ML20150E376
| ML20150E376 | |
| Person / Time | |
|---|---|
| Site: | 07003054 |
| Issue date: | 06/17/1988 |
| From: | Bauer E, Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20150E341 | List: |
| References | |
| 109068, NUDOCS 8807150104 | |
| Download: ML20150E376 (49) | |
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.BEFORE THE UNITED STATES NUCLEAR REGULATORY C0fttISSION i
DOCKET NO.'
70-3054 ll IN THE MATTER OF PHILADELPHIA ELECTRIC CCMPANY :
APPLICATION.
FOR i
AMENDMENT OF l
MATERIAL LICENSE NO. SNM 1977 FOR I
LIMERICK GENERATING STATION j
< UNIT NO.
2 1
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[ fr 1
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Edward G. Bauer, Jr.
Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania Attorneys for Philadelphia Electric Ccmpany 4
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l OEFORE THE UNITED STATES NUCLEAR REGULATORY C0hNISSION l
IN THE MATTER OF DOCKET NO.
70-3054 j
PHILADELPHIA ELECTRIC COMPANY:
APPLICATION FOR AMENEMENT OF MATERIAL LICENSE NO.
SNM 1977 FOR
' IMERICK GENERATING STATION UNIT NO.
2 On Decerrber 17, 1987, the U.S. Nuclear Regulatory-Ccmnission (NRC)
Issued'to Philadelphia Electric Cctroany-("Applicant") Materials License SFN-1977 which authorizes Applicant to receive, acquire, possess, transfer and use.certain special nuclear material contained in Instrunentation to be used at L1rnerick, Unit 2.
Based upon current schedules, Appilcant anticipates being ready to receive the first fuel-asserrblies for the initial core of L!rnerick, Unit 2 at the facility in Decerrbe r, 1988. Additionally, Appilcant wishes to c m form the inventory reaut rerrents of Condition 14 of License SFN-1977 to the present Inventory schedule currently in effect at Lirnerick Unit 1.
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e Accordingly. Appilcant hereby requests that liaterials License SNM-1977 i
be anended:
1) to authorize App 1tcant to receive, acquire, possess, store and deliver to a carrier for transport certain special nuclear material contained in fuel assenblies for I
Appilcants' Limerick Unit 2; and i
l-b 2) to revise Condition 14 of the License to provide that a physical inventory. shall be conducted annually to t
account for all sources End/or devices received and possessed under the IIcense.
Since the first Inventory under present Condition 14 would be required by June 17, 1988, it is requested that action on this request be taken by NRC prior to that date; and 3) to revise and update the resunes of the Fealth Physicists presented in Section 2.1.3 (Figures 2.1.3-1 thru 2.1.3-35) to reflect pranotions and Job title changes at Limerick Generating Station.
In support of this Application.for Amendment, Appilcant provides the Information set forth belcw. New information or infornation provided in the Octcber 26, 1987 Application which has been revised is Indicated by a bar in the right margin. A specific discussion of the basis for the requested change to Condition 14 of the license Is provided in Section 1.4.2, 1.0 General Information Applicant is a corporation organized under the laws of the Commonwealth of Pennsylvania with its princ' pal place of business at 2301 Market Street, Philadelphia, Pennsylvania 19101.
Philadelphia Electric Company is not aaned, controlled, or i
dominated by an allen, foreign corporation, or a foreign governnent. A list of Appilcant's officers, all of whan are citizens of the United States, is marked Exhibit 1.0, attached hereto, and incorporated herein. Application is hereby made l
pursuant to Section 70.22 of the Conmission's Regulations for a license authorizing Appilcant to receive, possess, store, use and deliver to a carrier for shipment certain special nuclear material contained in fuel asseablies at the Appilcant's Limerick Generating Station Unit 2.
The IIcense is requested untti Issuance of an operating IIcense for Limerick Unit 2.
The first fuel assenb;Ies for the initial core are anticipated to arrive on site in December 1988.
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1.1 Reactor and Fuel 1.1.1 Reactor Location-The Limerick Generating Station Unit 2 is presently i
under construction on a site located in Lim 9 rick Township, Montgomery County, Pennsylvania approximately 25 miles vast of Philadelpi Pennsylvania. The canpany currently own c'
operates Limerick Unit l'on this site pt.
NRC Operating License NPF-39.
Constructi Limerick Generating Station Unit 2 was au..
zed by_ the Atomic Energy Comnission in ConstrucWon Pennit CPPR-107 issued on June 19, 1974 (Docket No.
.i-50-353).
1.1.2 Fuel Assembly Description There will be 764 fuel bundles (and spares as required to replace defective bundles) In the Initial core of Limerick Unit 2.
A description of the physical dimensions and naterials of construction used in each of these fue1xbundles is contained in Section 2 of the General El~ctric e
Standard Application for Reactor Fuel (GESTAR-II:
GE documents NEDE-29011-P-A-8, and the United States Supplenent NEDE-24011-P-A-8-US, May 1986),
which are incorporated herein by reference.
1.1.3 Enrichnent Section 2 of GESTAR 11 also contains a complete description of the enrichment and weight of the uranium used in each assembly. -The specific bundle types, the nutber of each, enrichnents in U-235, i
and U-235 weights in the initial core of Limerick Unit 2 are presented in Taole 1.1.3, which is attached hereto and incorporated herein. Table 1.1.3 diso states the total U and U-235 weights and
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the average enrichment of the 764 bundles. The
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total weight,of each fuel bundle is approximately 272 kg.
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I 1.1.4 Isotopic Content t
The initial core will nominally contain 139.54 metric tons of uranium, 2.58 metric tons of.<h'ch is specified as being U-235.
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..a 1.2 Fuel Storage Conditions 1.2.1 Fuel Storage Location The new fuel will be stored outdoors _in the new y
fuel-storage area which.Is located on the west side of the plant as shown In' Figure 1.2.1 which is s
attached hereto and incorporated herein..The fuel j
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 i
in the new fuel storage vaults at Limerick. Unit 2.
1.2.1.1 Storage Area and Array Description The new fuel storage area will be enclosed by an eight (8) foot high fence and provided with a watchman 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 111uninated to pennit night surveillance of the fuel.
The fuel for the initial core of Unit 2 (764 assemblies) will be stored in three (3) plies with sixty-four (64) containers in each plie stacked four (4) high and sixteen (16) across; and four (4). plies with forty-eight (48) containers in each
-j-plie stacked four (4) high and twelve (12) across. A spacing of twenty-five j;
(25) feet will be maintained between any two plies and between each plie and the new fuel. storage' area-fence. The fuel will be stored in the outer wooden Reactor Assemblies (RA) containers that.
they were shipped in and additionally each plie of fuel will be covered by a five-sided box manufactured out of corrugated steel. The weight of each It pile of fuel is sufficient to withstand windstonns of 100 year mean recurrence Interval.
1.2.2 Activities in Adjacent Areas
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In the areas adjacent to the new fuel i
storage area there exist pernenent a
buildings.
In addition there is a i
permanent building that will be used for
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offices or a change house. There is also a substation adjacent to the new fuel storage area on the north side.
Activities in adjacent areas 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 Equipnent The Limerick Unit 2 spent fuel pool, as Illustrated in Figure l.2-15 of the Limerick Final Safety Analysis Report (FSAR), is an Integral structure within the reactor enclosure. The fuel storage 7
facilltles and handling equipaent are designated Selsmic Category I and are protected against the nost severe environmental ph'enmena which have 'been postulated to occur at this site.
