ML20150E690
| ML20150E690 | |
| Person / Time | |
|---|---|
| Site: | 07003054 |
| Issue date: | 10/26/1987 |
| From: | Kowalski S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20150E656 | List: |
| References | |
| 107994, NUDOCS 8807150251 | |
| Download: ML20150E690 (162) | |
Text
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COktilSSION In the Matter of PHILADELPHIA ELECTRIC COMP #4Y APPLICATION FOR SPECIAL NUCLEAR MATERIAL LICENSE FOR LIMERICK GENERATING STATICN UNIT NO. 2 i
1 E$vard G. Bauer, Jr.
Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania Attorneys for Philadelphia Electric Conpany N
8807150251 871217 i
REG 1 LIC70 SNM-1977 PN "OfflCIAL RECORD COM"M.
29 00T 1987 1U7884 i
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1.0 General Information Phl1adelphia Electric Ccrrpany (Applicant) is a corporation organized mder the laws of the Conmorwealth.of Pennsylvania with Its principal place of business at 2301 Market Street, Philadelphia, Pennsylvania 19101.
Philadelphia Electric Conpany is not owned, controlled, or dcrninated by an allen, foreign corporation, or a foreign goverrvnent. A list of Applicant's officers, all of whom are citizens of the United States, is marked ExhlSit 1, attached hereto, and Incorporated herein.
Appilcation is hereby made pursuant to Section 70.22 of the Ccrrmission's Regulations for a license authorizing Appilcant to receive, possess, store, use, and deliver to a carrier for shipment certain special nuclear material (SPN) conta!ned in Instrunentation at the Appilcant's Limerick Generating Station (LGS) Unit 2.
The period of time for which the Ilcense is requested Is from the anticipated arrival of the Instrunentation at the Limerick Generating Station site in Decenter 1987 until issuance of an operating Ilcense for LGS Unit 2.
The fuel assenbiles for the Initial core of LGS Unit 2 are not scheduled to arrive on site until late 1988.
Therefore, NRC authorization fee receipt of the fuel assenblies will be requested at a later date.
In support of its Appilcation, Applicant provides the following infonmtion:
2.0 Location of Use Limerick Generating Station Unit 2 is presently under construction on a site located in Limerick Township, Montgerrery County, Pennsylvania approximately 25 miles west of Philadelphia, Pennsylvania. Applicant currently operates Limerick Unit 1 on this site pursuant to NRC Operating License NPF-39. Construction of LIrrerick Generating Station Unit 2 was authorized by the Atcmic Energy Conmission In Construction Permit No. CPPR-107 1ssued on June 19, 1974 (Docket No. 50-353).
3.0 Description of Special pax:: lear Material An NRC License is being sought to authorize the receipt, possession, use, storage, and dellvery to a carrier for transport of the following Instrtsmntation containing special nuclear material in amounts spectfled:
a.
Source Range Monitors (SRM):
4 detectors at 2.72 mg U-235 each (10.88 mg total) and 0.19 mg U-238 each (1.52 mg total).
b.
Intermediate Range Monitors (IRM):
8 detectors at 0.75 mg U-235 each (6.0 mg total) and 0.053 mg U-238 each (0.424 mg total).
c.
Local Pcwer Range Monitors (LPRM):
172 detectors at 0.88 mg U-235 each (451.36 mg total), 3.3 mg U-234 each (567.6 ny total), and 0.08 mg U-238 (13.76 mg total) 107994 with a welght percent ccrrgnsitlen of 20.7% U-235, 77.5%
U-234,'and 1.8% U-2'l8.
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d.
Traversing-In-Core Probe (TIP):
5 detectors at 0.75 mg U-235 each (3.75 mg total) and 0.053 mg U-238 each (0.424 mg total).
Authorizatlon is also requested to receive, possess, use, store, and delivery to a carrier for transport special nuclear material in spare detectors and replacement as may be needed. The total quantity of SPN in all such Instninentation wl116e less than 10Kg of SPN of low strategic significance, l
4.0 Storage and Handling Conditions After receipt the SRMs, IRMs, LPRMs, and TIPS will be stored in the Stores Warehouse on the Limerick Generating Station site. Access to this area will be controlled as described in the Physical Security Plan for Unit I which has been previously approved by the NRC.
