ML20150E379
| ML20150E379 | |
| Person / Time | |
|---|---|
| Site: | 07003054 |
| Issue date: | 06/17/1988 |
| From: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20150E368 | List: |
| References | |
| NUDOCS 8807150104 | |
| Download: ML20150E379 (79) | |
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L BEFCRE TFE UNITED STATES NUCLEAR REGULATCRY CCf44ISSION IN THE MATTER CF DOCKET NO.
70-3054 PHILADELPHI A ELECTRIC CCl4PANY :
l APPLICATICN FOR AVENCMENT OF MATERIAL LICENSE NO. SNM 1977 FCR LIMERICK GENERATING STATION LilIT NC.
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j Edward G. Bauer, Jr.
Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania Attorneys for Philadelphia Electric Ccmpany L
BEFORE TFE UNITED STATES NUCLEAR REGULATORY CCttilSSION IN THE MATTER OF DOCKET NO.
70-3054 PHILA0ELPHIA ELECTRIC CCPPAt#:
APPLICATION FOR AMENDVENT CF PATERIAL LICENSE FC.
SMi 1977 FCR LIMERICK GENERATING STATION UNIT NO.
2 On Decenter 17, 1987, the U.S. Nuclear Regulatory Cormission (NRC)
Issued to Philadolphia Electric Ccrnpany-("Applicant") 14aterials License Stt4-1977 which authorizes Applicant to receive, acquire, possess, transfer and use certain speclat nuclear traterial contained in instninentatten to be used at Limerick, Unit 2.
Based ucon current schedules, Appilcant anticipates being ready to receive the first fuel assemblies for the Initial core of Limerick, Unit 2 at the facility in Decente r, 1988.
Additionally, Appilcant wishes to conform the Inventory requirerrents of Condition 14 of License SMi-1977 to the present inventory schedule currently in effect at Limerick Unit 1.
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i Accordingly Applicant hereby requests that Materials License SNM-1977 j
be amended:
1) to authorize Appilcant to receive, acquire, possess, store and deliver to a carrier for transport certain special nuclear material contained in fuel assenbiles for i
Appilcants' Limerick Unit 2; and t
2) to revise Conditicn 14 of the License to provide that a physical Inventory shall be conducted annually to account for all sources and/or devices received and possessed under the license. Since the first inventory under present Ccndition 14 would be required by June 17, 1988, it is recuested that action on this recuest be taken by NRC prior to that date; and l.I
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3) to revise and update the resunes cf the Health Physicists i:
presented in Sectlen 2.1.3 (Figures 2.1.3-1 thru 2.1.3-35) to reflect prortctions and Jcb title changes at Limerick Generating Station.
In su: port of this Application for Arendment, Appilcant provides the l
Infonration set forth below. New information or Information provided l
In the Octcber 26, 1987 Appilcation which has been revised is Indicated by a bar in the right margin. A specific discussion of the basis fcr the recuested change to Condition 14 of the license is I
provided in Section 1.4.2.
1.0 General Infermation
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Applicant is a corporatten organt:ed under the laws of the Commenwealth of Pennsylvanta with its principal place of business at 2301 Market Street, Philadelphia, Pennsylvania 19101.
Philadelphla Electric Coreany is not oaned, controlled, or i
dominated by an allen, foreign corporation, or a' foreign i
gove rnrent. A list of Appilcant's officers, all of whom are l
citizens of the United States, is marked Exhibit 1.0, attached hereto, and incorporated herein. Appilcation is hereby made pursuant to Section 70.22 of the Cannission's Regulations for a license authori:Ing Appilcant to receive, possess, store, use and deliver to a carrier for shipment certain special nuclear material h
I contained in fuel assemblies at the Applicant's Limerick j
i Generating Station Unit 2.
The license is requested until Issuance of an cperating Ilcense for Limerick Unit 2.
The first fuel assemblies for the Initial core are anticipated to arrive on site in December 1988, t
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, 1.1 Reactor and Fuel 1.1.1 Reactor Location The Limerick Generating Station Unit 2 is presently under construction on a site located in Limerick Tovnship, Mcntgomery County, Pennsylvania approximately 25 miles vest of Philadelphla, Pennsylvania. The ccmpany currently evns and operates Lirerick Unit 1 on this site pursuant to NRC Operating License NPF-39.
Construction of the Limerick Gererating Station Unit 2 was authorized by the Atomic Energy Ccmnission in Construction Penmit CPPR-107 Issued on June 19, 1974 (Docket No.
50-353).
1.1.2 Fuel Assembly Description There will be 764 fuel bundles (and spares as recurred to replace defective bundles) in the Initial core of Llrorick Unit 2.
A description of the physical dimensions and meterials of constructlen used in each of these fuel bundles is contained in Section 2 of the General Electric Standard Applicat ten for Reactor Fuel (GESTAR-il:
GE docunents NEDE-24011-P-A-8, and the United i
States Supplerent NEDE-24011-P-A-8-US, May 1986),
Which are incorporated herein by reference.
1.1.3 Enrichrent Section 2 of GESTAR !! also contains a conclete description of the enrichrent and weight of the uranium used in each asssmbly.
The specific bundle types, the nuTber of each, enrichnents in U-235, and U-235 heights in the initial core of Limerick Unit 2 are presented in Table 1.1.3, which is attached hereto and incorporated herein.
Table l
1.1.3 also states the total U and U-235 weights and the average enrichrent of the 764 bundles.
The total weight of each fuel bundic is approxirately 272 kg.
1 1.1.4 Isotente Content
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The initial core will nominally cor.tain 139.54 metric tons of uranium, 2.58 metric tons of which is specified as being U-235.
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.w 1 1.2 Fuel Storage Conditions 1.2.1 Fuel Stcrage Location The nev fuel will be stored outdoors in the new l
fuel storage area which is located on the west side of the plant as shonn in Figure 1.2.1 which is attached hereto and incorporated herein.
The fuel will then be brought to the refueling floor and stored in the Unit 2 Spent Fuel Pool (SFP) before the initial fuel load.
New fuel will not be stored in the nev fuel storage vaults at Limerick Unit 2.
1.2.1.1 Storage Area and Array Description The nev fuel storage area will be enclosed by an eight (8) foot high fence and provided with a wateFran 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day during the duration of the fuel's stay in this area.
The new fuel storage area will be sufficiently li taninated to permit night surveillance of the fuel.
The fuel for the Initial core of Unit 2 (764 assemblies) will be stored in three (3) pfles with sixty-four (64) containers In each plie stacked four (4) high and sixteen (16) across; and four (4) piles with forty-eight (48) containers in each pile stacked four (4) high and twelve (12) across. A spacing of twenty-five (25) feet will be meintained between any two piles and between each pile and the new fuel storage area fence.
The fuel will be stored in the ceter wooden Reactor Assemblies (RA) containers that they were shipped in and additionally each plie of fuel will be covered bv a
'five-sided box manufactured out of corrugated steel. The~ weight of each plie of fuel is sufficient to withstand windstonns of 100 year mean recurrence interval.
1.2.2 Activities in Adjacent Areas In the areas adjacent to the new fuel storage area there exist permanent buildings.
In addition there is a permanent building that wl11 be used for offices or a change house.
There is also a substation adjace-t to the new fuel storage area on the north side.
Activities in adjacent a eas will be of a nature such that the safety of the fuel will not be affected.
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1.2.3 Indoor Storage Facilities and Eculpnent The Limerick Unit 2 spent fuel pool, as It'ustrated in Figure 1.2-15 of the Limerick Final Safety Ar.alysis Report (FSAR), is an integral structure within the reactor enclosure. The fuel storage facilities and handling eculpment are designated Seismic Category I and are protected against the ecst severe environcental phenonena which have been postulated to occur at'this site.
1.2.3.1 Spent Fuel Pool The Limerick Unit 2 spent fuel pool will be used for storage of new fuel prior to initial fuel loading.
The spent fuel pool of Unit 2 is connected via a transfer canal to the spent fuel pool of Unit 1.
The spent fuel storage racks within the SFP have a storage capacity of 2,040 fuel assemb11es (267
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percent of full core load) with sufficleat space to expand to a maximum capacity of 2,862 b.
(375 percent of full core load). The storage racks are designed to meet Selsnic Category I requirenents as defined in
.gulatory Gulde 1.13.
These racks are designed to withstand the effects of a design basis earthquake (DBE) and recel'.1 functional, in accordance with Regulatory Guide 1,29 and the Code of Federal Regulations, Title 10, Part 50. Diagrams of the spent fuel racks are in Figures 1.2.3.1(a) through 1.2.3.1(h) which are attached hereto and incorporated herein. (It should be noted that the typical corner cross-section d
sketch on Figure 1.2.3.1(c) and the enlarged sketch of the typical corner cross-section on Figure 1.2.3.1(e) are conceptual in nature and j
a nominal 6.625 inches center-to-center spacing is maintained between fuel assenblies in a rack as Indicated in Section 9.1.2.2.2 of the Limerick FSAR).
The spent fuel racks consist of six basic structural canponents: top grid casting,
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bottan grid casting, poisen cans, side plates, corner angle clips, and adjustable foot assemblies. The tcp and bottcm cast aluninun grids sandwich the square cross-section poisen can into j
pockets in a checkerboard a rrangement. The grids are held in place by aluninun side plates and corner angles bolted and rivetad with aluninun blots an.d rivets. The rack modules are Individually
'eveled with adjustable foot assenblies at the four corners of the botton grid. The storage racks are modular, free standing, top entry racks designed to meintain the spent (and new) fuel in a space geometry whereby each fuel assenbly has a neutron r
poisoning material between it and any adjoining fuel assenbi l es.
This precludes the possibility of criticality under nonnal and abnonnal conditions as discussed in Section 2.2.4.3 of this Application. There are three sizes of storage racks, the 10x11 racks have 55 poison cans, the 10x12 racks have 60 poison cans, and the 11x12 recks have 66 poison cans.