1.2.3.1-Spent Fuel Pool The Limerick Unit 2 spent fuel
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i 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 r
fuel storage racks within the SFP have a storage capacity of 2,040 fuel assemblies (267
- percent of full core load) with sufficient space to expand to a maximum capacity of 2,862 (375 percent of full core load). The storage racks i
are designed to meet Seismic Category I requirements as defined in Regulatory Guide 1.13.
These racks are designed
?i to withstand the effects of a il design basis earthquake (DBE) and remain functional, in accordance with Regulatory Guide 1,29 and the Code of Federal Regulations, Title 10, Part 50. Diagrans of the spent fuel racks are in Figures 1.2.3.i(93 through 1.2.3.1(h) which are attached hereto and incorporated herein.
(It should be noted that the typical corner cross-section sketch on Figure 1.2.3.1(c) and
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the enlarged sketch of the typical corner cross-section on Figure 1.2.3.1(e) are conceptual in nature and
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. i e nominal 6.625 Inches center-to-centor spacing is maintained between fuel assenblies In a rack as Indicated in Section 9.1.2.2.2 of the Linerick FSAR). The spent fuel racks consist of six basic structural components: top grid casting, bottan grid casting, poison cans, side plates, corner angle.ctlps, and adjustable foot assenbiles. The top and botton cast aluninun grids sandwich the square cross-section poison can into pockets In a~ checkerboard arrangenent. The grids are held in place by aluminun side plates and corner angles bolted and rivetea with aluninum blots and rivets. The i
rack modules are Individually leveled with adjustable foot assenblies at the four corners r
of the bottom grid..The storage racks are mcdular, free standing, top entry racks designed to neintain the spent (and new) fuel in a space geometry whereby each fuel assembly has a neutron poisoning material between it and any adjoining fuel assenbiles. This precludes the possibility of criticality under nonnal and abnormal 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 polson cans, and the 11x12 racks have 66 polson cans.
Figure 1.2.3.1Cg) Illustrates the initial layout of the spent E
fuel racks in the spent fuel pool and Figure 1.2.3.1(h) illustrates the layout for maximun capacity. The poison cans consist of two 0.090-inch thick concentric square
.i aluminun tubes with four l
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> N (5.25 inches wide, 152* Inches long, 0.080 Inch ~ thick) plates-1 of Boral (Boron Carbide In an R
aluminun composite matrix,-
with an aerial nominal density-of 0.028;G/CM 3 In the annular gaps. The Boral is so positioned that it overlaps the fuel pellet stack length..
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In the: fuel assenbiles 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 anc vacuum leak tested through a 13/64 Inch hole, which is then plug welded. to -
Isolate the Boral ' rem the pool water. All.meterials used for 1
construction of the racks are specified in accordance with the issue of the ASTM specificatler. In.effect on March 1979, as appilcable.
1.2.3.2 Reactor Enclosure Crane-
.f The reactor enclosure crane.ls a bridge crane mounted on runway rails that are supported by the reactor enclosure superstructure.
The reactor enclosure crane is -
designed to handle loads with s
a maximun welght of 125 tons while maintaining a minimun safety factor of 5.
There is also an auxillary holst with a design caoacity of 15 tons.
The reactor enclosure crane Is designed to prevent movenent of the crane over the new fuel and spent fuel storage areas In the absence of specific action by the crane operator to allow such movement.
4 Figure 1.2.3.2, which is attached hereto and incorporated herein, 111ustrates the areas of restricted crane movanents.
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1.2.3. 3. _ Fuel Servicing. Equipment '
The fuel servicing equipment.
consists of' apparatus as described below; a)
New Fuel' Inspection Stand
.p-The new 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 a 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 simp 1tfied layout of the new fuel handling facIIItles.
b)
Channel Handling Tool The channel handling tool (Figure 1.2.3.3(b)), which is attached hereto and incorporated herein, is used in ccnjunction with the fuel preparation machine to remove, install, -and transport fuel channels in the fuel storage. pool. The tool is composed of a handling-ball, lock / release knob, extenslor, shaft, angle guides, and clamp arms ttat engage the fuel channel.
The channel handling tool is suspended by its ball from a spring balancer'on the channel hand 11.,g bocm located on-the fuel pool I
pe ri phe ry.
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Fuel Preparation Machine The two fuel preparation machines (Figure 1.2.3.3Cc)), which is attached hereto and incorporated herein, are nounted 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, Ic located between the two fuel preparation machines.
d)
General Purpose Grapple The general purpose grapple (Figure 1.2.3.3Cd)), which is attached hereto and incorporat ed herein, is a handling tool used generally with the fuel.
The grapple can be attached to the reactor enclosure aux 511ary holst, on the refueling pl atforns. The general purpose grapple is used to move new fuel fran 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 Storage Area The fire protection In the new fuel storage area consists of five-sided boxes merufactured out of corrugated steel placed over each plie of fuel.
Sufficier.t fire hose line will be available such that water can be directed to the fuel fran two
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Lightning protection will be provided by an overhead transmission line.
Access to this area will be controlled as described in the Physical Security Plar (see Section 1.3 of this
.acolication).
1.2.4.2 Reactor Enclosure All fire protection systeam within the reactor enclosure air-lock and the refueling floor will be in place and operative at the tine the fuel is transferred to the refueling floor.
Section 9.5.1.of the Limerick Generating Station FSAR describes the reactor enclosure fire protection systans.
1.3 Phys!;al Protection App 1! cant will -tore che Special'bbclear Material to be received in the Main Protected Area as defined in tne approved Physical Security Plan.for Limerick Generating Station Unit I 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 requirenents of 10CFR73.67 1.4 Transfer of Special Nuclear Material 1.4.1 Responsibility for Fuel Shipment General ElectriciConpan/ (the fuel fabricator) is responsible for shionent 5? the fuel asseablies from the fabrication plant in Wilmington, North Carolina to the Limerick site.
In i
addition, any return of fuel assembiles to Wilmington, N.C. (for any reason) is the responsibility of the General Electric Campany. The fuel will be shipped to the Limerick site in the General l
Electric Model RA-2 or RA-3 container authorized for use as a Fissile Clasa i container by NRC Certificate of, Core 11ance USA /4986 for the transport of j
fisslie radloactive material in the fonn of General Electric reactor fuel.
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1.4.2 SNM Control and Accounting Practices SNM control'and accounting practices that comply with the appilcable
. provisions of 10CFR Pert 70.52 cre described in procedures "A-44-P e;edure for Special Nuclear Material Acccunting" and "ST3-97-350-0 Annual StN Inventory".-
A-44 is attached as Exhibit 2.
ST3-97-350-0 is attached as Exhibit 3.
These proceduces provide.for an annual Inventory of Special Nuclear Material rather than the six (6) mcnth Inventory presently provided in Condition 14 of License SNS-1977.
Changing Condition 14 from a six month to annual basis for '
i SM3 Inventory will not lead to any adverse affects or significantly comrcmlse the accounting of Std at the t te.
1.5 Financial Protection and Indemnity The app 1! cant has currently purchased the maximur, 1
available nuclear liability insurance for the Limerick
_ i site from American Nuclear Insurers, policy No. NF-284
.i and from Mutual Atanic Energy Liability Underwriters,
'I policy No. MF-113. The original copies of the policies are on file with the NRC.
2.0 Health-and-Safety 2.1 Radiation Control This section provides information regarding radiation scfety at Limerick Generating Station.
