the fuel and reactor vessel internals. The refueling cavity is flooded with water so that the operators are shielded by about 30 ft l38 of water.

Before entering radiation areas to perform inspections, personn'le will ac-quaint themselves with the job location, the work to be done, and the radia-tion and contamination levels which may be experienced. Surveys are performed to the extent required to determine present contamination and/or radiation levels. From this data, and the past experience of personnel, a radiation work. permit is issued.dete444ng the neccc ary ::ps required te k :p : pecure >

ALARA.-

3. Radwaste Handling The handling of radwaste has been minimized by the design of the filters and the relationship of the filters and demineralizers to the radwaste facility.

Used filters can be transferred easily via monorail to a shipping container in the radwaste area, and used resins can be sluiced remotely to a shielded stor-age tank and after processing to shipping containers. Evaporator bottoms can be mixed remotely with a solidification agent.

4. Spent Fuel Handling, Loading and Shipping All spent fuel handling is performed underwater using fuel-handling cranes and/or manual tools. The same equipment is used to load the fuel into the 38 spent fuel shipping cask.

The handling, loading, and shipping of spent fuel normally requires that a small crew of personnel work in the Fuel-Handling Building a few days during 4 the year and usually involves little exposure. Some of the methods used to Q331.

assure that radiation exposures are ALARA are: 9

a. At least 10 ft of water is maintained above the fuel assembly in l4 the pools to minimize direct radiation.

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b. The fuel pool water is purified to minimize exposure due to water

. activity. .

c. The fuel pool water is cooled.to minimize inhalation doses.

d. Continuous air sampling is provided while moving fuel to evaluate airborne activity._ >

. Written procedures are provided for fuel handling operations.

5. Normal Operation The plant has been designed.so significant radiation sources are separately-shielded or located in cubicles. Much of the instrumentation required for

. 4' normal operation reads out remotely in the control room or outside the cubi-cles in corridors. Instrumentation which cannot be located remotely, or is read infrequently is situated where possible so.it can be read from the en-trance to the cubicle or from a low-radiation area within the cubicle. Survey meters and audible dosimeters are available for use to assist in minimizing exposures.

6. Routine Maintenance Routine maintenance includes preventive mainte' nance (planned and scheduled maintenance such as lubrication, adjustments, and tests) and corrective maintenance (unscheduled maintenance such as valve packing, pump set.1 4 s; replacement,'and stopping-leaks)r -Procedures are written for the usual preventive maintenance jobs and for some recurring corrective maintenance jobs.- "'he:2 pre :dare sp :ify the p:::: ti;;: : be tch:2 in::dr::

int:in p::::..r. 1 ;;pecure: AI. ARA.

Where applicable, the preventive maintenance procedures also list the required lubricants, special tools, and equipment and the acceptance criteria. In ad-dition, the initiating mechanism for these procedures identifies if a radia-tion work permit is normally required.--When an RWP is issued, the radiation

, and/or contamination levels are listed, shielding requirements are stated, and 4 additional specific instructions are given, where applicable.

l For corrective maintenance jobs in radiation areas, a similar approach is used. Normally, maintenance personnel will determine what has to be done, and plant radiation protection personnel will survey the radiation level in the !30

! work area. Based upon these determinations, the required tools and equipment are assembled and an RWP is requested.- Detailed surveys are performed, and the radiation work permit is issued.with-[pecific instruction manuals,er a , 4 5: ch:r pictures or3 sketches -eMe-id them in understanding what is to be ac-complished and how it is to be accomplished ;;d h;; it i: te h; e ;m ,,11ehed ,

as safely and quickly as possible. Additional requirements and techniques are listed below. 4

a. Workinhighradiationareas,wherewhole-bodydosesareexpectedgo 38 exceed 1002 mrem r where removable contamination levels exceed 10 dpm/100 cm ,will be preplanned. The purpose of the preplanning is 14 12.5-11 Amendment 38 a

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.k. -On jobs with exceptionally high radiation levels, a timekeeper who .

knows the exposure rate of the radiation field will keep track of the total time in the radiation field, using a stopwatch or similar device. I l

On major maintenance jobs, especially those that involve high radi-1.

ation levels, the job preplanning will include estimates of the PEAS *N -> aen-rem needed to complete the job. At the completion of the job, a debriefing session will be held with the people who actually 4 performed the work in an effort to determine how the work could Q331.

have been completed more efficiently, resulting in less exposure. 9 This information, together with the procedures used and actual man-rem expended, will be filed. The radiation, contamination, and airborne activity levels determined during the work will be filed.