Figure 1.2.3.1Cg) 111ustrates the initial layout of the spent
't fuel racks in the spent fuel pool and Figure 1.2.3.1(h)
-1 111ustrates the layout for maximun capacity. The poison cans censist of two 0.090-inch thick concentric square aluninun tubes with four l
_a-(5.25 inches wide, 152 inches long, 0.080 inch thick) plates of P. oral (Boren Carbide in an aluninun canposite matrix, with an aerial nominal density of 0.028 G/CM ) in the annular gaps. The Boral is so positioned that it overlaps the fuel pellet stack length in the fuel assenblies by one inch at the top and bottom.
The outer concentric tube is folded into the inner tube at both ends and totally seal welded.
Each poison can is pressure and vacuun leak tested through a 13/64 Inch hole, which is then plug welded to isolate the Boral from the pool water. All meterials used for construction of the racks are specified in accordance with the issue of the ASTM specifications in effect on March 1979, as appilcable.
1.2.3.2 Reactor Enclosure Crane The reactor enclosure crane is a bridge crane mounted on runway rails that are s;pported by the reactor onclosure superstructure.
The reactor enclosure crane is designed to handle loads with a maximun weight of 125 tons while maintaining -a minimt.m safety factor of 5.
There is also an auxiliary hoist with a design capacity of 15 tons.
The reactor enclosure crane is designed to prevent movement of the crane over the new fuel and spent fuel storage areas in the absence of specific action by the crane operator to allow sus.' movement.
Figure 1.2.3.2, which is j
attached hereto and incorporated herein, j
illustrates the areas of restricted crane movenents.
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_9-1.2.3.3.
Fuel Servicing Equipment The fuel servicing equipment consists of apparatus as described below; a)
New Fuel Inspection Stand The nev fuel inspection stand (Figure 1.2.3.3(a))
which is attached hereto and incorporated herein, serves as a support for the new fuel bundles undergoing receipt inspection and provides u working platfonn for technicians engaged in performing the inspection. Also, Figure 2.2.5.4(a) which is attached hereto and incorporated herein, gives a simplified layout of the new fuel handling facilities, b)
Channel Handling Tool The channel handling tool (cigure 1.2.3.3(b)), which is s*tached hereto and incorpc ated herein, is used in conjunction with the fuel preparation techine to recove,.
Install, and transport fuel channels in the fuel storage cool.
The tool is composed of a handling ball, lock / release knob, extension shaft, angle guides, and clamp arms that engage the fuel channel.
The channel handling tool is suspended by its ball fran a spring balancer on the channel handling boon located on the fuel pool peri phe ry.
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Fuel Preparation Machine The two fuel preparation machines (Figure 1.2.3.3Cc)),Td11ch is
.s attached hereto and incorporated herein, are mounted on the wall of the fuel storage pool and are used for channeling and dechanneling fuel.
The' channel gauging fixture, a go/no go' gauge used to evaluate the condition of a new fuel channel before channeling, is located between the two fuel preparation machines.
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General Purpose Grapple The general purpose grapple (Figuro 1.2.3.3(d)), vkIch is attached heretc and incorporated he ein, is a handling tool used generally with the fuel.
The grapple can be s
attached to the reactor enclosure auxiliary hoist, on the refueling pl atforns. The general
,urpose grapple is used to move new fuel from its storage location on the refueling floor, place it in the inspection ~ stand, and transfer it to the fuel pool.
1.2.4 Fire Protection 1.2.4.1 New Fuel Stor'.ge Area The fire protection in the new fuel storage area consists of five-sided boxes manufactured out of corrugated steel placed over each plie of fuel.
Sufficient fire hose line will be available such that water can be directed to the fuel fran two
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- different locations.
Lightning protection will be provided by an overhead transmission line. Access to this area will be controlled as described in the Physical Security Plan (see Section 1.3 of this application).
1.2.4.2 Reactor Enclosure All fire protection systems within the reactor enclosure air-lock ar.d the refueling floor will be in place and operative at the time the fuel is transferred to the refueling floor.
Section 9.5.1 of the Limerick Generating Station FSAR describes the reactor
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enclosure fire protection systens.
1.3 Physical Protection Applicant will store the Special Nuclear ibterial to be received in the Main Protected Area as defined in the approved Physical Security Plan for Limerick Generating Station Unit 1 which has been previously approved by the NRC. This Protected Area is considered the Controlled Access Area required by 10CFR73.67.
Such storage will provide for the physical protection of the Special Nuclear Material which meets the requirements of 10CFR73.67.
1.4 Transfer of Special Nuclear Material 1.4.1 Respor.sibility for Fuel Shipment General Electric Company (the fuel fabricator) is responsible for shipment of the fuel assemblies. fran the fabrication plant in Wilmington, North Carolina to the Limerick site.
I n' addition, any return of fuel assemblies to Wilmington, N.C. (for any reason) is the responsibility of the General Electric Company.
The fuel will be shipped to the Limerick site in the General Electric Model RA-2 or RA-3 container authorized for use as a Fissile Class I container by NRC Certificate of Compilance USA /4986 for the transport of fissile radioactive materlal in the form of General Electric reactor fuel.
_ - -. 1.4.2 SNM Control and Accounting Practices SNM centrol and accounting practices that comply with the appilcable provisions of 10CFR Part 70.51 are described in procedures "A-44-Procedure for Special Nuclear Material Account ing" and "ST3-97-350-0 Annual SW Inventory".
A hb is attached as Exhibit 2.
ST3-97-350-0 is attached as Exhibit 3.
These procedures provide for an annual inventory of Spect'al Nuclear Material rather than the six (6) month inventory presently provided in Condition 14 of License SM4-1977.
Changing Condition 14 from a six month to annual basis for SNM inventory will not lead to any adverse affects or significantly corpremise the accounting of SNM at the site.
1.5 Financial Protection and Indemnity The appilcant has currently purchased the maximun available nuclear l iabil lt,y insurance for the Limerick site from American Nuclear Insurers, policy No. NF-284 and from Mutual Atonic Energy Llability Underwriters, y'
policy No, MF-113.
The original copies of the policies are on file with the NRC.
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2.0 Health-and-Safety 2.1 Radiation Control This section provides information regarding radiation safety at Limerick Generating Station.
1 2.1.1 Minimun Qualifications for Positions having Radiation Safety Responsibilities.
The minimom qualifications for the Senior Health Physicist (Radiation Safety Officer) are those outlined in Section 4.4.4 of ANSI /ANS-3.1-1978, "American National Standard for Selection and Training of Nuclear Power Plant Personnel". The applied Health Physicist and Support Health Physicist fassist RS0s) have as a minimum a four-year degree in Health Physics or a related field and at least j
24 months applied Health Physics experience, j
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.- _ 2.1.2 Responsibili les for Radiatic'n Safety Personnel The responsibilities for the key radiation safety personnel are described by the following "Radiation Safety Program" description.
The radiation safety program is directed by the Senior Health Physicist. Assisting the Senior Health Physicist are the Support Health Physicist, the Applied Health Physicist, and the Supervisor, Radiological Engineering.
These positions have the authority to act for the Senior Health Physicist in his absence.
The objectives of health physics operations are to:
a) detect, identify, and define radiation hazards, b) provide protection for personnel against radiation hazards.
l c) control plant-related radiation exposures (occupational and general public) to levels As Low As Reasonably Achievable (ALARA),
d) conduct plant activities in confornaree with authorized procedures and applicable regulations.
i These objectives are acconpilshed or eahanced i
by the various training prograns, by ;he use of prepared Health Physics operating procedures, by periodic review and revision of procedures, by evaluation of activities for ALARA purposes, and by the control of plant operations to minimize occupational exposures and releases to the environnent.
Health Physics operations include the posting, notification, and reporting provisions of 10CFR Par *. 19 and General &nployee Training, or in sene cases task-specific Instruction, provides the requisite instruction to workers.
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Health Physics operations conform with the guidelines of Regulatory Guide 8.2 (Rev 9) and of ANSI N13.2-1969, Guide for.
Adninistrative Practices in Radiation Monitoring, Tvith the clarification that controlled areas which are locked or otherwise prevent personnel access are not required to be surveyed as a specific periodicity.
In addition to this section, Sections 12.1, 13.1, 13.2, and 13.5 of the Limerick FSAR describe the management ccnmitment, organization, responsibilities, authori ty, training procedures, and review techniques which implement Regulatory Guide 8.8 (Rev 3),
Regulatory Guide 8.10,f and Regulatory guide 1.8 (Rev. 1-R).
As described in Section 12.1 of the Limerick FSAR, a formal ALARA review program which is consistent with the guidelines given in Regulatory Guide 8.8 was implemented during the design and construction phase.
The qualification requirenents fcr the Senior Health Physicist are described in Section 13.1.3 of'the FSAR. Chapter 17 of the Limerick FSAR and the Limerick Technical Specifications address implementation of other applicable regulatory guides. The portion of the Health Physics progran related to special nuclear materials is outlined as follows:
4 RADIATION-PROTECTION-PERS0tNEL.
Senior Health Physicist (Radiation Safety Officer)
The Senior Health Physicist reports through the Station Superintendent of Services to the Plant Manager and receives technical direction and support from the offsite Director - Radiation Protection Section.
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The Senior Fealth Physicist corresponds to the Radiation. Protection Manager as described in Regulatory Guide 8.8-1977 (Revision 3) and 8.10-1977. His duties /respcnsibilities in this capacity include:
a) developing and Irplementing an effective radiation exposure control and rreasurement program in consonance with the PEco ALARA poIIcy.
b) ensuring that exposure neasurerent and control programs are periodically reviewed and that appropriate revisions and corrective actions are taken when the results of these prograns indicate that such actions are needed to conform to the PECo ALARA policy.
c) preparing and reviewing procedures for implementing the ALARA policy.
d) ensuring that the resources needed to implement the ALARA policy are available and used.
e) participating in reviews including design and procedure reviews at the Plant Operations Review Ca7mittee (PORC) level, of facllities, activities, and.eauf prent that can affect potential radiation exposures, f) supervising radiation, surface contanination, and airborne activity surveys and supervise the review of resulting data to identify locations, operations and conditions that have the potential for causing significant exposures and developing appropriate means for reducing such exposures.
g3 participating in the development of training programs related to the ALARA program to ensure that personnel are aware of PECo management's ccomitment to ALARA and are Instructed in ways of reducing exposures that are related to work in radiation areas or that involve radioactive materials.
s h) supervising the radiation surveillance prograns and the collection, analysis, and' evaluation of data fran raalological surveys and from personnel exposures and doses including the use of the radiation work pennit data.