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2.1.1 MinIntm Qualifications for Positions having Radiation Safety Responsibilities.
The minimun qualifications for the Senior Health Physicist (Radiation Safety Off!cer) are those outlined in Section 4.4.4 of 41SI/ANS-3.1-1978, "knerican Nat tor.a1 Standard for Selection and. Training of Nuclear Power Plant Personnel".
The applied Health
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Physicist and Support Health Physicist (assist RS0s) have as a minimun a four-year degree in Health Physics or a related field and at least 24 months applied Health Physics experience.
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i 2.1.2 Responsibilities for Radiation Safety Personnel The responsibilities for the key radiation safety personnel are. described by. the following "Radiation Safety Progran" 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 I
for the Senior Health Fhysicist in his absence.
The objectives of health physics operations are to:
6 a) detect. !dt.ittfy, and define rwGiat'on hazards, b) provide protection for personnel against radiation hazards, t-c) control plant-related radiation exposures i.
(occupational and general public) to levels As Low As Reasonably Achtsvable (ALARA).
d) conduct plant activities in conformance with authorized procedures and appilcable regulations.
Thsse objectives are acconpi tshed or enhanced by the various training prograns, by the use i
of prepared Health Physics operating-procedures, by periodic review and revision of procedures, by evaluation of activities for i
ALARA purposes, and by the control of plant operations to minimize occupational exposuras and releases to the envirornent.
Health Physics operations include the posting, notification, and reporting provisions of 10CFR Part 19 and General &nployee Training, or in sone cases task-specific Instruction, provides the requisite Instruction to workers, 1
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3 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, with 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 l
describe the management cannitment, organization, responsibilities, authority, training procedures, and review techniques which irrplement Regulatory Guide 8.8 (Rev 3),
Regulatory Guide 8.10,- and Regulatory guide 1.8 (Rev. 1-R).
As described in Section 12.1 of the Limerick FSAR, a formal ALARA review 1
program which is consistent with the guidelines given In Regulatory-Guide 8.8 was implemented during the design and construction phase. The qualification requirements for 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
.i oppilcable' regulatory guides.
The portion of Ii the Health Physica program related to special nuclear materials is outilned as follovs:
I' RADI ATION-PP.0TECT ION-PERSONtJEL i
Senior Health 'hysicist (Radiation Safety Officer)
The Senior Health Physicist reports i
through the Station Superintendent of Services to the Plant Manager and receives technical direction and support fran the o#fsite Director - Radiation Protection Section.
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'I 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 / responsibilities in this capacity include:
a) developing and InplementIng an
' effective radiation exposure control and' measurement program In-consonance with the PECo ALARA policy.
b) ensuring that exposure measurenent and control programs are periodically reviewed and that appropriate revisions and corrective J
acticns are taken when the results.
of these programs indicate that such actions are needed to conform to the
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PECo ALARA policy, j
c) preparing and reviewing procedures for inplementing the ALARA poIIcy.
.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 Co7mittee 6
(PORC) level, of facilities, activities, and eculpnent that can affect potential radiation exposures.
f) supervising radiatica, surface centanination, 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.
g) participating in the development of training programs related to the ALARA progran to ensure that personnel are aware of PECo management's ccermitment to ALAPA and are Instructed in ways of reducing exposures that are related to verk in radiation areas or that involve radioactive materials.
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.'. s h) supervising the radiation surveillance programs and the collection, analysis, and evaluation of data fecm radiological surveys and from personnel exposures and
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doses including the use of the radiation work permit data.
6 I) supetvising and training of the health physics staff.
-J) providing appropriate data and Information related to the ALARA l'
program and results to the Plant Manager and to the Director, i'
Radiation Protection Section, to keep ccmpany management informed about the program.
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k) acting Radiation Protecticn Manager.
In his absence a person temporarily filling,this position will have'a BS degree in engineering or science with tvx) years experience in radiation protection, one year j.
of which shall be nuclear power l
plant experience, six months of which will be on site.
Health Physicist (Assistant Radiation il Safety Officers).
The Support Health Physicist, the Applied Health Physicist, and the Supervisor, Radlological Engineering report to the Senior Health Physicist and implement the PECo ALARA program and perform functlens as assigned by the Senior Health Physicist.
Specifically the Health Physicists are responsible for:
a)
Performance of radiation, surface contamination, and j
airborne activity surveys and collection, analysis, and maintenance of associated data.-
t b) control and Implementation of personnel dosimetry requirements and the collection, analysis, and maintenance of associated data.
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c) classification and operation of barricades, control points, and access. conditions.
'd) performance and/or supervision of decontamination of areas, equipment, and personnel.
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e) 'surve(' lance of' laundry operations and radioactive material transfers, f) maintenance arid performance of equipment within his review.
g) respiratory protective equipment and protective clothing'and equipment program operatlons, t
h) bloassay ind Internal dose detenninat Ions.
1) monitor effluent releases to ensure ecmpliance with Technical Specifications.
2.1.3 Training and Experience The experience of the Health Physicists 1s-presented in Figures 2.1.3 2.1.3-35 The training necessary for Health Physicists is outlined in Sectlen 12.5.3.5 of the Limerick j
I FSAR.
i 2.1.4 Procedures and Equipment for Checking
'f Contamination i
The Health Physics personnel will be notifled i
when a shipnent of new fuel or Instrtrnentation containing Special Nuclear Material arrives on site. Health Physics personnel shall perform ccrnplete radiation and contamination surveys of the outside of the transport vehicle to ensure that the radiation levels are within-acceptable limits.
If all survey' data is within limits, the vehlqle will proceed with unloading.
If survev data is above established limits, appropriate actions, as defined in Plant Operations Review Ccmnittee (PORC) approved written station procedures, will be followed.
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2.1.5 Calibration and Testing of Instrumentation All instruments shall be tested and calibrated routinely in accordance with approved station procedures.
Sur/ey Instrunents will be callbrated on an annual basis.
Instrument calibration will be perforned by quallfled station personnel or through a vendor.
Each Instronent will bear a sticker Indicating the date when recalibration is due.
2.1.6 Procedures and Equipment Used to Meet Applicable Sections of 10CFR Part 20 The Limerick Generating Station will be operated and maintained in such a menner 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 acconplish this goal are described in Section 12.5 of the-Limerick FSAR..
4 2.1.7 Provisions for Disposal of Radioactive Wastes The smell quantitles of radioactive waste generated in the surveying of SNM ltens for contanination 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 Mininom Oualifications for Positions Having Nuclear Criticality and Fuel Handling Responsibilities The key position having nuclear criticality safety and fuel handling responsibilities is the Reactor i
Engineur. He is responsible in as much as he generates procedures for fuel handling that i
incorporate nuclear critica11tv safety guidelines.
These procedures are then reviewed by the Plant Operations Review Conmittee.
The mininun j
qualification for the Reactor Engineer are those stated in ANSI /ANS-3.1-1978 Section 4.4.1.
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f 2.2.2 Responsibilities for Personnel Having Nuclear Criticality and Fuel Handling Responsibilities.
The key personnel responsible for nuclear criticality safety and fuel handling is the Reactor -
Engineer.
The Reactor Engineer reports to the Technical Engineer and is responsible for determining and monitoring core performance and for establishing appropriate ope"ating guides and procedures to ensure safe economical reactor operation in conpliance csith the operating Ilcense and technical specif: cations..The Reactor Engineer is responsible fo nuclear history, and the performance of equipment under purview.