Prior to placement in the reactor, the detectors will be moved to terrporary storage area (s) to be designated. The area (s) will be enclosed by barriers substantial enough to deter entry by unauthorized personnel.
The final locatlon of SRMs, IRMs, and LPRMs will be in the reactor vessel. The final storage location of the TIP detectors will be within the TIP rMchines and associats d
- tubing, Spares and defective equlgment (if any) w!11 be stored in the Stores Warehouse as described above until j
dellvered to a carrier for shipment or untl1 placed in use.
The procedure for the Installation of the special nuclear material is the General Electric Nuclear Energy Division (GE NED) procedure nurber 22A4211, "Nuclear Instrurentation
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Installation Instructions".
This procedure was used for the instal. stlon of the neutron Instrurentation at Llrmrick Unit 1 and is attached as Exhibit 4 The GE NED procedure is the parent docurent vhich the Installer, General Electric Apparatus and Engineering Services Operations (GE AES0), uses to create their Inprocess "traveler". The "traveler" Includes the Instructions to be t
followed (including handling instructions) and the record f
sheets to be ccrri;1eted for the work.
5.0 Radiation Control A.
Procedures and Equiprmnt for Checking Contamination The Health Phys!cs personnel will be notified when a shlprrent of new fusi or Instrunentation containing Special fbclear Material arrives on site. Health Physics personnel shall perform ccrrolete radiation and contamination surveys of the i
outside of the transport vehicle to ensure that the radiatton levels are within acceptable limitt if all survey data is t
within Ilmits, the vehicle wit' or ::eed with u11oading.
If survey data is above estab11shed limits, appropriate actions, -
L as defined in Plant Operations Review Ccmnittee (PORC)
I approved written station procedures, will be followed.
The l
small quantitles of radioactive westo generated in the surveying of StN Items for contamination will be handled in
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accordance with applicable reout rements of Appendix A to Operating License NPF-39, specifically Section 3/4 11.3
)
- thereto, i
B.
Calibraticn and Testing of Instrtanentation All Instrurnents shall be tested and calibrated routinely In accordance with approved station procedures.
Survey Instrtrnents will be calibrated on an annual basis.
Instrtsnent callbration will be performed by quallfled station personnel or through a vendor.
Each Inst rtrnent will bear a i
sticker Indicating the date when recalibration is due.
C.
StN Control and Accounting Practices SFN control 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 i
Accounting" end "ST3-97-350-0 Annual StN Inventory". A-44 is attached as Exhibit 2.
ST3-97-350-0 is attached as Exhibit 3.
D.
Minimtsn Qualifications for Positions having Radiation Safety Respore,ibil ltles
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The mininun cualifications for the Senior Health Physicist (Radiation Safety Officer) are those outilned in Section t
4.4.4 of ANSI /445-3.1-1978, "knerican National Standard for Selection and Training of Nuclear Pcwer Plant Personnel".
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The applied Health Physicist and Support Health Physicist (assist RS0s) have as a minfrntrn a four-year degree in Health Physics or a related fleid and at least 24 months applied j
Health Physics experience. The experience of the Health I
Physicist is presented in Figures 2.1.3 2.1.3-47.
The training necessary for Health Physicists is outilned in i
l Section 12.5.3.5 of the Llrrerick FSAR.
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Responsibilities for Radiation Safety Personnel The responsibilltles for the key radiation safety personnel I
are described by the following "Radiation Safety PrograrrP description.
I The radiation safety progrern is directed by the Senior Health i
Physicist. Assisting the Senior Health Physicist are the Support Health Physicist and the App 11ed Health Physicist.
j Both of these positions have the authority to act for the Senior Health Physicist in his absence.
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I The objectives of health physics operations are to:
- a.
detect, Identify, and define radiation hazards, b,
provide protection for personnel agaInst radiation hazards.
c.
control plant-related radiation exposures (occupational and general pubilc) to levels as low as reasonably achievable (ALARA).
d.
conduct plant activlties in confonnance with 1
authorized procedures and applicable regulations.
l These objectives are acconplished or enhanced by the j
various training prograns, by the use of prepared Health i
Physics operating procedures, by periodic review and i
revision of procedures, by evaluation of activities for ALARA purposes, and by the control of plant operations 1
to minimize occupational exposures and releases to the envi ronnent.