1) supervising and training of the health physics staff.
J) providing appropriate data and infonnatIon related to the ALARA progran and results to the Plant Manager and to the Director, Radiation Protection Section, to keep canpany management infonned about the progran.
k) acting Radiation Protection Manager.
In his absence a person tanporarily filling this position will have a BS degree in engineering or science with tvo years experience in radletion protection, one year of which shall be nuclear power plant experience, six months of which will be on site.
Health Physicist (Assistant Radiation Safety Officers).
The Support Health Physicist, the Applied Health Physicist, and the Suoervisor, Radiological Engineering report to the Senior Health Physicist and implement the PECo ALAPA program and perfonn functions as assigned by the Senior Health Physicist.
Specifically the Health Physicists are responsible for:
a)
Perfornance of radiation, surface contamination, and airborne activity surveys and collection, analysts, and maintenance of associated data.
b) control and implementation of personnel dosimetry requirements and the collection, analysis, and maintenance of associated data.
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barricades, control points, and i1 access conditions.
l1 d) performence and/or supervision of decontanination of areas, equipnent, and personnel,
e) surveillance of laundry operations and radioactive material transfers.
f) maintenance and perfonnance of equipnent within his review, g) respi ratory protective equipnent and protective clothing and equipment program operations.
h) bloassay and Internal dose determinations.
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monitor effluent releases to
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ensure conpliance with Technica!
j Specifications.
2.1.3 Training and Experience
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The experience of the Health Physicists is presented in Figures 2.1.3 2.1.3-35.
The training necessary for Health. Physicists is I
outilned in Secticn 12.5.3.5 of the Limerick FSAR.
2.1.4 Procedures and Equipment for Checking Contamination The Health Physics personnel will be notified when a shipnent of new fuel or instrumentation containing Special Nuclear Material arrives on site. Health Physics personnel shall perfonn conplete radiation and contamination surveys of the outside of the transport vehicle to ensure that the radiation levels are within acceptabic limits.
If all survey,deta is within ilmits, the vehicle will proceed with unloading.
If survey data is above established limits, appropriate actions, as defined in Plant Operations Review Committee (PORC) approved written station procedures, wi l l be fol l o,ved.
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2.1.5 Calibration and Testing of Instnanentation All Instruments shall be tested and calibrated routinely in accordance with approved station procedures.
Survey instruments will be callbrated on an annual basis.
Instrument calibration will be perforred by cuallfled station personnel or thrcugh a vendor. Each Instrument will bear a sticker Indicating the date when recalibration is due.
2.1.6 Procedures and Equipment Used to Meet Appilcable Sections of 10CFR Part 20 The Limerick Generating Station will be operated and maintained in such a manner as to ensure that occupational radiation exposures are ALARA and that protection against radiation is in accordance with 10CFR Part 20.
The health physics provisions which accomplish this goal are described in Section 12.5 of the Limerick FSAR.
2.1.7 Provisions for Disposal of Radioactive Wastes The sna11 quantitles of radioactive waste generated in the surveying of SNM Itens for contamination will be stored in an approved location prior to burial.
Shipment of radioactive waste is strictly controlled by Health Physics Procedures which comply with 10CFR71 and 49CFR 171-178.
2.2 Nuclear Criticality Safety 2.2.1 Minimum Oualifications for Positions Having Nuclear Criticality and Fuel Handling Responsibilities The key position havirg nuclear criticality safety and fuel handling responsibilities is the Reactor Engineer. He is responsible in as much as he generates procedures for fuel handling that incorporate nuclear criticality safety guidelines.
These procedures are then reviewed by the Plant l
Operations Review Conmittee. The minIntm qualification for the Reactor Engineer are those stated in ANSI /ANS-3.1-1978 Section 4.4.1.
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. 2.2.2 Respcnsibilities for Personnel Having Nuclear Criticality and Fuel Handling Responsibilitics.
The key personnel responsible for nuclear criticality safety and fuel handling is the Reactor Engineer.
The Reactor Engineer reports to the Technical Engir.eer and is responsible for determining and monitoring core perforrence and for establishing appropriate operating guides and.
procedures to ensure safe, economical reactor operation in cono11ance with the operating Ilcense and technical specifications.
The Reactor Engineer Is responsible for nuclear history, and the j
perforrance of equipnent under purview.
2.2.3 Shipping Containers The new fuel asseabiles will arrive at the site in the General Electric RA shipping containers.
Upon receipt, the new fuel shipnents will be directed to the new fuel storage area previously described in Section 1.2.1.1 above.
The new fuel bundles will remain in their original shipping containers until such tire that they are transferred to the reactor enclosure.
2.2.4 Nuclear Criticality Safety of New Fuel Storage Locations 2.2.4.1 Nea Fuel Storage Area The nov fuel storage area is constructed so as to provide a well drained area such that should the area be flooded, water will not be retained around the stored shipping containers. A criticality safety analysis for fuel assenbiles in the inner retal containers for both flooded and non-flooded conditions is set forth in NRC Certificate of Conollance USA /4986/ for the General Electric RA-Series Shipping Package. The review has denonstrated that the RA container loaded with the nest reactive proposed General Electric BWR fuel meets the established Fissile Class I i
requirenents defined by 10CFR71.
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2.2.4.2 Refueling Floor Storage of New Fuel Fuel will be brought to the refueling floor in metal containers and stored as described in Section 2.2.5.3 of this application.
In the handling and inspection sequence on the refue1Ing
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ficor, two (2) bundles will be in the inspection stand and two (2) additional bundles will be standing upright within their metal RA' container with the top off.in the unloading station.
(See Figure 2.2.5.4(a) which is attached hereto and incorporated herein). The distance between fuel in an opened fuel box and the fuel in the new fuel Inspection stand will be a minimum of five (5) feet.
On the refueling floor no more than three (3) bundles will be out of their RA containers at any one time. The above constraints preclude the possibility of accidental criticality during the handling and inspection sequence on the refueling floor.
2.2.4.3 Storage of New Fuel in the Spent Fuel i
Pool The spent fuel storage facility is designed to store new and irradiated fuel assembi tes so that a k-eff less than or equal to 0.95 is naintained, assuming that the fuel storage racks are fully loaded with fuel of the highest j
anticipated enrichment and flooded with non-borated water, in compliance with General Design Criterion 62.
This is achieved through use of a neutron poisoning material (Boral) sandwiched in the racks between adjoining fuel
.I assemblies to ensure subcriticality by at least five (5) percent Ak under all conditions.
The basis for criticality control of fuel storage in the spent fuel pool is discussed in Section 9.1.2.3.1 of the Limerick FSAR.
The presence of Boral is verified bv receipt and in-service testing.
At receipt of the spent fuel racks, the presence of Boral was verified in each can, using the Boral Testing Device.
The in-service testing program is described in Section 9.1.2.4 of the Limerick FSAR.
t 2.2.4.3.1 Validation of the Calculational MetFed for Nuclear Criticality Safety The validation of the calculation netFod for nuclear criticality safety of fuel stored in the spent fuel pool is contained in Sections 9.1.2.3.1.1 through 9.1.2.3.1.6 of the Limerick FSAR 2.2.5 Handling Procedures 2.2.5.1 Fuel Receipt All new fuel bundles for Limerick Unit 2 initial core will be delivered to the new fuel storage area described above in accordance with the shipping procedures and arrangecents of General Electric Company, in container Model RA-2, or RA-3 authorized for use as a Fisslie Class I container.
General Electric Company is responsible for shipnent of the fuel bundles from the fabrication plant in Wilmingten, North Carolina, to the Limerick site.
Fuel will be shipped by truck trailers in cuantitles of up to sixteen (16) containers per load.
Each of these containers will contain two (2) fuel bundles.
Fuel bundles will be received at the storage site in the shipping containers mentioned above. Upon arrival et the new fuel storage area, the containers will be monitored for external radioactive contaminat ion.
The new fuel will then be removed from the trailer via fork-lift trucks. Only one shipping container at a time will be handled by any single fork-Ilft truck.
The shipping containers will be placed in predesignated locations within the new fuel storage area.
Experience in shipping fuel la the General Electric Moddl RA-2 and RA-3 container demonstrates'that there is a low probability of transport damage which could result in contanination._
2.2.5.2 Fuel Transportation to Reactor Enclosure A fork-1if t truck wi11 remove one fuel storage container at a time to be placed on a flatbed trailer for transportation to the reactor enclosure air-lock In quantitles not exceeding six (6) containers per load.
The route to be taken in the actual move of the new fuel from the new fuel storage area to the reactor enclosure air-lock is Indicated on attached drawing Figure 1.2.1.
The distance to be traveled is approximately
)
900 feet.
J
_a,
. 2.2.5.3 Fuel Movement to Refueling Floor The fuel bundles still within the outer vooden container will be backed into the reactor building air-lock where the wooden containers will be renoved. Up to six metal RA containers at a time will be holsted using the reactor enclosure crane or a cherry picker crane to the reactor enclosure 'efueling floor and stored in a predesignated storage area.
The fuel containers shall be stored no higher than a four high configuration.'
An area survey at the final temporary storage location shall be performed by Health Physics personnel on an as required basis.
2.2.5.4 Removal of Fuel Bundles Fran Shipping Container and Inspection Before the fuel bundles are renoved, the retal RA containers Clids removed) are suspended and placed in the unicading station located near the new fuel inspection stand.
The metal container end piece is then renoved. Health Physics personnel make a survey of removable contanination on the outside of the plastic bag covering the bundle, The bundio is then visually inspected for darage. The respective fuel bundle is rencved via the auxiliary hoist or cherry picker and transferred to and secured in i
the new fuel Inspection stand.
Figure 2.2.5.4(a) and Figure 2.2.5.4Cb), which are attached hereto and incorporated herein, give a sinclified layout of the new fuel handling facilities.