In addition, if any external body contamination or internal contam-ination was encountered during the job, this information will be filed to provide guidance at the preplanning stage of future similar operations.

7. Sampling Most sampling of radioactive systems is performed inside the hoods in the radiochemistry lab to protect personnel from airborne activity. Protective clothing and gloves are required when sampling radioactive systems to prevent contamination of personnel. A portable radiation survey instrument 'is avail-able to check radiation levels while sampling and to determine the level of the sample container. The liquid sampler container normally is washed off with clean water and dried before being taken from the hood for analysis.

8. Calibration ,

l Calibration of most ranges of the portable gamma detection instruments is performed inside a shielded calibrator, thus almost eliminating exposure. I Portable sources used to calibrate fixed instruments are transported in l shielded containers, l Nonradioactive calibration of instrumentsp "'ich ir perfer ed 5-; the Inctru ent --d Oe-tr^1 ca-*4aa may be performed in the shop or in place. l 38 Where possible, instruments requiring routine calibration are placed in hallways where the radiation level is low, and the necessary valves and/or electrical connections are provided so the instrument can be calibrated in place,

__ 12.5.3.3 PR$fE'rtj,, _ Portions _ Controlling of the Access and Stay Time in Restricted Areas.

rTbtricted area are categorized as radiation areas, high-radiation areas, airborne radioactivity areas, and radioactive materials areas to comply with 10CFR20. [3 PReTie120 During its construction, Unit 2 will be# separated by a fence from Unit 1 so construction workers cannot enter the $4tricted area of Unit 1. This will alleviate the need to badge personnel at Unit 2 during construction. TLD badges situuted on the fence or in the work area will be used to verify that the radiation exposure of the Unit 2 construction force is minimal.

12.5-13 Amendment 38

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ATTACHMEfLT ST HL AE M

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pedu54 Personnel entering the rectricted areas of the plant must e knowledgeable in health physics, must receive training in this area as spec fied in Section 12.5.3.8, or must be escorted. Entrance to the :: tricted cree for Unit 1 and l 3 later for Unit 2 normally is through the respect;ive access control points (previously discussed in Section 12.5.2), where a RWP nay be issued, if l3 required, for the area to be entered. Additional monitoring devices, protective clothing, and respiratory equipment also may be issued here if required.

Radiation and high-radiation areas are segregated and identified in accordance 38 with 10CFR20.203 and the Technical Specifications.

Additional control over entries is provided by using RWPs. Entrance to ucu, %g high -radiation areas and ;^tenance verk in radiation areas requiresan RWPy pest.

AcopyofthepermitisY at the :ntrance :: the verk :::f. Operators cntering these areas normally are covered by a separate RWP to enable them to perform their routine duties.

RWPs describe the work to be performed and the radiological controls necessary 38 to perform the work safely. Each RWP states such information pertinent to the job as radiation and/or contamination levels in the work area, allowable stay times and/or dose rates, areas with lowest dose rates, protective clothing required, respiratory equipment required, any special personnel-monitoring devices required, and any temporary shielding requirements. It may also state special sampling requirements,(such as an cxplosisater check prior to-welding),- special tools and equipment. required, and other cautions or notes.

Notes specifying continuous radiation protection coverage, a timekeeper, or requirements for a debriefing session may also be added. All such permits require the approval of the titPT%- designee. In addition appropriate admin-istrative controls will be used to inform operations personnel of RWP use and 38 status.

12.5.3.4 Contamination Control. Contamination limits for personnel, equipment, and areas are listed in the plant procedures. Surveys are par-formed routinely, as= discussed in Section 12.5.3.1, to determine contami-nation levels. Additional surveys may be performed after maintenance work or after an operation which may have increaned contamination levels. Any area found contaminated is roped off or otherwise delineated with a physical bar-rier, then posted with appropriate signs, and decontaminat%8n-as soon as prac-tical. In areas where the radiation level is high or where it is considered impractical to decontaminate the area to general controlled area limits, a step-off pad is used to prevent the spread of contamination. It is intended ,

that the housekeeping practices that have proved successful at many other l plants will be used for operation of this plant. I Tools and equipment used in contaminated areas of the controlled area are mon-itored and/or bagged (or wrapped) prior to being removed from the job site to prevent the spread of contamination. All tools and equipment being removed from the centrolled*arca are monitored for. contamination by radiation. l MAB,FRB,adRCBl protection personnel (or other qualified personnel) to see that they meet clean area limits. If the tools or equipment do not meet the limits,=they are dscontaminated. Decontamination facilities have been discussed previously in Szetion 12.5.2.