Health Physics operations include the posting, notification, and reporting provisions of 10CFR Part 19 I
and General Dnployee Training, or in sone cases task-specific Instruction, provides the requisite Instruction to verkers.
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Health Physics operations conform with the guidelines of Regulatory Guide 8.2 (Rev. 9) and of ANSI N13.2-1969, t
i Guide for Administrative 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 l
periodicity.
In addition to this section, Sections 12.1, 13.1, 13.2, 13.5, and of the Lireelck 1
FSAR describe the management conmitnent, organization, responsibilities, authority, training, procedures, and
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review techniques which Implenent Regulatory Guide 8.8 l
(Rev. 3), Regulatory Guide 8.10, and Regulatory guide j
1.8 (Rev. 1-R).
As described in Section 12.1 of the
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FSAR, a formal ALARA review program which is consistent with the guidelines given in Regulatory Guide 8.8 was l
4 Implemented during the design and construction phase.
j The quallfication requirements for the Senior Health l
Physicist are described in Section 13.1.3 of the FSAR.
Chapter 17 of the FSAR and the LGS Technical Specifications address implementation of other appilcable regulatory guides.
The portion of the Health Physics program related to special nuclear enterlat s is outilned as follows:
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RADI ATIOfJ PROTECTION PERSONNEL 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 frcm the Offsite Director - Radiation Protection Section.
The Senior Health Physicist corresponds to the Radiation Protection Manager as described in Regulatory Guide 8.8-1977 (Revision 3) and 8.10-1977. His dutles/ responsibilities in this capacity include:
a.
developing and Irmlementing an effective radiation exposure control and measurement program in consonance with the PECo ALARA policy.
b.
ensuring that exposure measurement and control programs are periodically reviewed and that appropriate revisions and corrective actions are taken when the results of these programs indicate that such actions are needed to conform to the PECo ALARA policy.
c.
preparing and reviewing procedures for Irrolanenting the ALARA policy.
d.
ensuring that the resources needed to irmlement the ALARA policy are available and used.
e.
participating in reviews including design and procedure reviews at the Piant Operations Review Ccmnittee level, of facilities, activities, and equipment that can affect potential radiation exposures.
f.
supervising radiation, surface contemination, 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 program to ensure that personnel are aware of PECo management's ccmnitment to ALARA and are Instructed In ways of reducing exposures that
are related to work in radiation areas or that involve radioactive materials.
h.
supervising the radiation surveillance programs ar'd the collection, analysis, and evaluation of data from radiological surveys and from personnel exposures and doses 1
including the sue of the radiation work pennit data.
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supervising and training of the health physics 1
staff.
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providing appropriate data and Infornetton related to the ALARA program and results to the Plant Manager and to the Director, i
Radiation Protection Section, to keep conpany management Informed about the program.
k.
acting Radiation Protection Manager.
In his absence a person tenporarily filling this 4
position will have a BS degree in engineering or science with two years experience in radiation protection, one year of which shall be nuclear power plant experience, six nonths of which will be onsite.
Health Physicist (Assistant Radiation Safety Officers) 1 The support Health Physicist and the Apolled Health 4
i Physicist report to the Senior Health Physicist and 4
Inplecent the PECo ALARA program and perforTn I
functions as assigned by the Senior Health Physicist.
Specifically the Health Physicists are I
responsible for:
a.
perfornance of radiation, surface i
contanination, and airborne activity surveys and collecticn, analysis, and maintenance of associated data.
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b.
control and implementation of personnel dos! metry requironents and the collection, analysis, and maintenance of associated data.
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c.
classification and operation of barricades, l
J control points, and access conditions.
d.
perfornence and/or supervision of I
decontamination of areas, eaulonent, and l
personnel.
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e.
surveillance of laundry operations and radioactive material transfers.
f.
maintenance and performance of equlgrnent within his review.
I g.
respiratory protective equipment and protective clothing and equlgrnent program l
operations.
h.
bloassay and Internal dose determinations.
4 monitor effluent releases to ensure cartpliance l
wlth Technical SpectfIcatlon.
4 Correspondence with respect to this Application should be addressed to:
3 Edward G. Bauer, Jr., Esq.
Eugene J. Bradley, Esq.