The acceptance inspection is perforced with olther one or two fuel bundles in the l
vertical position.
Fuel bundles that do not pass acceptance inspection are returned to their shipping containers. A Defective Tag will be placed on the exterior of the shipping container and the discropancies noted.
2.2.5.5 Channeling in the New Fuel Inspection Stand Upcn comcietion of the fuel inspection, ead bundle is channeled in the nov fuel inspecticn stand. A channel is selected and positioned above the fuel bundle.
The channel is lowered onto the fuel i
bundle and secured with the channel fastener asser61y.
Folloaing the cceplet ion of the channel ing process, each assenbly is transferred to a storage location in the spent fuel storage pool by the refueling bridge.
(See Figures 2.2.5.4(a) and 2.2.5.4(b) which are attached hereto and incorporated herein).
2.2.6 Exemption 2.2.6.1 Criticality Accident Recuirements The procedures and storage facilities described in this application provide assurance that inadvertent criticality cannct occur during receipt, possession, and storage of new fuel assenbiles at Lirerick Generating Statten.
i The General Electric shipping containers In which fuel will be received meet the Fisslie Class I requirements defined by 10CFR71.
In addition, the spent fuel pool is designed to ensure subcriticality by at least five (5) percent Ak under all cenditions (see Section 2.2.4.3).
Furtherrore, the procedures for unloading and inspecting the new fuel are based in part on the preventien of criticality during these operations.
Based on the above discussion, Philadelphia Electric Company requests exemption from the requirerents of 10CFR70.24 as provided in 10CFR70.24(d).
- - 2.3 Accident Analysis 2.3.1 New Fuel Storage Area In the new fuel storage area, only one shipping container at a time will be handled by any single fork-lif t truck during. loading and unloading activities. General Electric Company has conducted hypcthetical accident condition tests of 'the Inner metal shipping containers in the sequence specified Ir, Appendix B to 10CFR71 and the inner metal containers passed the acceptance criteria as described in NRC Certificate of Compliance USA /4896 for the General Electric RA Series Shipping Package.
2.3.2 Spent Fuel Pool No adverse reactivity effect is expected fran dropping a fuel assembly on top of a fully' loaded storage rack during handling because of the large water thickness (acproximately 10 Inches) existing between the top of the assemblies already inside the cavities and the dropped assembly resting on top of the rack.
The dropping of an assembly outside the rack is a possible event because of the unobstructed water area existing between the periphery of the storage rack and the side walls of the pool (See Figure 2.3.2, which is attached hereto and Incorporated herein).
The K-eff for this case was 0.8861, an increase of K:0.003 over the same geonetry without the dropped fuel. A more detailed discussion of this case can be found in Section 9.1.2.3.1.5Cb) of i
the Limerick FSAR.
l The structure of the racks is designed to renain functional and to maintain the required spacing
)
between stored fuel assemb11es in the event of impact of a fuel bundle dropped on the racks form an elevation of 36 inches.
See Sect!on 9.1.2.3.2.1 of the Limerick FSAR for a more detailed discussion of this case.
In addition, Section 9.1.2.3.2.3 of the Limerick FSAR addresses the analyses of a dropped fuel bundle.
Extrene cautlen is exercised during the fuel handling to prevent a fuel assembly fran striking another fuel assembly or other structures.
In the unilkely event that a fuel assembly would be dropped, all fuel handling activities would be stopped. An assessment of the damage wculd be l
made and appropriate corrective action taken prior to authorization to continue fuel handling activities.
1 i
Correspondence with respect to this Application should be addressed to:
Ed.va rd G. Baue r, J r., Esq.
Eugene J. Bradley, Esq.
2301 Parket Street Philadelphia, PA 19101 Respectfully submitted, PHILACELP IA ELECTRIC COMPANY j
BY:
( -
h
/' / Vice President FMS/cb/03308802 i
(
CC/NCtNEALTH OF PENNSYLW4;I A
- ss COUNTY OF PHILADELPHI A S. J. Kowalski, being first duly svorn, deposes and says:
That he is Vice President of Philadelphia Electric Ccmpany, the Applicant herein; that he has reviewed the foregoing Application for knendrnent of the Special Nuclear Material License for Limerick Generating Station (Jnit No. 2 and kncws the contents thereof; and that the staterwnts and matters set forth therein are true and correct to the best of his knowledge, informetion and belief.
-i l
/
[ hW
/
l' Eubscribed and svorn to
' f',, day of before this 7
April, 1988 f
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- 2.. co. at muu, LIMERICK GENE R ATING STATION UNITS 1 AND 2 FINAL S AFETY AN ALYS15 REPORT HIGH DENSITY SPENT FUEL STORAGE DROPPED FUEL ASSEMBLY ACCIDENT Fig;:re 2.3 *;
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jdd4V47IIV SENIOR HEALTH PHYSICIST - RADIATION PROTECTION OFFICER r NAME: Gary W. Murphy EDUCATION AND TRAINING 1987 General Physics Corporation, Royersford, Pa. Certified Senior Reactor Operator 1979-1980 University of North Carolina, Chapel Hill, School of Public Health, Department of Environmental Sciences and Engineering M.S.P.H. Radiction Protection with concentration in industrial hygiene 1976-1979 Harvard University, School of Public Health Graduate level courses in: Radiation Eiology Radiation Protection Occupational Health Environmental Health Management Short courses in: Nuclear Emergency Planning Radiation Safety 1969-1973 Merrimack College, North Andover, Mass. B.A. Biology WORK EXPERIENCE 11/87 Senior Health Physicist / RPM /RSO-Limerick to Present Generating Station 1. Responsible for the implementation of the Radiation Protection Program at Limerick Generating Station. 2. Provides administrative and technical directien to the Health Physics staff in the areas of Dosimetry and Bioassy, Respiratory Protection, ALARA Programs implementation, Radioactive Effluent i Monitoring, and Radiation Monitoring ) Instrument Calibration and use. 'l H 3. Serves as a member of the Plant Operation Review Committee. Figure 2.1.3-1 j
3COHVLJl Iv 4. Oversees the development and implementation of training for Health Physics Professionals and Technicians. 11/83 to 11/87 Support Health Physicist, Limerick Generating Station Supervise the Technical Support Health Physics Group which includes the Dosimetry, Respiratory Protection, and Protective Clothing, Special Projects, Enviromental Monitoring, and Radwaste and Radioactive Material Shipping Programs. Responsibilities include: Establish objectives for program area managers consistent with excellence in plant operation. Provide technical direction and resources as required to support program objectives. Review and approve technical reports and test results generated within program areas. Serve as Emergency Offsite Dose Assesment Team Leader. Serve as Plant Operations Review Committee Alternate. Serve as Health Physics Department Safety Representative. 3/83 - 11/83 Resident Engineer, G.A. Technologies, Inc. Lead Project Engineer for Philadelphia Electric Company for Digital Process Radiation Monitoring System and Emergency offsite Dose Assesment System. 9/80 - 3/83 Engineer / Health Physicist Mechanical Engineering Division Philadelphia Electric Company Lead Project Engineer, Limerick Radiological Environmental Monitoring Program Project Engineer, Limerick Plant Process and Area Radiation Monitoring Systems Lead Project Engineer, Limerick Emergency Offsite Dose Assessment System and Effluent Monitoring System 9/76 - 7/79 Senior Research Assistant, Laboratory of Radiation Biology, Harvard University, School of Public Health j 3/74 - 7/76 Tufts University Medical School, Senior Research Assistant, Sidney Farber Cancer Research Center Figure 2.1.3-2 m.
3804U2Y//U APPLIED HEALTH PHYSICIST DATE APPOINTED: March 1983 NAME: Richard J. Titolo EDUCATION AND TRAINING i ) 1976-1980 Georgia Institute of Technology B.S. in Health Physics (Magna Cum Laude) 1980-1981 Georgia Institute of Technology M.S. in Health Physics (Summa Cum Laude)
- January, 1982 Midlands Technical College - One week Regulatory Awareness Course in 49 CFR, Chem Nuclear Systems, Inc.
1982 Georgia Power Company-Supervisor Safety Training Observation Program
- May, 1983 PECo, Kepner Tregce (K-T) - 2 days, Problem Solving and Decision Making
- July, 1983 PECo, Engineer Orientation Training Program-4 weeks, covering BWR Systems and Reactor Theory
- June, 1984 Theory & Operation of Eberline Survey Instrumentation
- November, 1984 Radioactive Material Shipping Regulatory Awareness Course - Chem Nuclear Systems
- June, 1985 INPO Radiation Protection Manager's Workshop-3 days
- December, 1985 Nuclear Professional Training-3 weeks, Nuclear Plant Systems, i
Regulatory Awareness September, 1986 Edision Electric Institute Meeting-4 days
- February, 1987 Beta Dosimetry Training-2 days; Porter Consultants
- June, 1987 Advanced Respiratory Protection-2 days; Radiation Safety Associates l
1 Figure 2.1.3-3 ~ _....,,. _ _
3834029770
- July, 1987 Health Physics Audits-2 days s
WORK EXPERIENCE 3/83 to Applied Health Physicist, Limerick Generating Present Station Duties: General: Responsible for the development and implementation of the station operational Health Physics program. Function in the capacity of the Senior Health Physicist (RPM) in his absence. Specific: 1. Responsible for the development and implementation of the station roytine and special radiological surveillance program. 2. Responsible for the development and implementation of the station Radiation Work Permit system. 3. Direct the Instrument and Control group responsible for maintenance and calibration of Health Physics instrumentation. 4. Evaluate Health Physics instrumentation requirements and assist in procurement.
- 5. Supervise the Health Physics Supervisor, Health Physics Technical Assistants, and Technicians.