2.2.3 Shipping Containers The new fuel assenblies will arrive at the site In the General Electric RA shipping containers. i Upon receipt, the new fuel shipnents wlit be directed to the new fuel storage area previously descr,1 bed in Section 1.2.1.1 above. The new fuel bundles-will receln in their original shipping containers until such time that they are transferred to the reactor enclosure.
2.2.4 Huclear Criticality Safety of New Fuel Storage Locations 2.2.4.1 New Fuel Storage Area The new fuel storage area is constructed e
so as to provide a well drained area such that should the aroa be flooded, water will not be retained around the stored shipping containers. A criticality safety analysis for fuel asseablies In j
the Inner retal containers for both l
Flooded and non-flooded conditions is set forth in NRC Certificate of I
i Conpliance USA /4986/ for.the General Electric RA-Series Shipping Package. The review has demonstrated that the RA conteiner loaded with the most reactive proposed General Electric BWR fuel meets the established Fisslie Class I t
requi rements defined by 10CFR71.
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 appilcation.
In the hand 1Ing and Inspection sequence on the. refueling
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I floor, two (2) bundles will-be In the inspection stand and two (2) additional bundles will be standing upright within their nwtal 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 secuence on the refueling floor.
2.2.4.3 Storage of New Fuel in the Spent Fuel Pool The spent fuel storage facl!ity is designed to store new and irradiated fuel assemblies so that a k-eff less than or equal to 0.95 is nalntained, I'
assuming that the fuel storage recks are fully loaded with fuel of the highest anticipated enrichnent and flooded with non-borated water, in compilance with 1
This is achieved through use of a neutron poisoning material (Boral) sandwiched in the racks between adjoining fu~el asseablies to ensure suberiticality by at a
least five (5) percent hk 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.
'l The presence of Boral is verifled by i
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 !n-service testing program is described in Section 9.1.2.4 of the Limerick FSAR.
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2.2.4.3.1 Validation of the Calculational Method for Nuclear Criticality Safety Tivs validation of the calculation method for nuclear criticality safety of fuel stored in the i
spent fuel pool 15 contained in Sections 9.1.2.3.1.1 through 9.1.2.3.1.6 of the Limerick FSAR.
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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 arrengements of General Electric Ccrnpany, in container Model RA-2, or RA-3 authorized for use as a Fissile Class I container. General Electric Company is responsible for shipment of the fuel bundles from the fabrication plant in Wilmington, North Caro 1Ina, to the Limerick site.
Fuel will be shipped by truck trailers in quantitles of up to sixteen (16) containers per load.
Each of these containers will contain tvo (2) fuel bundles.
Fuel bundles will be received at the storage site in the shipping containers mentioned above. Upon arrival at the new fuel storage area, the containers will be monitored for external radioactive contaninat 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-lift truck. The shipping containers will be placed in predesignated locations within the new fuel storage area.
Experience in shipping fuel in the General Electric Model RA-2 and RA-3 i
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-lift truck will renove one fuel storage container at a time to be placed on a flatbed trailer for transportation to the reactor enclosure ale-lock in quantitles not exceeding six (6) containers per load. The route to be taken in the actual move of the new fuel fran the new fuel storage area to the reactor enclosure air-lock is indicateo on attached drawing Figure 1.2.1.
The distance to be traveled is approximately 900 feet.
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- 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 wi11 be removed. 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 refueling 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 From Shipping Container and Inspection Before the fuel bundles are renoved, the metal RA containers (lids removed) are suspended and placed in the unloading station located near the new fuel I
inspection stand. The metal container end piece is then renoved. Health
_l Physics personnel make o survey of renovable contamination on the outside of
?
the plastic bag covering the bundle.
The bundle is then visually inspected for i
damage. The respective fuel bundle Is removed via the auxiliary holst or cherry picker and transferred to and secured In the new fuel Inspection stand.
Figure 2.2.5.4Ca) ano Figure 2.2.5.4Cb), which 1
are attached hereto and incorporated herein, give a simollfled layout of the new fuel handling facilities.
The acceptance inspection is performed with either one or two fuel bundles in the 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 discrepancies noted.
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-2.2.5.5 Channeling in the New Fuel Inspection Stand Upon canpletion of the fuel Inspection, each bundle is channeled in the new fuel inspection stand. A channel is selected and positioned above the fuel bundle.
The channel is laaered onto the fuel' bundle and secured with the channel fastener assembly.
Following the ccepletion of the channeling process, each assenbly/ s transferred to a storage I
location in the spent fuel storage pool by the refueling bridge.
(See Figures 2.2.5.4(a) and 2.2.5.4Cb) which are.
attached hereto and incorporated herein).
2.2.6 Exemption 2.2.6.1 Criticality Accident Requirenents The procedures and storage facilities described in this application provide assurance that inadvertent criticality cannot occur during receipt, possession, and storage of new fuel assenblies at Limerick Generating Station.
The Gene, al Electric shipping containers f
in which fuel will be received neet the Fissile Class I requirements defined by 10CFR71.
In addition, the spent fuel pool is designed to ensure s
subcriticality by at least five (5) percentAgk under all conditions (see Section 2.2.4.3).
Furthernere, the procedures for unloadir.g and Inspecting the new fuel are based in part on the preventien of criticality during these ope rat i ons.
Based on the above discussion, Philadelphia Electric Company requests exemption frcm the requirements of 10CFR70.24 as provided in 10CFR70.24Cd).
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2.3 Accident Analysis.
2.3.1 New Fuel Storage Area In the new fuel storage area, only one shipping container at a tine will be handled by any single fork-lift truck during loading and unloading activities. General Electric Company has conducted hypothetical accident condition tests of the Inner metal shipping containers in the sequence specified in Appendix B to 10CFR71 and the Inner metal containers passed the acceptance criterla as described in NRC Certificate of Compilance USA /4896 for the General Electric RA Series Shipping Package.
2.3.2 Spent Fuel Pool No adverse reactivity effect is expected from dropping a fuel asseTbly on top of a fully loaded storage rack during hand 11ng because of the large water thickness (approximately 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 (3ee 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 geometry without the dropped fuel. A more detailed discussion of -
this case can be found in Section 9.1.2.3.1.5Cb) of 1
the Linerick FSAR.
The structure of the racks is designed to renaln functional and to maintain the required spacing between stored fuel assenblies in the event of impact of a fuel bundle dropped on the racks form an elevation of 36 inches.
See Section 9.1.2.3.2.1 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.
Extreme caution is exercised during the fuel handling to prevent a fuel assembly from striking another fuel assembly or other structures.
In the unlikely event that a fuel assembly would be i
dropped, all fuel handling activities would be stopped. An assessment of the damage would be nede and appropriate corrective action taken prior 4
to authorization to continue fuel handling activities.
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Correspondence with' respect to this Appilcat!x1 should be addressed to:
Edward G. Bauer, Jr., Esq.
Eugene J. Bradley,Esq.
I 2301 Market Street
' Philadelphia, PA 19101 4,
Respectfully. submitted,-
PHILADELk IA LECTRIC COMPN #
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BY:_' -
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.i C0t?OMEALTH OF PENNSYLVANIA -
- ss COUNTY OF PHILADELPHIA S. J. Kowalski, being first duly sworn, deposes and says:-
That he Is'Vice President of Philadelphia Electric Cormany, the Applicant herein; -that he has reviewed the foregoing Application for kendment of the Special Nuclear. Material License for L1rnerick Generating Station Unit No. 2 and knows -the contents thereof; and that the statements and rnatters set forth therein are true and correct to the best of his knowledge, information and belief.