2301 Market Street Philadelphia, PA 19101 Respectfully submitted, PHILADELPHIA ELECTRIC COM)#W t
By:
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/ V'pjef President I
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l COMMONWEALTH OF PENNSYLVANIA ss 1
COUNTY OF PHILADELPHIA f
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S. J. Kowalski, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company, l
the Applicant herein; that he has reviewed the foregoing 2
Application for Special Nuclear Material License for Limerick Generating Station Unit No. 2 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and l
belief.
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I Subscribed and sworn to i
before this M" day of October, 1987 l
4 N<.b.o 1f n tl 5 1
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Notary Public sc- - ~.~ %.,
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Philadelphla Electric Company Officers J. L. Everett, III Chairwan of the Board and Chief Executive Officer R. F. Gilkeson Chairman of the Executive ConTnittee J. H. Austin, Jr.
President and Chief Operating Officer R. G. Gilmore J. S. Kempe r Senior Vice President Senior Vice President E. G. Bauer, Jr.
A. G. Mikalauskas Vice President & General Counsel Vice President A. L. Parry, Jr.
C. Brenner Vice President Vice President C. L. Fritz J. W. Gallagher Vice President Vice President M. W. Rlmenrren S. J. Kowalski Vice President Vice President R. C. Wi l l i ans A. J. Weigand Vice President Vice President P. G. Mu111gan K. G. Lawrence Vice President Vice President R. F. Holman Vice President L. S. Binder D. P. Scott Secretary Treasurer i
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l Rd.5/cmv/06268705 EXHIBIT 1
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l > 3 /e a /rf 3853077270 Page 1 of 14 A-44, Fev. 3 Effective Date KWE:4gs i & 2fM f PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION Q
3 14 - T T A-44 PROCEDURE FOR SPECIAL NUCLEAR MATERIAL ACCOUNTING 1.0 PURPOSE This procedure describes the administrative controls, responsibilitien, methods and documentation required for proper accounting of special nuclear ma hrial (SNM).
It is imperative that the plant staff have a complete record of SNM locations.
This information is required by the Philadelphia Electric Company, the code of Federal Regulations and the vendors of SNM.
Philadelphia Electric Company requires the location and quantities of SNM to aid in core performance optimization, scheduling of refueling outages and the purchase or reprocessing of SNM.
10 CFR, Part 70.51 states that the licensee sha'11 keep records of the receipt, inventory, disposal, acquisition and q'.
transfer of all SNM.
10 CFR, Parts 70.53 and 70.54 require the submittal of Material Status Reports and Nuclear Material Transfer Reports, respectively (Ref. 1).
Fuel and SNM venders require reports concerning their product.
The contents of these reports are outlined in the warranty contract and are usually required as part of the warranty contract.
2.0 RESPONSIBILITIES 2.1 The Purchasing Division of the Purchasing and Genera'l Services Department shall be responsible.to 2.1.1 Aid the Reactor Engineer in packaging and shipping arrangements for ine utgoing SNM and other incore compoae j f 2.2 The Nuclear Engineering Section of t 1
y.g Research Department shall be responsible to.
2.2.1 Provide administrative guidance of 2.2.2 Provide technical advice at yoyimreaterial shipments and receipts.
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EXHIBIT 2
l A-44, Rav. 3 Page 2 of 14 hWdirgs
{U 2.2.3 Aid the Reactor Engineer in maintenance of inventories, stcra.ge, internal transfers, measurements, records, reports and procedure changes conctrning SNM.
2.3 The Suparintendent - Nuclear Generation Division, shall be responsible to:
l 2.3.1 Manage SNM for Philadelphia Electric Company.
2.4 The Fuel Management Section of the Electric Production Department snall be responsible to:
2.4.1 Aid the Reactor Engineer in administration, accounting, shipping and receiving, inventory maintenance, storage, internal transrers, measurements, records, reports and procedure L
char.ges of SNM.
2.4.2 Complete and distribute Nuclear Material Transaction Reports - DOE /NRC Form-741.
2.4.3 Complete and submit Material Balance Reports -
DOE /NRC Form-742 and Physical *'ventory Listing DOE /NRC Form - 742C.