6. Supervise the ALARA Physicist and Technical Assistants, and direct the development and implementation of the station ALARA program. 7. Supervise procedure development and review technical procedures for adequacy and accuracy. I 8. Serve as Personnel Safety Team Leader j (alternate) during emergencies. I t i i i Figure 2.1.3-4
-3884029770 10/81 - 3/83 Georgia Power Company-Health Physicist E.I. Hatch Nuclear Plant 1. Responsibility for the development of the site ALARA program in collaboration with INPO personnel. 2. Studied and evaluated' methods to estimate exposures, established all site exposure goals, and formulated monthly exposure update reports. 3. Provided ALARA input to the Engineering department concerning proposed design changes. 4. Instructed decontamination personnel in the use of strippable. coating, approved and supervised initial applications. 5. Collaborated with maintenance personnel in the development of a pre-job checklist and supervised the initial phases of implementation. 6. Performed job reviews for ALARA concerns i and coordinated preparatory activities. 7. Devised protective clothing and respiratory protection guidelines and action levels. 8. Developed and provided ALARA training to plant personnel, i 9. Performed plant inspections of health j physics related activities, e.g. posting, procedural compliance, and directed HP staff in the resolution of ) problems identified. 10. Investigated Radiation Occurrence Reports written by HP technicians and provided direction for corrective action. 1 11. Wrote Laboratory Standing. Orders (LSO) at the request of the HP Supervisor which provided instruction in the resolution of problems encountered by the HP operating organization; supervised initial phases of LSO implementation. Figure 2.1.3-5
3884029770 12. Provided guidance and technical support to the technicia.., responsible for radwaste shipments. 13. Prepared project documentation for equipment and services required in the annual budget. This included vendor interface for functional specifications and cost-benefit analysis. Emergency Preparedness Duties: 1. Developed ar;d revised Emergency Plan Implementing Procedures. 2. Supervised HP technicians assigned emergency preparedness duties. 3. Participated in the development of corporate response to appraisals and evaluations. 4. Responsible for the development and coordination of site mini-drills, held in preparation for the annual graded exercise. 5. Developed and provided training to Operations personnel on control room procedures for emergency classification, offsite dose assessment and recommendation of protective action. 6. Supervised and dispatched offsite monitoring teams during emergency drills and exercises. 1/80 - 9/81 Georgia Institute of Technology Research Assistant Project: Correlation of absorbed dose to the hand with dosimetry measuring devices attached to the extremeities. This project was designed to study the reliability and accuracy of extremity dosimeters through a comparison of point readings with a continuous dose distribution. Directly responsible for the formulation of a model of the hand and wrist composed of tissue equivalent material and TLD powder. Also, responsibl9 for the calibration of the CaF TLD, i.e. formulation of glow curves. Figure 2.1.3-6
3884029770 9/80 - 12/80 Georgia Institute of Technology Research Assistant This project involved the experimental verification of the MIRD computer based calculations in the area of internal dosimetry. Responsible for searching the literature available on the subject of aqueous dosimetry. Studied the feasibility of using a sensitive liquid dosimeter in lieu of a TLD dosimeter. l 6/80 - 9/80 Applied Physical Technology Project Director Involved primarily with emergency assessment and response systems. Directly responsible for i project scheduling, customer communications, and procuring the necessary equipment. Assisted in system configuration and testing, as well,as preparation of associated equipment manuals. I 6/79 - 6/80 Georgia Institute of Technology Research Assistant Research done on the field of environmental impact from radioactive waste disposal. Responsibilities included the design, performance and interpretation of experiments utilizing columns nt:%ed with minerals from proposed disposal sites. Also, responsible for the activation of Na-23 at the university reactor. Employed the use of radioactive tracers, appropriate electronics and a computer I program to analyze results. l l TROFESSIONAL AFFILIATIONS l l Health Physics Society American Nuclear Society ] I i I i 1 !I I! l il l Figure 2.1.3-7 i i
3884029HU NAME: Stephen L. Taylor EDUCATION AND TRAINING 1977 Red Lion Area Senior High 1983 Philadelphia Electric Company Health Physics and Chemistry Assistant Technician through A Technician 1 Radwaste Quality Control Inspector ISI Ultrasonic Inspector 1984 General Physics - Mitigation of Core Damage Chem Nuclear - Regulatory Awareness Radioactive Waste Packaging, Transportation and Disposal 1985 Philadelphia Electric Company Nuclear Professional Training 1986 Philadelphia Electric Company Management Development Program Time Management Training Writing Than Can Be Understood Kepner Tregoe-Resolving Concerns Through Rational Process 1987 Philadelphia Electric Company Continuing Training Advanced Respiratory Protection Perter Associates-Beta Dosimetry Training WORK EXPERIENCE 12/84-t Present Health Physics Technical Assistant - Plant ALARA, Limerick Generating Station Duties: 1. General ALARA Responsibilities A. Identifying areas where exposure can be reduced B. Pre planning and reviewing activities which have high potential exposures C. Providing technical assistance and guidance for on-site groups '.o ensure ALARA effectiveness D. Evaluating procedures and methods for completing jobs with minimum interference while maintaining exposures ALARA l Figure 2.1.3-8
3884029770 Page 2 E. Assisting in development of ALARA procedures F. Calculating man-rem estimates of jobs being planned G. Collecting data for use in cost benefit analysis H. Assisting with the development of training programs to promote the ALARA program I. Assisting in the review of design modifications J. Performing observations of w6rk in progress for conformance with good ALARA practices 2. Health Physics Responsibilities A. Review and Sub-Pore of Maintenance procedures to ensure Health Physics direction is provided B. Developing a guideline for inspection of containment glove bags and tents C. Assisting in the Sub-Pore of various Health Physics procedures, providing operation experience when requested D. Assisting in t.ie review of RWP's for completeness and accuracy E. Assisting in the development of an RWP and ALARA computer tracking program 3. Specific First Refueling Outage j l A. Refuel Floor Area Coordinator for first refue' activities B. Assisted in development of an office enclosure utilized on the Refuel Floor C. Review of Refuel Maintenance Procedures to ensure appropriate guidance is included to control the spread of contamination and to reduce worker exposures t D. Assisted in the development of the Outage Schedule for the Refuel Floor to ensure that proper sequencing of activities were evaluated to minimize worker exposures t l Figure 2.1.3-9 l
3884029770 Page 3 E. Responsible for fabrication of a grating walkway to be utilized during Refueling. This grating will reduce worker exposures and reduce anti-C and resrirator usace. Performed an evaluation of cost vs' savings to justify the need for this ~ walkway F. Assisted in the planning for Control Rod Drive Replacement, developing an appropriate temporary location for CRD rebuild and to ensure that engineering controls for CRD Maintenance were avaluated and included in the purchase of equipment to support this function. 12/83-12/84 Limerick Generating Station - Health Physics Tech A upgraded to Senior Technician Duties: A. Performed duties of Technical Assistant Plant ALARA as specified in the previous section t 3/01-12/83 Peach Bottom Atomic Power Station - Technician B Duties: 1. Crewleader of Controls Points-Responsible for: A. Covering jobs in work area B. Maintaining logs C. Interfacing between work groups 1 D. Informing H.P. Supervision of Control Point 1 activities j i E. Reviewing paperwork, RWPIs being worked F. Ensuring appropriate surveys and representative air samples are performed a G. Assigning Health Physics technicians to provide coverage during maintencance activities T 2. Laundry Radwaste/ Shipments Duties: A. Performing HP surveys for receipt and i shipment of Radwaste and Laundry, assisting wi'ch paperwork for all shipments Figure 2.1.3-10
3 "'S* 4 3884029770 4 B. Quality control inspector for shipments of Radwaste including cask and trailer loading C. Quality and Surveys control inspector for loading, compacting of Radwaste containers i a 3. Operations HP - Duties on backshifts responsible for HP coverage in the plant. Work directly for operating shift supervision (trained in emergency,. esoceduces) interim personnel safety team leader on backshifts 4. Health Physics Crewleader of control points during following jobs:- A. Refuel Floor 1. Reactor disassembly, fuel exchange, l LPRM/CRB removal-replacement, jet pump removal-replacement i 2. Feedwater sparger modification, involved draining reactor vessel and decon, l installing shielding on vessel internals, removing old spargers, machining vessel walls, shrink fit of new spargers and installation I B. Turbine Deck 1. Breach turbine hoods, disassemble turbines, repair rotor, sandblast repair turbine diaphrams, coverage on reactor feed pump turbines and feedwater heaters C. Drywell 1. Breaching systems, removing mirror insulation, perform internal heat stress i of welds, clad overlay on RER-recire piping 4 i 6/80-3/81 Peach Bottom Atomic Power Station Technician "C" Perform surveys, provide HP coverage, system breaches, unrestricted release of tools / equipment Duties: Specific Responsibilities include: 1. Providing HP coverage for first feedwater j sparger replacement, performing invessel Figure 2.'1.3-11 _ _ _. _._ _ --_. -. _, ~..