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Subscribed and sworn to s.'
t' before this y 7 day of Apri1, 1988 L
lkt rd Notary Public MELANIE R CAMPANELIX Notary NbAc, Philadelchla Philadelels Co, My CMtn'tt 04 traires febtwy 12, 1990 5
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j,: h-i t:' z... e,.., u-,,, 1 1 1-l i LIMERICK GENER ATING STATION UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT a HIGH DENSITY SPENT FUEL STORAGE DROPPED FUEL ASSEMBLY ACCIDENT F i;;= e 2. 3. *: R E V.10,09/82 u
j h b t.t V 4 7 1. I V - m SENIOR HEALTH PHYSICIST - RADIATION PROTECTION OFFICER ~NAME:- Gary W.' Murphy . EDUCATION AND TRAINING 1987 General Physics Corporation, Royersford, Pa. Certified Senior Reactor Operator I 1979-1980 University of North Carolina, Chapel Hill, School of Public-Health, Department of Environmental' Sciences.and Engineering M.S.P.H. Radiation Protection with j concentration in industrial hygiene 1976-1979 Harvard University, School of Public Health Graduate level courses in:- .l Radiation Biology 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 .}l to Present Generating Station I 1. Responsible for the implementation of the Radiation Protection Program at i Limerick Generating Station. 2. Provides administrative and technical direction to the Health' Physics staff Jn the areas of Dosimetry and Bioassy, j Respiratory Protection, ALARA Programs implementation, Radioactive Effluent Monitoring, and Radiation Monitoring Instrument Calibration and use. i O 'i 3. Serves as a member of the. Plant Operation Review Committee. i f $l Figure 2.1.3-1 4 p -( y..*. 7 7, p r- _m _;> y 7 _ _ _-_ 7 - 77 7y _y 4-
p p ~ 4. Ovorsoos ths'dsvelopmsnt and implemGntation of training for H3cich-Physics Professionals and Technicians.
- 4. -
,3 l 11/83 to 11/87 -Support Health Physicist, i, Limerick Generating StationL Supervise the Technical Support Health Physics Group which includes.the Dosimetry, Respiratory "l Protection, and Protective Clothing, Special Projects, Enviromental Monitoring, and Radwaste t' and Radioactive' Material Shipping Programs. Responsibilities include: Establish. objectives t ~ 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' l' j Emergency Offsite Dose Assesment Team Leader, j Serve as Plant Operations Review Committee j 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. 4 jl 9/80 - 3/83 Engineer / Health Physicist a Mechanical Engineering Division ,t Philadelphia Electric Company Lead Project Engineer,. Limerick Radiological Environmental Monitoring Program (1 Project Engineer, Limerick Plant Process and-Area Radiation Monitoring Systems j Lead Project Engineer, Limerick Emergency 1 Offsite Dase Assessment System and Effluent Monitorin7 System I 9/76 - 7/79 Senior Research Assistant, Laboratory of Radiation Biology, Harvard University, School of Public Health 1 3/74 - 7/76 Tufts University Medical School, Senior g j Research Assistant, Sidney Farber Cancer k Research Center i I Figure 2.1.3-2 ,) f
3Bb4Ud>//U APPLIED HEALTH PHYSICIST DATE APPOINTED: March 1983 NAME: Richard J. Titolo EDUCATION AND TRAINING 1976-1980 Geo gia Institute of Technology B.S. in Health Physics f (Mngna Cum Laude) 1980-1981 Georgia Institute of Technology M.S. in Health Physics (Summa Cum Laude)
- January, 1982 Midlands Technical College - One week Regulatory l
Awareness Course in 49 CFR, Chem Nuclear Systems, Inc. 1982 Georgia Power Company-Supervisor Safety Training Observation Program
- May, 1983 PECo, Kepner Tregot (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 Trainin,-3 weeks, Nuclear Plant Systems, 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 i Figure 2.1.3-3
3834029770
- July, 1987 Health Physics Audits-2 days 140RK EXPERIENCE 3/83 to Applied Health Physicict, Limerick Generating Present Station Duties:
General: Responsible for the' development and implementation of the station operational-Health Physics program. Functicr. In the capac ty 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 requi.ements and assist in procurement.
- 5. Supervise the Health Physics Supervisor, Health Physics Technical Assistants, and Technicians.
6. Supervise the ALARA Physicist and l Technical Assistants, and direct the development and implementation of the ', l station ALARA program. 7. Supervise procedure development'and review technical procedures for acequacy and accuracy. 8. Serve as Personnel Safety Team Leader (alternate) during emergencies. Figure 2.t.3-4 ~
~ ~ ~ 3884029770 10/81'- 3/83 Gsorgio_ Power Company-Hocith Physicist E.I. HStch Nuclear Plcnt
- l 1.
Responsibility for the development.of the site ALARA program in collaboration with INPO personnel. 9 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 and coordinated preparatory activities. 7. Davised protective clothing and respiratory protection guidelines and action levels. 8. Developed and provided ALARA training to plant personnel. 9. Performed plant inspections of health physics related activities, e.g. posting, procedural compliance, and directed HP staff in the resolution of f problems identified. 10. Investigated Radiation Occurrence Reports written by IU? technicians and provided direction for corrective j action. j i 11. Wrote Laboratory Standing Orders (LSO) at the reqJest of the HP Supervisor which provided instruction in the resolution of problems encountered by the HP operating organization; y supervised initial phases of LSO j implementation. O F'.gure 2.1.3-5 L 1
s 3884.029770. 12. Provided guidance and. technical support to the technicians 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 and revised ~ Emergency Plan Implementing-Frocedures. j 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. -i! procedu~res for emergency classification, j! offsite dose assessment and ,l recommendation of protective action. l 6. Supervised and dispatched offsite monitoring teams during emergency dr!.lls and exercises. .1 1/80 - 9/81 Georgia Institute of Technology Research lj'j Assistant Project: Correlation of absorbed dose to the j i 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, responsible for the calibration of the CaF TLD, i.e. formulation of glow curves. 9 Figure 2.1.3-6 i i 1i or .~'-s 1
~ ~ ~ ~ ^ 3884029770. 1 I. 9/80 - 12/80 ;Goorgia Instituto of=Tcchnology Roscarch - l 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 dosi neter. 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 i system configuration and testing, as well.as q preparation of associated equipment manuals. 6/79 - 6/80 Georgia Institute of Technology Research Assistant Research done on the field of environmengal impact from radioactive waste disposal. -i Responsibilities included the design, performance and interpretation of experiments utilizing columns packed with minerals from proposed disposal sites. Also, responsible for che activation of Na-23 at the university reactor. Employed the use of radioactlye tracers, appropriate electronics and a computer 1. program to analyze results. v z pro?_SSIONAL AFFILIATIONS J 1 j Health Physics Society 1 1 American Nuclear Society 'l 1 i U I } Figure 2.1.3-7 4 1
il 388402Y//U i JMggEh Stephen L. Tcylor EDUCATION AND TRAINING 1977 Red Lion Area Senior High 1983 Philadelphia Electric Company Health Physics and Chemistry Avsistant Technician through A Technician Radwaste Quality Control Inspector ISI Ultrasonic Irspector 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 Dhiladelphia 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 i Advanced Respiratory Protection Porter Associates-Beta Dosimetry Training WORK EXPERIENCE L 12/84-Present Health Physics Technical Assistant - Plant ALARA, Limerick Generating Station Duties: 1. General ALARA Responsibilities d A. Identifying areas where exposure can be reduced B. Pre-planning and reviewing activities which have d high potential exposures [ C. Providing technical assistance and guidance fer i on-site groups to ensure ALARA el.*ectiveness D. Evaluating procedures and methods for completing jcbs with minimum interference while maintaining e):posures ALARA Figure 2.1.3-8 i . I