2.5 The Station Superintendent or his designated respresentative shall be responsible to:
2.5.1 Provide station management of SNM.
2.5.2 Receive SNM.
2.5.3 Review and approve SNM. accounting procedures.
2.5.4 Acknowledge the outgoing shipment of SNM.
2. 6-The Technical Engineer shall be responsible tot 2.6.1 Supervise the administration of SNM.
2.6.2 Supervise the maintenance of records necessary to determine depletion of SNM.
2.6.3 Supervise the preparation of reports concerning changes, additions or deletions to SNM or SNM related components.
2.7 The Reactor Engineer shall be responsible tot 2.7.1 Control the on s,ite administration of SNM.
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l A-44, Rev. 3 Page 3 of 14
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d 2.7.2 Develop implementation procedures to receive, handle, store, account and ship SNM.
2.7.3 Maintain and submit the reports, records and logs necessary to ensure accountability of all on site SNM.
2.7.4 Coordinato site personnel activities such as receiving, shipping, storage, internal transfer and acco,unting of SNM.
2.7.5 Provide direction for the receipt, unloading, loading and shipment o: SNM.
l 2.7.6 Ensure that station accountability records, reports and logs concerning SNM are appropriately maintained.
2.8 The Health Physics Supervision shall be responsible to
- 2.8.1 Provide Health Physics direction of the receipt, f
loading and shipment of SNM.
2.8.2 Ensure that the appropriate Health Physics documents concernius the SNM are appropriately l f,';',.
maintained.-
w 2.9 The Operations Shift Superintendent shall be responsible tot i
2.9.1 Ensttre that personnr4 responsible for core alteratiuns ste Seniet Reactor Operators who have io other concurrent responsibilities during this activity.
2.10.The Fuel Handling director shall be responsible toe 2.10.1 Direct, from the refueling' platform, fuel movement and any core alteration.
2.11 Administration Engineer shall be responsible tot 2.11.1 Develop and implement station procedures to ensure that all SNM is properly guarded and patrolled.
3.0 PREAEQUISITES None I
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l A-44, Rov. 3 Page 4 of 14 Kh*Hargs i
Ih 4.0 DEFINITIONS 4.1 5pecial Nuclear Material (SNM) is plutonium, uranium 233, uranium enriched in the isotopes 233 or 235, or any material artificially enriched in the preceeding, but does not include source material.
SNM includes i
Source Range Monitors (SRMs), Intermediate Range Monitors (IRMs), Traversing Incore Probes (TIPS), Local Power Range Monitors (LPRMs) and fuel (10CFR 70.4).
4.2 Material Balance Areas (MBAs) are specific areas on site where SNP s stored or processed.
Inventories of a
each MBA as wel. rs records and logs of all additions l
and removals arr maintained by the Reactor Engineer (10CFR 70.51).
The following locations are defined as MBAs for fuel:
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New Fuel Storage 1
2.
Temporary Storage
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Unit 1 T'ael Floor 4.
Unit 2 Fuel Floor i
5.
Unit 1 Reactor 6.
Unit 2 Reactor i
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Unit 1 Fuel Pool I] cq 8.
Unit 2 Fuel Pool 6-j' The following locations are defined as MBAs for SRMs, IRMs, LPRMs, TIPS and other SNM:
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Temporary Storage i
2.
Unit 1 Fuel Floor l
3.
Unit 2 Fuel Floor, 4.
Unit 1 Reactor i
1 5.
Unit 2 Reactor i
6.
Unit 1 Fuel Pool i
7.
Unit 2 Fuel Pool 8.
Irradiated Storage.*
4.3 Fuel Handling director - During an outage with the reactor' head removed and irradiated fuel in the vessel tae Fuel Handling director shall be a SRO licensed J
individual.
During an outage with the reactor head not removed or during a non-outage period the Fuel Handling 1
i director shall be a cogni. tant individual designated by the Station Superintendent.
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5.0 PROCEDURE l
5.1 RECEIPT OF SRM
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. 5.1.1 SNM shall be received at the station by the
.9tation Superintendent or his designated i
representative.
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5.1.2 Shipping records accompanying the SNM shall be delivered to the Storeroom for disposition (Except for fuel).
A copy of the shipping records containing item serial numbers for all SNM (except for fuel) will be transmitted by the store keeper or OC Receipt. Inspection, to the Reactor Engineer.