3884029770 1 page 5 i surveys, monitoring worker doses, surveying i tools and equipment i i 4 2. Providing HP coverage for Torus Prope-Modification, draining decon of Torus Proper, open sand-blasting of Torus, welding new supports a 3. Performing non outage coverage of piping i' support modifications in the Torus Room, Residual Heat Removal Rooms and Core Spray l 1 s. ,I i 5 1 h 4 'l j s i i 1 1 1 +1 Figure 2.1.3-12
Page 6 3884029770 3/79-6/80 Peach Bottom Atomic Power Station Assistant Technician - Duties: Routine surveys, in-plant training, provide HP coverage Specific responsibilities include: 1. Providing coverage during the first feedwater heater (FWH) replacement in a commercial nuclear plant. Removed outer turbine shield wall, cut FWH away from condensor, wrapped, transfered FWH to controlled area, installation of new FWH i l 1 'l I il ] Figure 2.1.3 13 2
3884029770 NAME: Stanley F. Baker EDUCATION AND TRAINING r 1976 East Senior High School (West Chester, Pa.) 3/79 - 11/83 Aca.emic and "On the Job" training in Health Phy.ics, Chemistry and BWR technology at the Asf.stant Technician, Technician "C", Technician "B", and Technician "A" levels in the following general subject areas: Mathematics, Physical Science, Nuclear Pt;ysics, Radiation Biology, Radiation Detection, ALARA, Radiation Work Permits, Radiation, Contamination and Airborne Survey Techniques, Emergency Response, Health Physics Standards and Regulations, Counting Room Instrumentation, Analytical Techniques, Counting Room Techniques and Radioactive Waste. 1/80 Ultra Sonic testing of Scram Volume Discharge Header Water Level training (Trained by PECo. In Service Inspection Group) 7/80 Nuclear Operator Preparedness Course (N.U.S. Nine day course) 1/81 Quality Control Inspection of Rad-Waste Packaging and Shipment (Trained by PECo. Quality Assurance Department) 1/84 Mitigation of Core Damage for Technicians (General Physics Corporation) 11/85 Managing Safety Training PECo/Dupont 11/85 CPR Instructor Qualification 6/86 Nuclear Professional Training PECo 6/86 Identifying Abberant Behavior PECo 9/86 Kepner Tregoe Decision Analysis / Problem Solving 1/87 Bett Dosimetry / Skin Dose Assensment-Porter Consulting 7/87 Advanced Respiratory Protection Training-Paul i Steinmeyer Fuure ?.l.3-14
3884029770 woax exprartner 12/84 to Unit #1 Technical Assistant Present Limerick Generating Station 1. Develop Health Physics procedures and Sub-Pore reviews of same 2. Health Physics co-ordination of Rad-Waste Operations 3. Health Physics interface of I&C calibration and accountability of Health Physics instrumentation 4. Prepared training' courses and instructed technicians and nuclear workers of Health Physics procedures and work practices 5. Attended plant Staff Operational Meetings 6. Established Surveillance Program and developed U-1/U-2 Isolation Program 7. Ordering of consumabit-supplies 8. Approved locations for temporary radioactive storage locations material 9. Performed duties of area co-ordinator for i Limerick Generating Station's firs * [ refueling outage. 12/83 to Health Physics Technician "A" { 12/84 Limerick Generating Station l. Pre-PORC review of Maintenance Procedures for Health Physics concerns. 2. Assist in development of rough drafts of survey maps and review of same. 3. Develop Health Physics Procedures. 4. Received and surveyed radioactive material shipments, i 5. Instructed technicians on radioactive material receipt, truck survey technique, radiation and contamination survey techniques and procedures. - risu, 2,1,3-15 j
..a.. 3884029770 l 6. Day-to-day instruction of the technicians at LGS in work duties. 3/81 - 12/83 Health Physics Tech "B" PBAPS 1. Perform major control-point Health Physics activities in the following areas: drywell, fuel floor, turbine deck, moisture separator, torus proper, reactor water clean-up and control rod drive rebuild. 2. Conducted HP and QC inspections of. Rad-Waste and Radioactive-Material shipments, including solidified liquids, resins, laundry, filters, FW & R heaters and motors. 3. Wrote changes to various procedures. 4 4. Prepared, issued, revised radiation work i permits. ,j S. Performed all types of surveillanet tests and Health Physics surveys in accordance with HP & C procedures. 6. Performed duties of operations HP (i.e. operator escorts, surveys and responses to all emergencies). t 7. Evaluated ALARA information for ALARA categorization. 8. Off-site emergency coordinator for 'l Emergency procedure exercises along with various other roles in response to emergencies and drills. i ] 9. Performed duties of Rover HP with interface ) with L11 job groups at PBAPS Units 2,3, and Rad-Waste and review of all work in plant i and coordination of jobs. l
- 10. Conducted on-site test of surface contamination sealants and paints.
- 11. Coverage of Hydro-lazing, f reon, actd 7End sandblasting decon efforts.
l . l i a Figure 2.1.3-16
3884029770
- 12. Coverage of use of mini accelerator radiography.
- 13. Surveys for unrestricted release.
6/80 - 3/81 Health Physics Tech "C" 1. Assist in Health Physics activities at major control points in the following areas: drywell, fuel floor, torus proper, moist sep. 2. Initial surveys for MRFs and breach surveys. 3. Coverage of MSIV and relief valve rebuild. 4. Coverage of core spray sparger replacement, shielding, monitoring, surveys. 5. Torus proper modification of supports, hydrolazing, sandblasting, welding, surveys. 6. Feedwater Heater Removal -Breach of Feedwater Etr. Breach of secondary containment, cut-up, and preparation for shipment. 1 7. Performed ultrasonic inspection of scram header on a routine basis. 3/79 - 6/80 Health Physics Assistant Tech. - PBAPS 1. Assist at major control points, l 2. Surveyed low level radwaste. i J 3. Conducted clean area surveys. 4. Assisted in surveys in Torus rooms. RHR's, isolation valve rooms, RWCI valve, pp., and filter rooms recombiner and various othe-areas. PROFESSIONAL AFF LATIONS l l Appointed Limerick Generating Station Red Cross Blood Drive Chairman 10/86 4 i : i i i Figure 2.1.3-17
svv vc<< <v TECHNICAL SUPPORT PHYSIC!ST NAME: Martha A. Christinziano ![ EDUCATION AND TRAINING 1983 Rutger's University, New Brunswick, NJ MS Radiation Science / Health Physics 1981 Georgian Court College, Lakewood, NJ BS Physics, minor Chemistry Certified to teach Physical Sciences, (K-12) 7/87 Adv. Respiratory Protection (2 d); by Radiation Safety Associates, Inc. 12/86 Beta Dosimetry (2 d), by Sid Porter Consultants, Inc. 9/86 Air Sampling Techniques & Program Validation (2 d); by Technical Management Services Inc. 8/86 PBAPS Offsite Dose Assessment Computer Model (1 d); by Impell 12/85 Dupont Safety Training (3 d); by PECo l 7/85 Nuclear Professional Training (NUPRO) (3 wks); by PECo 7/85 RMMS Troubleshooting & Data Base (2 d); by Spectrum RMS { 6/S5 RMMS Circuit Boards & Calibration (2 d); by Spectrum RMS ll 6/85 Fitness for Duty (1 d); by PECo/NTS 6/85 RMMS Gen. Overview for MCR Operators (1/2 d); by i Spectrum RMS 4/85 RMMS Gen. Overview (2 d); by Spectrum RMS j 12/84 Radwaste Regulatory Awareness (4 d); by Chem Nuclear 10/84 Medical and Legal Aspects of Radiation Induced Cancer; (3 d); by University of Pennsylvania and 3 RMC/ canberra. 9/84 PEA Nuclear Subcommittee Meeting; (2 d); by PA Power Generation Ccmmittee. 1 1, Figure 2.1.3-18 1 i --y.,. 4 ~ ,~,-,,-s.--
3884029770 10/83 Disposal of Low Level Radioactive Waste; (2 d); by Pena State University. 9/83 Bi7R Recirculation Piping Seminar; (2 d); by Power Cutting, Inc. 7-8/83 PFCc Engineer Orientation Program; (3 week). 6/83 t Detectors in Nuclear Counting System; (. Canberra /PSE & G Co. 6/63 HP. Summer School on Internal Dosimetry. (1 wee., 4/83 NJ 'APS. Cur:ent Topics in Health Physics. (1 d) 1-2/83 Radwaste Management Workshop. (3 d) by ASME. 12/82 Brookhaven National Lab Environmental Monitoring Seminar (1 d) 11/82 EPRI Hydrogen Water Chemistry Workshop. (2 d) WORK EXPERIENCE 2/88 to Support Health Physicist, Present Limerick Generating Station Supervise the Technical Support Health Physics Group which includes the Dosimetry, Respiratory Protection and Protective Clothing, Special Projects, Environmental Monitoring, and EP Instrumentation Programs. Responsibilities include: Establish objectives for program area managers consistent with excellence in plant operation. Provide technical direction and resources as required to support program objectives. Reveiw and approve technical reports and' test results gnerated within program areas. Serve as Emergency Offsite Dose Assesment Team Leader. Serve as Plant Operations Review Committee Alternate. 10/84 to Effluent Monitoring Physicist-Philadelphia Electric present Company, Limerick Generating Station, Tech Support Staff t Figure 2.1.3-19
^ ^ ~ 3bd4U49//V' Responsibilities: RMMS System Manager; EP Dose Assessment Team Leader; maintain integrity of RMMS Rad. Monitors, RMMS routine and emergency programs; and ODCM: generate all effluent / dose assessment reports per Tech. Spees. Refuel Floor Area Coordinator (FRO): ' assisted in development of Outage Schedule, justified fabrication of Rx cavity grating for use on top of Rx cavity Seal Plate during (dis /re) assembly. 8/82 to Physicist Philadelphia Electric Conpany 10/54 Nuclear Services-Radiation Protection Staff Responsibilities: Peach Bottom (PB) U2 '83 Pipe Replacement (Corp Alara rep); EP Dose Assessment Team Member; PB U3 '84 Outage (Corp Alara rep); developed initial PB 10CRF61 program; PB Hydrogen Water Chemistry (Corp. rep); developed HP/QA audits and continuing education lesson plans for staff. 6/82 to Health Physicist-Brookhaven Naticaal Lab, Upton, NY 8/82 Internship provided training in HP/IH instrumentation, emergency response, dosimetry and respiratory protection. Directly responsible for determining neutron sprectral distribution @ National Synchrotron Light Source for PSAR submittal. 1/81 to Student teacher - Brick Twp. H. S., Bricktown, N. J. i. 5/81 Physics (Seniors) & Chemistry (Juniors) 6/80 to Tutor / Counselor - Upward Bound Program 8/80 at Georgian Court College. High school math and science. Professional Affiliations 1. Delaware Valley Chapter Health Physics Society 2. American Nuclear Society 3. PA Department of Envir. Resources-BRP HP call-out list. Figure 2.1.3-20 4 .w-- ,e. ...,c
3884029770 NAME: Robert K. Barclay EDUCATION AND TRAINING l 1977 University of Pittsburgh B.S. in Biology. 19'/0 Community College of Allegheny County A.S. in Radiation Therapy Technology 1981 University of Pittsburgh Graduate' School of Public Health M.S. in Hygiene (Radiation Health) University of Tennessee,-Oak Ridge Associated Universities Additional post-graduate credits'(12) in Health Physics and Microdosimetry 1. Panasonic Operations Course: University of Michigan, Ann Arbor, Jan-Feb. 1985-3veeks 2. Canberra SU-519 Whole Body Count Operations trainiqg, Jan. 1985 (Accuscan) Feb. 1987 (Fastscan) I week each 3. Compliance with new 10CFR20: Gaithersburg, MD 9/86 2 days 4. Delaware Valley Society for Radiation Safety-Sponsored Review for American Board of Health Physics Exam Course, Jan-June, 1986 (20 weeks - 4 hrs / week) 5. American Board of Health Physics Certification, Comprehensive, 10/86 WORK EXPERIENCE 7/84 to Philadelphia Electric Co. Present Responsibilities: Dosimetry Program; includiag external and internal dosimetry (Eberline, Panasonic, Landauer dosimeters and Canberra W. B. C. equipment), procedures, data review. Nuclear Employee Data System (NEDS) site contact. Supervision of contractor dosimetry employees. Special Projects: Drywell penetration neutron monitoring with Landauer dosimetry, Panasonic badge magazines, irradiation jig, irradiator field mapping. Figure 2.1.3-21 h.I)bO@(' y ~w v....- "SECHON COPY".