3884029770 Pcg2 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-Porc 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-Porc of various Health Physics procedures, providing operation experience when requested D. Assisting in the review of RWP's for completeness and accuracy l E. Assisting in the development of an RWP and ALARA computer tracking program 3. Specific First Refueling Outage A. Refuel Floor Area Coordinator for first refuel activities I B. Assisted in development of an office enclosure utili=ed 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 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 Figuro 2.1.3-9 I l
3884029770 P go 3 E. Responsible for f abrication of a grating walkway to be utilized during Refueling. This grating will reduce worker exposures and reduce anti-C and respirator usage. 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 3/81-12/83 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 D. Informing H.P. Supervision of Control Point activities E. Reviewing paperwork, RWP!s being worked F. Ensuring appropriate surveys and representative air samples are performed G. Assigning Health Physics technicians to provide coverage during maintencance activitie-2. Laundry Radwaste/ Shipments Duties: A. Performing HP surveys for receipt and shipment of Radwaste and Laundry, assisting with paperwork for all shipments i Figure 2.1.3-10
Page 4 ~388.4029770 B. Quality control inspector for shipments of Radwaste including cask and trailer loading I C. Quality and Surveys' control inspector for [ loading, compacting of Radwaste containers i j 3. Operations HP.- buties on backshifts responsible for HP coverage in the plant. Work directly for l. operating shift supervision (trained in emergency etooedures) interim personnel safety team leader i on backshifts d i 4. Health Physics Crewleader of control points during following jobs: A. Refuel Floor l. Reactor disassembly, fuel exchange, LPRM/CRB removal-replacement, jet pump removal-replacement 2. Feedwater sparger modification, involved draining reactor vessel and decon,. installing shielding on vessel internals, removing old spargers, machining vessel walls, shrink fit of new spargers and i installation j B. Turbine Deck 1. Breach turbine hoods, disassemble turbines, repair rotor, sandblast repair -l turbine diaphrams, coverage on reactor j feed pump turbines and feedwater heaters 1 C. Drywell j 1. Breaching systems, removing mirror ~ insulation, perform internal heat stress of welds, clad overlay on RHR-recire 3 piping a 6/80-3/81 Peach Bottom Atomic Power Station Technician "C" I Perform surveys, provide HP coverage, system breaches, unrestricted release of tools / equipment j l Duties: Specific Responsibilities include: i i 1. Providing HP coverage for first feedwater j sparger replacement, performing invessel l Figure 2.1.3-11
3884029770-7" Pgg, 3 surveys, monitoring work'er doses, surveying tools and equipment
- 7..
Providing HP coverage for Torus Proper Modification, draining decon of Torus Proper, open sand-blasting of. Torus, welding new supports I 3. Performing non outage coverage of piping support modifications-in the Torus Room, Residual Heat Removal Rooms and Core Spray Rootas e i 4 l l Figure 2.1.3-12
.Pags'6-3884029770-H I J: 3/79-6/80 Peach Bottom Atomic Power Station Assistant s Technician - Duties: Routine surveys, in plant j training, provide'HP coverage-3 Specific responsibilities include: j 1. Providing coverage during the first feedwater heater (FWH) replacement in a commercial nuclear. j:. plant. Removed outer turbine shield walli cut FWH away from condensor, wrapped,;transfered FWH to controlled area, installation of new FWH
- I 1,
} e f t-4 f l 0 e 1 i i d 1 l l 1 l 1 Tigure 2.1.3-13 2
3884029770 NAME: Stanley F. Baker-EDUCATION AND TRAINING 1976 East Senior High School (West Chester,,Pa.) 3/79 - 11/83 Academic and "On the Job" training in Health Physics, Chemistry and BWR technology at the Assistant Technician, Technician "C", Technician "B", and~ Technician "A" levels in the following general subject areas: 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, 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 PECv/Dupont 11/85 CPR Instructor Qualification 6/86 Nuclear Professional Training PECo 6/86 Identifying Abbe: ant Behavior PECo 9/86 Kepner Tregoe Decision Analysis / Problem Solving-1/87 Bett Dosimetry / Shin Dose Assessment-Porter Consulting 7/87 Advanced Respiratory Protection Training-Paul Steinmeyer, t Figure 2.1.3-14
3884029770 WORK EXPERIENCE 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-Wa.ste Operations 3. Health Physics interface of I&C calibration j' and accountability of Health Physics instrumentation 4. Prepared training' courses and instructed ') technicians and nuclear workers of Health Physics procedures and work practices 5. i Attended plant Staff Operational Meetings j i 6. Established Surveillance Program and developed U-1/U-2 Isolation Program 7. Ordering of consumable supplies 8. Approved locations for temporary radioactive storage locations material 9. Performed duties of area co-ordinator for Limerick Generating Station's first refueling outage. 12/83 to Health Physics Technician "A" 12/84 Limerick Generating Station 1. 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. 5. Instructed technicians on radioactive material receipt, truck survey technique, radiation and contamination survey techniques and procedures. - Figure 2.1.3-15
L. .= =.a J: = 3884029770 l 6. Day-to-cty 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 OC inspections of R'd-a Waste and Radioactive Material shipments, j including solidified liquids, resins, filters, FW & R heaters and le"~~ motu 3. Wrote changes to various procedures. 4. Prepared,' issued, revised radiation work permits. 5. Performcd all' types of surveillanca 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). 9 7. Evaluated ALARA information for ALARA categorization. 8. Off-site emergency coordinator for '[ Emergency procedure exercises along with ?; various other roles in response to emergencies and drills. 9. Performed duties of Rover HP with interface with all job groups at PBAPS Units 2,3, and Rad-Waste and review of all work in plant and coordination of jobs.
- 10. Conducted on-site test of surface contamination sealants and paints,
- 11. Coverage of Hydro-lazing, f reon, actd lihd sandblasting decon efforts.
[i l ' Figure 2.1.3-16
.1 ~
- 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 l activities at major control points in the following areas:.drywell, fuel floor, torus proper, moist sep. j 2. Initial surveys.for MRFs and breach' j surveys. J 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 Htr. Breach of secondary containment, cut-up, and preparation for shipment. 7. Performed ultrasonic inspection of scram header on a routine basis. 3/79 - 6/80 Health Physics Assistant Tech. - PBAPS i 1. Assist at major control points. 2. Surveyed low level radwaste. 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 other-areas. PROFESSIONAL AFFILATIONS Appointec Limerick Generating Station Red Cross Blood Drive Chairman 10/86 , Figure 2.1.3-17
e I TECHNICAL SUPPORT PHYSICIST 'l 'NAME: Martha A. Christinziano EDUCATION AND TRAINING 1983 Rutger's University, New Brunswick, NJ MS Rad 4*** '9nce/ Health Physics 1981 Georgian C'_;c College, Lakewood, NJ 1 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 Saf ety 'iraining (3 d); by PECo 7/85 Nuclear Professional Training (NUPRO) (3 wks); by PECo 7/85 RMMS Troubleshooting & Data Base (2 d); by Spectrum M4S 6/85 RMMS Circuit Boards & Calibration (2 d); by Spectrum RMS ) 6/85 Fitness for Duty (1 d);' by PECo/NTS 6/85 RMMS Gen. Overview for MCR Operators (1/2 d); by Spectrum RMS H 4/85 RMMS Gen. Overview (2 d); by Spect.;um RMS 12/84 Radwaste Regulatory Awarener; (4 d); by Chem Nuclear 10/84 Medical and Legal Aspects of Radiation Induced Cancer; (3 d); by University of Pennsylvania and RMC/ canberra. 9/84 PEA Nuclear Subcommittee Meeting; (2 d); by PA Power Generation Committee. Figure 2.1.3-18 .;., n s.m..m, j,g,,g,,, y,73,;.,--,... q ,,.7 ,_,m. .. _., _.........,..,.,,,,,,,.,,,._.y.,,,_,,,,,,..