A copy of the fuel shipping records containing item serial numbers will be i
transmitted by the Reactor Engineer to the Fuel Management Section of the Electric Production Department.
5.1.3 Health Physics personnel shall measure external j
radiation levels of the shipment and examine the l
shipment for surface contamination.
l 5.1.4 The shipping containers shall be checked for signs of damage and any damage found shall be dispositioned as per FH-101. In the event of major container damage, the SNM manufacturer must be notified and remedial actions implemented.
The Reactor Engineer will file a report concerning the steps taken after the discovery of major container damage.
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5.1.5 For fuel shipments, the serial number of the two
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seals on the wooden shipping box and the three seals on the metal container shall be verified to be as, listed on the shipping records containing the container serial numbers.
5.1.6 The fuel shipment shall be unloaded and moved according to approved Fuel Handling Procedures.
5.1.7 Fuel shipping containers Shall be inspected for content according to the snipping records containing item serial numbers at.the earliest i
practicable time af ter m.ovement to the Fuel-Floor.
SRM, IRM, LPRM and~TIP shippirg containers shall be inspected for content according to the shipping records :ontaining item serial numbers when the item is receipt i
l inspected.
5.1.8 Discrepancies in SNM quantities discovered during the inspection shall be reported to.the Reactor Engineer, Station Superintendent and the Fuel Management Section of the Electric Production Department.
The Reactor Engineer shall contact the shipper to resolve the discrepancy.
Any unresolved discrepancies shall h.
be reported immediately by telephone to the Nuclear Regulatory Commission (NRC) in accordance vith
- 0 CFR Part-70.52 (Ref.1).
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5.1.9 A-44-la Fuel Receipt / Tracking Data Sheet and A-44-lb Temporary Fuel Storage Data Sheet, if required, shall be initiated upon the receipt of fuel.
A-44-6 Non Fuel Receipt and Storage Data l
Sheet shall be initiated upon the receipt of any l
cther SNM by the Reactor Engineering Group or l
any cognizant technical staff member.
l A-44-lb TO BE INITIATED ONLY IF NEW FUEL STORAGE AREA IS NOT TO BE USED.
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5.2 SHIPMENT OF SNM 5.2.1 The preparation of SNM shipments is the responsibility of the Station Superintendent.
j 5.2.2 Packaging and shipment arrangements for SNM are supervised by the Reactor Engineer with guidance from the HP Group, the Fuel Management Secticn I
of the Electric Production Department, the Nuclear Engineering Section of the Engineering and Research Department and the Purchasing Division of the Purchasing and General Services Department.
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5.2.3 Changes to the site SNM inventory are recorded at the departure of each shipment by the Reactor Engineer or his designated respresentative.
I 5.2.4 Shipping records for each shipment of SNM are l
kept on file in the station files. Ceples of the fuel shipping records containing item serial numbers are forwarded by the Reactor Engineer to the Fuel Management Section of the Electric Production Department and, if required, to the Nuclear Engineering Sec. tion of the Engineering and Research Department.
5.2.5 _ The completion and distribution of DDE/NRC-741' is the responsibility of the Fuel Managemer.t Section of the Electric Production Department.
5.2.6 Shipping discrepancies between Philadelphia Electric Company and the receiver of SNM are to be resolved promptly.
Unaccountable
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discrepancies are reported immediately by i
telephone to the NRC in accordance with 10 CFR 70.52 (Ref.1) by the Reactor Engineering Group or any cognizant technical staff member.
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A-44, Rev. 3 Page 7 of 14 KWH:rgs f
5.2.7 Shipping discrepancies are reported to the Fuel Management Section of the Electric Production Department due.to the possible impact on DOE /NRC - 741 by the Reactor Engineering Group or any cognizant technical staff member.
5.2.8 Shipment of irradiated fuel shall comply with 10 CFR 20, 10 CFR 70, 10 CFR 71, and applicable Department of Transportation regulations.
5.3 STORAGE OF SNM 5.3.1 SNM shall be stored only in the MBAs specified in Step 4.2.
5.3.2 FNM shall not be stored in the new fuel vault.
5.3.3 Fuel stored in the New Fuel Storage Area shall be documented on Form A-44-la.
5.3.4 Fuel stored in a temporary storage area shall be documented on Forms A-44-la and A-44-lb.
5.3.5 Storage of non-fuel SNM in temporary storage MBA shall be documented on Form A-44-6 and A-44-9 7,
(as required).