3884029770 8/82 to Union Carbide Corp. Nuclear Division 7/84 Responsibilities: maintenance and ongoing development of sodium iodide /hyperpure-germanium in vivo analysis program, body count result investigation, prediction equation analysis, preparation of purchase specifications, TLD system _ quality assurance, duties with medical staging area of plant emergency response team. 2/80 - 7/82 University of Pittsburgh Responsibilities: radiation safety surveys, personnel dosimetry review and investigation, air sampling, gamma counting and liquid scintillation programs, urinalysis programs, in vivo thyroid dosimetry, low-level radioactive waste processing, federal and state licensing applications and renewals. 10/77 - 8/79 Allegheny General Hospital Responsibilities: Laboratory Technici$n with hospital blood team Figure 2.1.3-22
3884029770 NAME: John F. Scone EDUCATION AND TRAINING 1972 State University of New York at Albany - 2 week seminar in X-ray Spectrometry II.. Widener University - B.S. in Business Administration 1977 Delaware Technical and Community College - basic course in Electricity 19R' Philadelphia Electric Company - Health Physics Assistant Technician Through A Technician Training 1985 Panasonic TLD System Operation Training Accuscan Whole Body Counter Operation Training 1987 Fastscan Whole Body Counter Operation Training Kepner-Tregoe Management Decision Training Seminar WORK EXPERIENCE 12/84-Health Physics Technical AssistLnt-Dosimetry Limerick Generating Station 1. Participate in development / review of Dosimetry procedures 2. Develop and implement methods for maximizing efficiency and productivity in the Dosimetry Dept. 3. Co-ordinate process to ensure Eberline TLD's are properly exchanged each month and returned for Read 4. Review operable status of Dosimetry equipment and report to Dosimetry Physicist j 5. Calibrate and requalification of Direct Reading Dosimeters 6. Perform monthly Eberline Cycle and related activities to ensure integrity of external Figure 2.1.3-23 i
388,029770 Dosimetry monitoring program (NUPERS), and to resolv4 discrepancies vs estimates 7. Interface with PECo Services Divisicn to correct deficiencies in Dosimetry computer programs (NUPERS/NEDS); suggest improvements to these programs 8. Prepare monthly Dosimetry Management Report 9. Assist as needed Review of NRC-4 for problems and resolutions 10. Monitor NUPERS Reports to identify dosimetry exposures results in excess to LGX guidelines 11. Maintain integrety and confidentiality of Dosimetry Personnel files 12. Interface responsibility with audit groups (OA, NRD, etc.) 13. Supervise the use of the Panasonic TLD System A. Maintain current operability staus for daily personnel TLD external estimates B. Review QC of system C Perform / supervise monthly calibrations D. Develop element correction factors E. Test new system lamps before use 14. Co-ordinate submission of Dosimetry Records to NRMS 15. Participate in Emergency Response Organization as Dosimetry, Bioassay, Respiratory Protection Group Leader at the TSC 16. Maintain Environmental TLD Surveillanc e Program in Unit #2 and off-site areas 12/83 Health Physics Technician "A"-Limerick Generating Station 9/83-12/83 Philadelphia Electric Company - Peach Bottom Health Physi Duties: Figure 2.1.3-24 m 4m-e- m,
3884J29770 Implement Radiation Work Permits, perform Radiation Surveys and advise / assist plant workers in an attempt.to keep radiation exposure as low as reasonably achievable per 10CFR Part 20. Progressed from Assistant Techniciar. to A Technician while at Peach Bottom and worked five i refuel outages as well as numerous mini-outages on both i units. Major areas and work covered as an HP include: 1. Torus Room - Structural Support and piping. modifications. Systems Breaches with and without Torus water on RHR and Core Spray. Room Decon after outages. 2. Torus Procer - Dewatering of Torus including mor.itoring river for underwater preinspection, Hot Spot locations and removal prior'to pump down, pump down and initial entry to Torus, decontamination of Torus, monitoring structural and piping modification. 3. Drywell - Initial entry to Drywell at units shutdown. Elevation surveys, breaches and airborne surveillance during outages. Control point worker as well as Control Point Leader, i A. Core Spray Line Replacement Unit 2. l B. RWCU Line Replacement Unit 2. C. Recire Pump Seal Replacements. D. Vessel pump down for Core Spray nozzle replacement, i E. Inboard and Outboard MSIV repairs and breaches. F. Subpile Room Sump pump down, clean out ar.d repairs. G. Downcomer initial entries and decon. I H. Clad overlap of both units of the Recirculation Headers and Risers and RER Loops. I. Recirc Motor removal and Replacements j including Decon & Transport between units. i ! l Figure 2.1.3-25 l ,, 3
3884029770 J. CRD removal and replacement (as well as repair) undervessel as well as Cor. trol Point Leader. K. LPRM Replacement under vessel. L. SRM Replacement under vessel. 4. Tio Room - Initial entry into Room for Tip probe caole change and repair. Trip r.achine breach and Decons. 5. CRD_ Rebuild, Area - Control point worker for CRD transport from Drywell to Rebuild Area, CRD disassembly, Decon & Rebuild. 6. RWCU Cell Rooms - Initial entries, Mods to system. Pre & post-shielding evaluations prior to work. Demin filter change out and breach. Post strainer breach and clean out. RWCU outboard isolation valve, Hot Spot removal (1000 R/hr) on Unit 2. RWCU pump breaches and repair with parts transport and Decon. 7. RHR Heat Exchancers - Breaches, decon repair of both heat exchangers and pumps. 8. Refuel Floor - Refuel outage general maintenance work for fuel change out. A. Jet Pump Removal from Unit 2 and movement to Refuel Storage Pool. B. Core Spray nozzle replacement with in vessel coverage Unit 2 and 3. C. Refuel Storage Pool Old Rack Removal and
- Decon, 1
D. New fuel receipt and inspections. E. Spent fuel bundle disassembly by GE with pin puncture coverage. F. Initial entries to Vessel pre & Post Decon inclusive of disassembly and assembly of Reactor Vessel Components. 9. Turbine Floors - Disassembly, Repair and modifications to EP & LP turbines, RFP Turbines, CIV's, Stop Valves and Control Valves. Sandblast _4_ Figure 2.1.3-26
38E402.770 coverage of LP' Turbine and RFPT spindles and buckets. 10. Moisture Seoarator Arena _LPT Condenser-Initials and Decon Surveys including Hot Well. Drain tank breaches and entries. Reducers Power entries to water boxes for tube leak. plugging. 11. Radwaste - HP & OC coverage for receipt and shipments of Radioactive materials - sources, condensate and RWCU spent resins, LSA compactors trash, contaminated tools and parts. 12. Ooerations HP Shift Coverace - Escort' operators as needed to Hi Rad Areas. 13. In Plant and Off Site Emergency Response Team Member - Participate in required drills for emergency situations. 14. In Plant and Outside Plant Rover' HP - Toured both units, Radwaste and outside plant-observant of any deviations in good HP practices and 10CFR20 infractions. Report to responsible TA fqr the area. 15. Special projects & Surveillance Test - As assigned. 16. -Control Rod Blad Stellite Roller Removal - CRB decon anc prep for shipment, and shipment i coverage 9/78-3/79 Artesian Water Company, William De - Corporate Property Account - maintain and audit investment work orcer in progress accounts 1/77-9/78 Piquet Security Systems - Site Commander - Supervised 15 man security force 2/73-12/76 Reynolds Metals Company - Cost Accounting Clerk - Responsible for maintenance and updating of a standard cost production file per budget information, industrial engineering machine rate information and approved manufacturing specification. Engineerine Technician (R&D) tested electrical stability and integrity of high voltage transmission cables. Constructed EV test circuits utilizing test transformers, Figure 2.1.3-27 ___ ~,.