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Gme .

-Regulated tools .and equipment are in dich, because of their design or use,

.are not considered practical:to decontaminate. These tools and equipment are

~

marked and.are<used only in the restricted area by workers wearing appropriate protective clothing 3emL%ger getably p,ashA. art.as.

Iaw g we=A g'ci. h W )

' Control of personnel contaminatio (external and internal) is provided by using the protective. clothing respiratory equipment previously discussed

-in Section 12.5.2. . Each ind idual is responsible-for monitoring himself and his clothing when crossing a local control point or the main access control.

points, which have been discussed previously in Section 12.5.2. If contam-ination is found, the individual is decontaminated.-using one of the facili .

ties previously described in Section 12.5.2, under the direction of health-physics personnel.

Decontamination through the use of the equipment listed in Section 12.5.2 may 38 be aided by_special coatings that are applied to the walls and floors of areas containing radioactive fluids and by a system of floor drains.

In addition, equipment vents and drains are piped directly to sumps or.other collection devices to' prevent radioactive fluids from flowing across the-floor to the drains.

12.5.3.5 Airborne Activity Control. The plant Ventilation Systems-(see >

Sections 9.4 and 12.3.3) provide a means of purging areas of the Reactor Containment to minimize the accumulation of airborne radioactive materials.

Airflow is directed from normally occupied or routinely accessible areas of l 38

_ low-potential-contamination to areas of higher potential contamination.

Airborne contamination is minimized by keeping loose contamination levels low and by reducing sources of leakage as much as practical. ~The ventilation airflow prevents the buildup of air contamination concentrations.

For jobs that significantly increase airborne activity, auxiliary ventilation I is used where feasible. In some cases, flexible ducts may be connected to the normal exhaust system and then positioned to remove-the contaminated air from the work area.- In other cases, a mobile system - consisting of a blower, banks of filters to remove the activity, and flexible ductwork to connect to the work area - may be used. The mobile unit can be used to recycle the air -

or to discharge into the normal ventilation system.

If personnel entry is required into areas where the source of airborne radio-activity cannot be removed of controlle~d, occupancy is restricted and/or respiratory protection equipment is provided to maintain exposures within the-limits of 10CFR20.103. When airborne radioactivity is detected in excess of- g the limits in 10CFR20.103, the area is posted as an " Airborne Radioactivity Area" and access is cont:illed. Entry into these areas requires-the issuance of an RWP (previously discussed in Section 12.5.3.3), which provides radiation-exposure control by controlling and recording conditions under which work in airborne radiation areas is performed. Air-sampling techniques are used to ensure that appropriate respiratory protective equipment is specified on the RWP. Selection of the appropriate type of respiratory' equipment is then determined. The respiratory protection program is organized to conform to RG i.

8.15 in an effort to ensure the effectiveness of respiratory equipment.

Whole-body counting, bioassay analysis,3 nasal smears, :: f;;; piece--interier i- ameeee-may be performed to evaluate the protection afforded.

i l \ dhd i

12.5-15 Amendment 38 .

L___ _ _. ___ __ _ _ , _ _ _ . . _. . _m, _ __._ _, _

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! ATTACHMENT

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ST-HL AE. 2.2 /f STP FSAR PAGE1/ OF T The major portion of the respiratory equipment .(previously discussed in '

38 Section 12.5.2) is available for entry at the main access control point.

Supplementary emergency respiratory equipment is available in the control room cnd emergency kits.

The RPS is responsible for administration of the respiratory protection l 38 program at the plant. To ensure an adequate program, the following controls are incorporated in the program:

1. Procedures are established to ensure adequate personnel training in the correct fitting, use, maintenance, and cleaning of the various types of respiratory equipment. ,

2. Respirator users are evaluated by medical personnel to ensure that they are physically and mentally able to wear respirators under actual working conditions.

3. Each respirator user is fitted in a respirator fitting test booth under simulated conditions to verify that the types of respirators to be worn under actual work conditions will fit the face properly.