5.4 INTERNAL TRANSFER DOCUMENTATION UPDATE FOR SNM 5.4.1 Fuel transferred between storage MBAs or between a storage MBA at.d a fuel floor or between a fuel floor and a fuel pool shall be documented on Form A-44-la and, if required, on Form A-44-lb.
5.4.2 Fuel transfer between MBAs requires updating the following fuel accounting.cocumentst.
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A-44-2, Fu.1 Inventory Summary Sheet 2.
A-44-3, Fuel inventory Log-fuel pool (fuel pool only) 3.
A-44-4, Fuel Inventory Log - Core (core only) 4.
Storage Location Tag Board (fuel pool and reactor only) 5.
A-44-5, Fuel Location History Sheet (fuel Pool and reactor only) 5.4.3 Transfer of fission chambers between MBAs shall be authorized by A-44-8, Fission Chamber Transfer Authorization Sheet (FCTAS).
Movement of fission chambers may occur only after the Reactor Engineer or his designated representative has signed A-44-8. (Exception:
See Step 5.4.4.)
l A-44, Rev. 3 Page 8 of 14 KWH.rgs
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5.4.4 Replacement of LPRM's is an exception to Step 5.4.3.
LPRM replacement is a core alteration and requires a Core Component Transfer Authorization Sheet (CCTAS).
5.4.5 Fission chambers transferred beeseen MBAs using either a FCTAS or CCTAS require updating the following fission chamber accounting documents:
1.
A-44-7, Fission Chamber Inventory Summary Sheet 2.
A-44-9,, Fission Chamber Location History Slieet 5.5 TRANSFER OF FUEL IN THE FUEL POOL 5.5.1 Movement of fuel from the fuel floor to the fuel pool is recorded on A-44-la and as required by the applicable FH Procedure.
ALL FUEL MOVEMENTS FOLLOWING PLACEMENT IN THL FUEL PREP MACHINE MUST BE ACCOMPLISHED BY USING THE REFUELING PLATFORM FUEL GRAPPLE.
5.5.2 Movement of fuel within the fuel pool is authorized by a CCTAS.
(l 5.5.3 Manipulation of fuel within the fuel pool should be accomplished in accordance with S97.0.H (General Handling of Core Component and Irradiated Items in the Fuel Pool / Cask Pool).
5.5.4 Within three mor.ths of a fuel handling cperation in the fuel pool, the applicable fuel accounting records shall be assembled and the following logs and records updated:
1.
A-44-3 the Fuel Inventory Log - Fuel Pool shall be updated.using the C.CTAS and the Fuel. Pool Tag Board.
2.
A-44-5 Individual Fuel Location History Sheets shall be updated using the CCTAS.
5.6 TRANSFER OF FUEL DURING REFUELING 5.6.1 Movement of fuel into or out of the reactor is authorized with a CCTAS.
6Ch (as i
e
l A-44, R9v. 3 Page 9 of 14 KWH:rgs
(..\\
.i v 5.6.2 Transfer of fuel into or out of or within the reaqtor should be accomplished in accordance with S97.0.C (Transfer of Fuel from the Fuel Pool to the Reactor), S97,0.D (Transfer of Fuel from the Reactor to the Fuel Pool) and S97.0.E (Transfer of Fuel Within the Reactor).
ALL FUEL MOVEMENTS SEALL BE ACCOMPLISHED BY PORC APPROVED PROCEDURES.
5.6.3 Visual confirmation of fuel assembly serial numbers in the reactor shall be done following refueling operations.
5.6.4 Within three months of a refueling outage the applicable fuel accountirg records shall be s
assembled and the following logs and records updated:
1.
A-44-3, A-44-4 the Fuel Inventory Logs for the Fuel Pool and Core are updated using the CCTAS and the Storage Location Tag Boards.
2.
A-44-5 the Fuel Location History Sheets are updated using the CCTAS.
5' 5.7 SNM INVENTORY 5.7.1 The plant process computer provides reactor thermal power and fuel burnup information that the Technical Engineer should forward to the Fuel Management Section of the Electric Production Department.