3854029770 terminations and-splicing techniques. Interpreted data and reported to Electrical Engineers 5/66-10/72 Sun Oil Company R&D Technician - Performed quantitative and qualitative element analysis of X-ray spectrometry. Also operated a petroleum distillation lab. j 5 1/62-5/66 Avisun Corp. - Quality control and.Research Technician - performed physical and chemical analysis of polypropelene films and polymers. Supervised experimental film manufacturing process. . Figure 2.1.3-28
3884029770 NAME: Clark D. Smith EDUCATION AND TRAINING 1975 Kennard-Dale High School-College Prep l 1975 Millersville State College-Six semesters towards BA in Earth Science 3/79 - 8/79 Classroom training by General Physics Corp. at the Peach Bottom site as contracted by the Philadelphia Electric Co. This training covered mathematics, physical science, nuclear physics, radiation biology, radiation detection, ALARA, Radiation Work Permits, radiation, contamination and airborne survey techniques, emergency response, Health Physics standards and regulations, counting room instrumentation and techniques, radioactive waste, and chemistry theory and laboratores. 8/79 - 12/83 Periodic in depth classroom training by PECo in both health physics and~ chemistry totaling 726 hours. 1/80 Ultra sonic testing of Scram Volume Discharge Header water level. This training was given by PECo In Service Inspection Group. 1/81 Quality Control Inspection of Radioactive Waste Packaging and Shipment. This training was given by PECo Quality Assurance Department. 1/84 "Mitigation of Core Damage" given by General Physics Corp. 7/84 "Air-Pak 2.2/4.5 Field Maintenance" given by the Scott Co. "Quantitative Fit Testing of Respiratory Protective Apparatus Using Oil Mist Aerosols" given by Dynatech Frontier Corp. 10/84 Radioactive Waste Packaging and Disposal - 24 hours l 3/85 Radon Survey Techniques - 4 hours 9/86 Problem Solving and Decision Making (Kepner Tregoe) - 24 hours Figure 2.1.3-29 l
3884029770 1/87 Beta Dosimetry Workshop - 15 hours 6/87 Advanced Respiratory Protection - 16 hours 7/84-Present Technical Assistant - Plant ALARA Duties: Perform review and hold briefings / debriefings for ALARA category 1 and 2 jobs. Develop and supervise the program controlling use of portable ventilation devices. avelop and supervise the program controlling use and accountability of temporary shielding, coviding calculations and other shielding etechnical support when needed. Act as Health Physics shift supervisor (Sr. Technician) for Technicians to fill temporary job vacancies. Write and review procedures. Act as a sub-PORC Member to approve of both new and revised procedures for Health Physics and other groups such as Maintenance. Attend various Maintenance, Outage Planning and other meetings as needed to provide Health Physics imput. Walk down designated areas of the plant to troubleshoot problems and act as-a quality assurance inspector for Health Physics. Act as an outage coordinator for designated sections of the plant: coordinate efforts of Outage Planning, various work groups and Health Physics; routine plant walkdowns; catalyzed job onset and minimized job delays due to poor communication and misunderstandings. _2_ Figure 2.1.3-30
3884029770 Woax exPra: sC 12/83-6/84 Health Physics Technician "A"-Limerick Generating Station Duties: Filled job of Technical Assistant. Worked " vards set-up of training _ program. Wrote and reviewed procedures. Approved various procedures as a PORC member. Worked toward acquisition of contracts for personnel, servicet, and equipment. Approved purchases of equipment and supplies as needed to set up the haalth physics program. Helped set up Emergency Preparedness Plan and served as the Evacuee Control and Vehicle Decontamination Group Leader during emergency exercises. 3/81-12/83 Health Physics Technician "B"-Peach Bottom Atomic Power Station Duties: Running control points, writting RWPS,' radioactive shipment surveys, quality control inspection, emergency off-site survey team member and seven months of count laboratory work. 6/80-3/81 Health Physics Technician "C"-Peach Bottom Atomic Power Station Duties: Initial, Breach, and RWP update surveys. Job coverage and surveys as assigned including all areas of the plant. 7/79-6/80 Health Physics Assistant Technician-PBAPS Duties: Assist at major control points. Surveyed low level radwaste. Conducted clean area surveys. Assisted in surveys in the Drywell, RWCU system rooms, RHR rooms, Moist Separators Area, etc. Figure 2.1.3-31
3884029776 RADIOLOGICAL ENGINEERING SUPERVISOR NAME: Robert E. Leddy EDUCATION AND TRAINING 9/80 - 9/81 Georgia Institute of Technology Master of Science in Health Physics 9/78 - 6/E0 Manhattan College Bachelor of Science in Health Physics 9/74 - 6/78 Manhattan College Associate in Applied Science in Nuclear Medicine Technology 10/85 Technical Management Services "Designing Effective ALARA Programs" 12/S4 Chem-Nuclear Systems, Inc. "Radioactive Material Shipping-Regulatory Awareness Course" 9/84 General Dynamics, "ALARA Training Program" WORK EXPERIENCE 11/87 - Present Philadelphia Electric Company Radiological Engineering Supervisor Responsibilities: developing the ALARA program, procedures and guidelines; developing techniques to evaluate the effectiveness of the ALARA program; reviewing engineering and design changes to ensure inclusion of appropriate ALARA concerns; implementing a temporary shielding control program, interfacing with work groups to ensure that ALARA practices are incorporated into work activities; implementing an RWP Tracking and Exposure Control Computer system; serving as Secretary of the Station ALARA Review Committee; serving as Personnel Safety Team Leader during emergency exercises. Figure 2.1.3-32
3884029770 4/84 - 11/87 Philadelphia Electric Company ALARA Physicist Responsibilities: developing the ALARA program, procedures and guidelines; developing techniques to evaluate the effectiveness of the ALARA program; reviewing engineering and design changes to ensure inclusion of appropriate ALARA concerns; implementing a temporary shielding control progran., interfacing with work groups to ensure that ALARA practices are incorporated into work activities; implementing an RWP Tracking and Exposure Control Computer system; serving as Secretary of the Station ALARA Review Committee; serving as_ Personnel Safety Team Leader during emergency exercises. 6/82 - 7/83 American Electric Power Service Corp. Associate Scientist Responsibilities: providing corporate, technical support for a two-unit PWR, radiological review of design change requests, shielding design, corporate liaison between plant and ALARA-program contractor, dose assessment during emergency exercises, maintenance of emergency plan and procedures. 10/81 - 6/82 Georgia Power Company Health Physicist Responsibilities: assisting in the development of the ALARA program; surveillance of plant areas and personnel to ascertain compliance with proper housekeeping and radiation protection procedures; issuance of deviation reports and laboratory standing. orders; interfacing with regulatory agencies (NRC, INPO) on inspection findings; procurement of Health Physics instrumentation; dose assessment during emergency exercises; maintenance of emergency plan and procedures.
- Figure 2.1.3-33 J
3884029770 Josech W. Moon EDUCATION 1970 Graduated Bordentown Military Istitute, Bordentown, N. J. -1975 Graduated Ursinus College, Collegeville, Pa. B. S. Degree in Biological Science 1977 Brockhaven National Laboratory, Upton, Long Island, N. Y. i Health Physics Fellowship. (E.R.D.A.) 1980 Graduated Rutgers University, New Brunswick, N.-J. M. S. Degree in Radiation Science WORK EXPERIENCE 1986 to Philadelphia Electric Company Present Special Projects Physicist. Developed Field Isotopic Analysis system for E-Plan using intrinsic Germanium Detector and Multichannel Analyzer. Developed Operation Procedures,and incorporated system into E-Plan. Successful demonstration of fully operational system during practice drill. Conducted training of HP technicians on system. Managed Contamination Control Program and upgraded system of area tracking to include waste generation figures for consideration in priority for Decontamination. Functioned as Field Survey Group Leader during Emergency Drills. Conducted review of Instrumentation Program for INOP open item RP-6-1. Rewrote procedure controlling Instrument Calibration requirements. Implemented changes to program. Assessment of new instrument types. Obtained recertification of instrument Calibration Source. Wrote Operation Procedures for Alarming Dosimeters, Continuous Air Monitors and Underwater Radiation Monitoring Program. Implemented Engineering Controls for Drywell while Purge System inoperable. Layout of Outage Exposure Control Points. Implemented Station Radiological Deficiency Tracking Program. Figure 2.1.3-34 ~., _ _..
3884029770 1984-1986 Radiological Engineering Consultant at Palo Verde Nuclear Generating Station ~1982-1986 Corporate Health Physicist at Numanco Inc., RNode 1 Island 1984 Radiological Engineering Consultant to Morrison-Knudsen at Point Beach Steam Generator. Replacement Project Special Consultant to Duke Power Co., Mc Guire Station 1983 Radiological Engineer on plant staff at Grand Gulf Nuclear Station 1982 Functioned as Health Physics Shift Supervisor at Yankee Rowe Sr. Health Physics Technician at D. C. Cook Nuclear Power Plant Functioned on plant ~ staff as Radiological Engineer during start-up operations at Grand Gulf, Nuclear Power Plant Sr. Health Physics Technician at Ginna Station 1981 Senior Health Physics Technician at Crystal River Sr. Health Physics Technician and Counting Room Shift Technical Advisor at Yankee Rowe 1980 Sr. Health Physics Technician at Yankee Rowe Sr. Health Physics Technician at.J. A. Fitzpatrick 1979 Sr. Health Physics Technician at Zion Generating Station ALARA Coordinator at Millstone Point Unit 1 I Decontamination Foreman at Surry Station, Steam Generator Replacement Project i 1978 Sr. Health Physics Technician at Zion Generating Station 1977 Health Physicist at Millstone Point j Professional Affiliations: j i i Health Physics Society; Arerican Nuclear Society l Figure 2.1.3-35 1
SPEC IFiC B U tJ D L E S I fl L I t-1 E R I C K U r4 1 T 2 INITIAL CORE TOMitlAL U-235 WT. PER BUNDLE BUNDLE TYPE AVG w/o 235 ButJDtES KG GE7-P8C1071 0.71 92 1.30 GE7B-P8CIB09't 0.9's 132 1.72 GE78-P8CIB163 1.63 160 2.98 GE78-P8CIB278 2.78 72 5.08 GE78-P8C I B2'68 2.'68 308 '+. 5 2 76's Total U Weight 139,5'53.31 Kg Total U235 Weight 2,581.82 Kg Average Enrichment - 1.85 w/o U-235 Table 1.1.3
Philadelchia Electric Cccoany Officers J. F. Paquette, Jr., President Chainren of the Board and Chief Executive Officer J. L. Everett, III Chairman of the Executive Comittee Corbin A. FtNeII, Jr. Executive Vice President-Nuclear R. G. Gilnere J. S. Kemper Senior Vice President - Finance Senior Vice President S Chief Financial Officer E. G. Bauer, Jr. R. F. Holman Senior Vice President Senior Vice President S General Counsel - Operations A. L. Parry, Jr. A. G. Mikalauskas Vice President Vice President C. L. Frit: C. Brenner Vice President Vice President M. W. Rinmerman J. W. Gallagher Vice President Vice President R. C. Williams S. J. Kcwalski Vice President Vice President P. G. Mulligan A. J. Weigand Vice President Vics President G. M. Leitch K. G. Lawrence Vice President Vice President D. M. Smith D. P. Scott Vice President Treasurer L. S. Binder Secretary FMS/vvg/02048802 Exhibit 1.0}}