'l 3884029770 ~ \\ 10/83 Disposal of Low Level Radioactive Waste; (2 d); i by Penn State University. 9/83 BWR Recirculation Piping Seminar; (2 d);.by Power Cutting, Inc. 7-8/83 PECo/ LGS Engineer Orientation Program; (3 week). I 6/83 Germanium Detectors in' Nuclear Counting System; j (1 d); by Canberra /PSE & G Co. 6/83 HPS 1983 Summer School on Internal Dosimetry. (1 week) 4/83 NJ HPS. Current Trpics in Health Physics. (1 d) I l-2/83 Radwaste Managerent Workshop. (3 d) by ASME., .) 12/82 Brookhaven National Lab Environmental Monitoring Seminar (1 d) 11/82' EPRI Hydroget Water Chemistry Workshop. (2 d) -. WORK EXPERIENCE' 2/88 to Support Health Physicist, 'Present Limerick Generating Station jj i Supervise the Technical Support Health Physics ) Group which includes the Dosimetry, Respiratory Protection and Protective Clothing, Special Projects, Environmental Monitoring, and HP Instrumentation Programs. lj Responsibilities include: Establish objectives for program area managers consistent with excellence in plant operation. j Provide tecinnical direction and resources as 1' required to support program objectives.. Reveiw and approve technical reports and tes* results gnerated within program areas. Serve as Emergency Offsite Dose Assesmer.' Team Leader. Serve as Plant Operations Review Committee Alternate. I !i 10/84 to Effluent Monitoring Physicist-Philadelphia Electric 'l present Company, Limerick Generating Station, Tech Support Staff I l s ! Figure 2.1.3-19 lj)
Responsibilities: RMMS System Manager; EP Dose Assessment Team Leadcr; maintain integrity of RMMS Rad. Monitors, RMMS routine and emergency programs; and ODCM: generate all effluent / dose assessment reports per Tech. Specs. ~ Refuel 'loor 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 Company 10/84 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 National 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. 3 5/81 Physics (Seniors) & Chemistry (Juniors) 6/80 to Tutor / Counselor - Upward Bound Prograin 8/80 at Georgian Court College. High school math and science. Professional Affiliations 1. Delawarc 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 s ,m, f
3884029770 ~ NAME: Robert'K. Barclay EDUCATION AND TRAINING l l 1977 University of Pittsburgh B.S. in Biology 1979 Community College of Allegheny County. q A.S.'in Radiat' ion Therapy' Technology 1981-University of Pittsburgh Graduate School j of Public Health 1 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 l: Arbor, Jan-Feb. 1985-3 weeks 2. Canberra SU-519 Whole Body' Count Operations training,.Jan.- 1985 (Accuscan) Feb. 1987 (Fastscan) 1 week each 3. Compliance with new 10CFR20: Gaithersburg, MD 9/86 2' days l- \\ i 4. Delaware Valley Society for Radiation Safety-Sponsored i i Review for American Board of Health Physics Exam Course, Jan-June, 1986 (20 weeks - 4 hrs / week) i 5. American Board of Health Physics Certification, Comprehensive, 10/86 q WORK EXPERIENCE !l 7/84 to Philadelphia Electric Co. s Present Responsibilities: Dosimetry Program; including external and internal dosimetry (Eberline,. Panasonic, Landauer dosimeters and Canberra W. B. C. equipment), procedures, data review. l Nuclear Employee Data System (NEDS) site 'I contact. Supervision of contractor. dosimetry employees. Special Projects: Drywell .) penetration neutron monitoring with Landauer i dosimetry, Panasonic badge magazines, r irradiation jig, irradiator field mapping. 1. _1_ Figure 2.1.3-21 008980- "SECTION COPY" Q
~ 3884029770 ~ 8/82 to Union Carbids Corp. Nuclect 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, lou-level radioactive--. waste processing, federal and state licensing applications and renewals. 10/77 - 8/79 Allegheny General Hospital Responsibilities: Laboratory Technician with hospital blood team ) i 4 5 + Figure 2.1.3-22 r-g
NAME: John F. Scone 388402SF770 EDUCATION'AND TRAINING j 1972 State-University of New York at Albany - 2' week-s'eminar in X-ray' Spectrometry. 15,5 -Widener-University - B.S. in Business i ' Administration 1977 Delaware Technical and Community College -- basic course in Electricity. -1 1983 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 'i WORK EXPERIENCE 12/84-Health Physics Technical Assistant-Dosimetry Limerick Generacing Station l. Participate in-development / review of Dosimetry procedures l 2. Develop and implement' methods for maximizing efficiency and productivity inithe 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 5. Calibrate and requalification of Direct. Reading Dosimeters 6. Perform monthly Eberline Cycle and related a activities to ensure integrity of external i _y-Figure 2.1.3-23 Y q
388-029//0 l Dosimstry monitoring program (NUPERS), and to rGsolvs discrepancias vs estimntes l 7. Interface with PECo Services Division to correct deficiencies in Dosimetry computer programs l (NUPERS/NEDS); suggest improvements to these programs l l 8. Prepare monthly Dosimetry Management' Report i 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 in:egrety and confidentiality of Dosimetry Personnel files { l 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 Surveillance 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
3884629770 Implement Radiation Work Parmits, 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 Technician to A Technician while at Peach Bottom and worked five refuel outages as well as numerous miai-outages on both 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.:toring river for underwater preinspection,- Hot' Spot locations and removal prior to-pump down, pump down and initial entry.to Torus, i decontamination of Torus, monitoring structural i' 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. A. Core Spray Line Replacement Unit 2. B. RWCU Line Replacement Unit 2. C. Recirc Pump Seal Replacements. D. Vessel pump down for Core Spray nozzle replacement. E. Inboard and10utboard MSIV repairs and breaches. Subpile Room Sump pump down, clean out and repairs. G. Downcomer initial entries and decon. H. Clad overlap of both units of the Recirculation Headers and Risers and RHR Loops. I. Recirc Motor removal and Replacements including Decon & Transport between units. ) i sI . Figure 2.1.3-25 ~
3884029770 ~- J.