4. Sufficient air samples and surveys are made to identify the various forms and types of nuclides present and to estimate the individual exposures so that selection of appropriate respiratory equipment can be made, gemove. his REspiR AnR. AHd _

5. Each respirator user is advised that he m M eave $ airborne radioh^ #

activity area for psychological or physical relief from respirator use.

Each user must leave the area in the case of respirator malfunction or any other condition that might cause reduction in the protection afforded.

EggACTA *ANAlyS55

6. Bioassaysbysurinilycerorwhole-bodycountsofindividualswillbemade as required to evaluate individual body burdens of radioactivity and to assess the overall effectiveness of the respiratory protection program, as discussed in Section 12.5.3.6.

12.5.3.6 Personnel Monitoring. Plant employees, contractors, support personnel, and visitors are required to wear a direct-reading dosimeter and/or -posrtd a beta-gamma-sensitive TLD when in a reetricY94 area. However, this require-ment may be waived, such as for a group of visitors, if they stay together and are escorted by an individual who is wearing a direct-reading dosimeter. The dosimeter result is interpreted as the dose received by the group.

Direct-reading dosimeters are read and recorded daily (when used). TLDs are l 38 processed monthly and more frequently if necessary, such as during a refu-eling, a maintenance outage, or when an individual's exposure status is in doubt. Dosimeter and TLD badge readings will be recorded. --

It is not expected that the neutron dose-vill exceed 300 mrem.per--quarter; therefore, a calculated neutron dose equivalent measured _with portable mon- 4_jUd Y itoring instruments and known occupancy times + ebb # be used in place of neutron Q331.

dosimeters. In the event that such operating data indicates the neutron dose 10 equivalent does not exceed 30 mrem per quarter, the calculated neutron dose equivalent will be assumed equal to zero.

(

17.5-16 Amendment 18

l ATTACHMENT

! ST HL-AE-o74/9 STP FSAR i oAGE $ OF7f Bioassay (usually for tritium evaluation) and/or whole-body counting vill be performed as necessary. The type of determination and the frequency of per-forming the determination depends upon the work environment of the individual under consideration and the present work situation at the' plant. It is, in-tended that each member of the permanent plant organization who works in the restricted area vill receive a whole-body count at least once each year.

Exposure data of all personnel will be collected and recorded on NRC Form 5,

" Current Occupational External Radiation Exposure," or the equivalent. Oc-cupational exposures incurred by individuals prior to working at STP, bierrecy Aca, and whole-body counting data vill be summarized on NRC Form 4,

" Occupational External Radiation Exposure History," or the equivalent. These records will be maintained and will be preserved indefinitely or until the NRC authorizes their disposal pursuant to Paragraph 20.401 of 10CFR20. Reports of overexposure to radiation workers will be made to the NRC and to the individual involved pursuant to 10CFR20.405 f ,*u 4ec.sa dAuee wM PLd" ?"**'dC'

12.5.3.7 Radioactive Materials Safety Program. The health physics program is designed to control personnel radiation exposure from the normal by-product, source, and special nuclear material directly associated with the power production aspects of the plant. The various types of sealed and un-sealed sources used for calibration are normally used under the direction of l38 personnel listed on NRC 2nd/cr Stat: ef Tcrec radioactive materials licenses.

These individuals have received training in the safe use and handling of sources as part of their normal training.

The sources involved are used to calibrate the process and effluent radiation 3 monitors described in Section 11.5, the area radiation monitors described in Section 12.3.4, and the portable and laboratory radiation detection instru-ments described in Section 12.5.2. Check sources that are integral to the monitors or portable instruments, and that are exempt quantities, do not require special handling, storage, or use procedures for radiation protection.

This also applies to exempt quantities of sources used to calibrate or check laboratory instruments.

Recognized methods for the safe handling of radioactive materials (especially unsealed sources), such as those recommended by the National Council on Radiation Protection and Measurement, will be implemented, where applicable, to maintain potential external and internal dose / at levels that are ALARA.