- CRD removal and. replacement (as well as j
repair) undervessel as well as Control Point ~ Leader. K.- LPRM Replacement under vessel. L. SRM Replacement under_ vessel ~. 4. Tip' Room . Initial entry into Room for Tip probe cable change and repair. Trip machine breach and Decons. 5. CRD Rebuild Area - Control point worker for CRD transpoiE 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 (1030 R/hr) on Unit 2. RWCU pump. breaches and repair with parts transport and Decon. 7. RHR Heat Exchanaers - 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 D> con. D. New fuel receipt-and inspections. l E. Spent fuel bundle disassembly by GE with pin puncture coverage. F. Initial entries to Vessel pre & Post Decon 1 inclusive of disassembly and assembly of Reactor Vessel Components. 9. Turbine Floors - Disassembly, Repair and modifications to HP & LP turbines, RFP Turbines, CIV's, Stop Valves and Control Valves. Sandblast 4 Figure 2.1.3-26 a ~
38F4.0L.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. 'ReducerssPower entriesJto water boxes for tube' leak plugging.
- 11..
Radwaste --HPL&'OC coverage for. receipt and shipments of. Radioactive: materials - sources, ~ condensate.and RWCU spent resins, LSA compactors-trash, contaminated tools-and parts. 12. Operations HP-Shift Coverage - 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 EP practices and 10CFR20 infractions. Report to responsible TA fqr the a area. 15. Special projects & Surveillance Test - As assiyhbd. 16. Control Rod Blad~ Stellite Roller Removal - CR3 decon and. prep for shipment, and shipment j coverage 9/78-3/79 Artesian Water Company, William'De., Corporate Property Account.- maintain and audit investment work order in progress accounts 1/77-9/78 Piquet Security Systems - Site Commander a Supervised 15 man. security force. + 1 2/73-12/76 Reynolds Metals Company - Cost Accountin'g Clerk - Responsible for maintenance and updating of.a standard. cost. production file per budget information, industrial engineering machineTrate information and approved manufacturing specification. Engineering Technician (R&D) tested electrical stability and integrity of high voltage transmission cables. Constructed MV test circuits utilizing test transformers,. - Figure 2.1.3-27 =,. -
3884029770 I 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. 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. h l
- l l
i i ' Figure 2.1.3-28 r -x ~ ,.n,.
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 I 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 l physics, radiation ~ biology, radiation l 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 nealth 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 3/85 Radon Survey Techniques - 4 hours 9/86 Problem Solving and Decision Making (Kepner Tregoe) - 24 hours Figure 2.1.3-29
3884029770 1/87_ Beta Dosimatry 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 i portable ventilation devices. Develop and supervise the program controlling use and accountability of temporary shielding, pcoviding calculations and other shielding i technical support when needed. Act as Health Physics shift supervisor (Sr. Technician) for j 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 walkdow' i; catalyzed job onset and minimized job delays due to poor communication and misunderstandings. 1 l 1 l ,- Figure 2.1.3-30
^ 3884029770 Woax exprartnCr 12/83-6/84 Health Physics Technician "A"-Limerick Generating Station { l Duties: Filled job of Technical Assistant. Worked towards set-up of training program. Wrote and reviewed procedures. Approved various procedures as a PORC member. Worked toward acquisition of contracts for personnel, l services, and equipment. Approved purchases of equipment and supplies as needed to set up the naulth physics program. Helped set up Emergency Preparedness Plan and served as the l' tvacuee Control-and Vehicle Decontamination L Group Leader during emergency exercises. ll 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, RER rooms, Moist Separators Area, etc. < Figure 2.1.3-31 i
<3884029770 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 - 6/80 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" 12/84 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 l-e
3884029770 t 4/84 - 11/87 Philadelphia Electric Company I ALARA Physicist Responsibilities: developing the ALARA program, procedures and guidelines; developing-tachniques to evaluate the effectiveness of~the ALARA program; reviewing engineering and design changes to ensure inclusioti of appropriate-ALARA concerns; implementing a '- p.cary shielding control progran., int facing with. work groups to, ensure that ALAL1 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. i i 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 dcring emergency exercises, maintenance of emergency plan and procedures. 10/81 - 6/82 Georgia Power Company I Health Physicist Responsibilities: assisting. in the developmer.t 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 -l ,1._..._,-.,
3884029770 Joseoh W. Moon / j EDUCATION 1970 Graduated Bordentown Military Istitute, Bordentown, N. J. t .1975-Graduated Ursinus College, Collegeville, Pa. B. S. Degree in Biological Science 1977 Brookhaven Nation:1 Laboratory, Upton,.Long Island, N. Y. Health Physics Fellowship. (E.R.D.A.) j ? ! 1980 Graduated Rutgers University, New Brunswick,'N. J. j M. S. Degree in Radiation Science i l WORK EXPERIENCE 1986 to Philadelphia Electric Company i Present Special Projects Physicist. Developed Field Isotopic Analysis system for E-Plan using intrinsic Germanium Detector and Multichannel and Analyz'er. Developed Operation Procedures,ful incorporated system into E-Plan. Succcss 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 j Engineering Controls for Drywell while Purge System inoperable. Layout of Outage Exposure Control ) Points. Implemented Station Radiological Deficiency Tracking Program. 4 j h Figure 2.1.3-34
38840297/0 1984-1986 Radiological Engin:ering Consultant at Palo Verdo Nuclear G3nerating Station 1982-1986 Corporate Health Physicist at Numanco inc., Rhode 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 Radiolegical Engineer during start-up operations at Grand Gulf. Nuclear Power Plant Sr. Realth 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 St& tion ALARA Coordinator at Millstone Point Unit 1 Decontamination Foreman at Surry Station, Steam Generator Replacement Project 1978 Sr. Health Physics Technician at Zion Generating Station 1977 Health Physicist at Millstone Point 2rofessional Affiliations: Health Physics Society; American Nuclear Society Figure 2,1.3-35
s. .Z... ' SPECIFIC BUNDLES IN LIMERICK. U N 1 - T. 2 'm_, INITIAL CORE NOMINAL U-235 WT. PER BUM)LE BUM)LE TYPE AVG w/o 235 BUNDLES KG 1 GE7-P8CIO71 0.71 c 92 1.30 GE78-P8CIB094 0.94 132 1.72 GE78-P8CIB163 1.63 160 2.98 GE78-P8CIB278 2.78 72 5.08 i GE78-P8CIB248 2.48 308 4.52 764 Total U Weight 139,543.31 Kg Total.U235 Weight 2,581.82 Kg i Average Enrichment - 1~.85 w/o U-235 .y i: 4 I. W 4 i l 1; Tcble 1.1.3 4 ~ ~ _. _ _.... _ _ ---r --a
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ik ,y l" Philadelphia' Electric Company Cfficers 'd. F. Paquette, Jr.,-President Chairnen of the Board and Chief Executive Officer J. L. Everett,,III-Chairman of the Executive Conmittee Corbin A. McNeil, Jr. Executive Vice President-Nuclear i R. G. Gilnore J. S. Kemper, Senior Vice President - Finance Senior Vice President & Chief Financial. Officer E..G. Bauer, Jr. R. F. Holnen Senior Vice President Senter Vice President & General Counsel - Operations A. L.. Parry, Jr. A. G. Mikalauskas Vice President Vice President C. L. Fritz C. Brenner Vice President Vice President M. W. Rlanernen J. W. Gallagher Vice President Vice President R. C. Wi l l i ams S. J. Kowalski Vice President Vice President P. G. Mulligan A. J. Weigand. Vice President Vice President G. M. Leitch K. G. Lawrence Vice President .Vice President D. M. Smith D. P. Scott Vice President Treasurer i L. S. Binder Secreta ry j i FMS/vvg/02048802 3 Exhibit 1.0 d /}}