External doses will be minimized by a combination of time, distance, and shielding considerations. Internal doses will be minimized by the measurement and control of loose contamination. The handling of licensed material will be addressed in the plant health physics procedures. ,

1 NSERT44 1

[Sealedradionuclidesourceshavingactivitiesgreaterthanthequantitiesof\

radionuclides defined in Appendix C to 10CFR20 and Schedule B_of 10CFR30 will be subject to material controls for radiological protection. Those controls '

[ will include:

~

1. Monitoring of all packages containing radioactive materials for external dose rate and removable contamination immediately upon receipt at the plant and immediately prior to shipment away from the plant. If incoming packages are found to have removable surface contamination, the transport vehicle also will be monitored, if feasible.

12.5-17 Amendment 38 i l

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ATTACHMENT ST HL AE 3219 AGE 93 OF 95' Insert for p. 12.5-17 Sealed radionuclide sources, except quantities less than those specified in 10CFR20.203(e) as requiring posting as radioactive materials or items specifically exempted or generally licensed under the provisions of 10CFR30 through 10CFR35, will be subject to material controls for radiological protection. Those controls will include:

l

,/^

r ATTACHMENT l ST HL AE #A/f STP FSAR l PAGE 79 OF '75

2. Monitoring of each source for removable surface contamination (leakage -

testing) at 6-month intervals. Excluded are inaccessible sources (such as startup sources in the reactor) and sealed sources containing 100p Ci or less beta and/or g d emitting materials and .16p Ci or 4%ge of alpha-emitting materials. # LESS

3. Labeling of each source with the radiation symbol, stating the activity, radionuclide, and source identification number.

of EMh sosunce a ,a

4. Storag? in a locked area ef ecch ceurce th2t ic not in use or installed in an instrument or other piece of equipment.

5.

Inventory of all sources every 6 months. -

12.5.3.8 Health Physics Training. As part of the general employee training, each member of the permanent operating organization whose duties F1578dTntail entering cent 9:lled areas, or directing the activities of others who

- enter ec 4r:11:d areas, will be instructed in the fundamentals of health phys ,posys/

ics. They must pass an exam to be allowed to enter the cc : :11 d area unes-corted. These same personnel will also be required to attend a retraining program in health physics at least annually. Personnel whose duties -e4*noth do require entering e h i d areas e will be made aware of reasons for keeping out of these areas.

An outline of the general employee training in health physics is listed in Section 13.2. The training program incicdes instructions in applicable ,

provisions of the NRC regulations for the protection of personnel from radi-ation and radioactive material (10CFR20) and instruction to women concerning prenatal radiation exposure.

Additional training and testing is given to, personnel training for reactor operator or senior reactor operator license 7 to meet the requirements of 10CFR55. Their training is discussed in Section 13.2.

In addition to the above training, chemistry and radiation protection tech-nicians receive training in areas that apply to their specific job function such as radiation and contamination surveys, air-sampling techniques, use of portable and laboratory instrumentation, release limits, and safe handling of sources. For details, see Section 13.2.

12.5-18 Amendment 38 A

ATTACHMENT f.

+* *0

- ST-HL-AE-R2/9 i

PAGE 1SOF 75 STP FSAR 4

Table 12.5-1 RADIATION MONITORING INSTRUMENTATION The approximate quantity, sensitivity, and range of typical survey instruments, TLDs, and self-reading dosimeters are shown below:

SURVEY INSTRUMENTS:

Quantity (Approximate) Type of Radiation Range (typical)

Detected 20 per unit Beta, Gamma -

1(Radto5,000(Rad /hr 5 per unit Beta, Gamma 10m Rad to 50,000f( Rad /hr 2 per unit Gamma 0.1 to 1000 R/hr 1 Neutron inCRem to 5 Rem /hr 1 each unit Alpha 100 dpm to 20,000 dpm-TLDs:

Quantity (Approximate) Type of Radiation Range (typical)

Detected 2500 per unit Beta, Gamma 10(REMto1000 Rem

% Rect

, M -READING DOSIMETERS:

Quantity (Approximate) Type of Radiation Range (typical)

Detected 1000 per unit Gamma 0-200m[ Rem 100 per unit Gamma 0-1R 10 per unit Gamma 0 - 20 R SPECIAL INSTRUMENTATION:

Quantity (Approximate) Type of Radiation Range (typical)

Detected 1 per unic Gamma 1R/hr to 10,000 R/hr 12.5-19 Amendment 53 1

ST-HL-AE-2219, Forwards Annotated Rev to FSAR Chapter 12, Radiation Protection, Reflecting Personnel Organization,Corrections, Clarifications & Editorial Changes.Rev Will Be Incorporated Into Future FSAR Amend

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