5.7.2 The Fuel Management Section of the Electric Production Department shall calculate the isotopic quantities of fuel present on site.
5.7.3 The Reactor Engineer shall conduct an inventory of all on site SNM annually or'when a descrepancy in any of the MBAs is discovered.
The SNM in the reactor is exempt from the inventory when the reactor head is in place and verification of reactor inventory has been performed.
Outstanding discrepancies shall be brought to the attention of the PORC for review.
Unaccountable discrepancies in SNM inventory shall be reported immediately by telephone to the NRC in accordance with 10 CFR 70.52 1
(Ref. 1).
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-.-... -.>...- - -.. ~.-. - - -.. ~:....-- -
l A-44, Rev. 3 Page 10 of 14 KWH:rgs (P
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5.7.4 The Reactor Engineer should forward the results of inventories to the Fuel Management Section of the Electric Production Department.
5.7.5 The Fuel Nanagement Section of the Electric Production Department shall prepare NRC/ DOE-742 for transmittal.
5.8 CHANGES TO SNM AND SNM ACCOUNTING 5.8.1 If SNM other than fuel, SRMs, IRMs, LPRMs or TIPS is to be used, the Reactor Engineer shall develop SNM accounting controls for the new SNM similar to those already in use.
1.
If the new SNM is to be used temporarily, the Reactor Engineer shall determine if existing procedures are sufficient to provide adequate accounting.
l 2.
A permanent change to SNM may require I
ahanges to this procedure.
The Reactor Engineer shall determine the accounting L
needs of the new SNM.
I
{0h 3.
New accounting procedures and changer to this procedure shall be performed in accordance with LGS Procedure A-1 (Reference 7.2).
5.9 SNM ACCOUNTING DOCUMENTS 5.9.1 A-44-la, Fuel Receipt / Tracking Data Sheet (Form M-21974) - This sheet indicates the location of fuel from receipt on site to storage in the Fuel Pool after the receipt inspection.
When fuel is stored in Temporcrv Storage rather than the New I
. Fuel Storage' Area, A-44-lb must also be used and l
l I
the "lb" cclumn on A-44-la checked.
As a i
minimum this sheet shall contain arriv31 date and time, Container Serial Numbers cont 41ning seal numbers, Fuel Assembly Serial Number, transfer dates, location on the Fuel Floor
("pile" as specified in FH-102 (COL), "Row" with number 1 starting from the north and west walls and "Tier" as the level position with the lowest position being 1) and Date ruel inspecteo on Fuel Floor.
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f A-44, Rev. 3
,Page 11 of 14 KWH rgs
(.')
5.9.2 A-44-lb, Temporary Fuel Storage Data Sheet (Form M-21975) - This sheet is used when fuel received is not stored in the New Fuel Storage Area.
The "Temp. Storage Area" column should describe the area of the plant where the fuel is stored.
The "Location in Temp. Storage Area" column should give detailed location information in the Tehtporary Storage Area (e.g. row, tier, column).
As a minimum this sheet shall contain:
Container Serial Number, Fuel Assembly Serial Number, Temporary Storage Area, location in Temporary Storage Area, Date/ Time in and out of storage.
5.9 3 A-44-2, Fuel Inventory Summary Sheet (Form M-21976)
This sheet is a listing of the site MBAs.
The areas are at defined in Step 4.2.
All fuel assemblies shall be accounted for in these MBAs.
Whenever ftel is received, shipped or transfetred, the Fuel Inventory Summary Sheet shall be updated.
The total fuel on site shall equal the sum of the fuel in the MBAs.
As a minimum this sheet shall contain:
date received, number of items received or shipped, total on site, number in New Fuel Storage,
<?,
Temporary Storage, Fuel Flo,or, Reactor and Fuel floor.
5.9.4 A-44-3, Fuel Inventory Log - Fuel Pool (Form M-21977) A-44-4 Fuel Inventory Log-Core (Form M-21978)
These logs are a location record of fuel assemblies in the Fuel Pool or Core.
The Fuel Inventory Logs are updated and verified correct at the completion of a fuel handling operation.
Normally, tabulations of Fuel Pool and Core positions are used, however, other,.
means are acceptable.
The fuel assembly serial 4
e number is entered in the space provided on the log cot responding to the location in the Fuel Pool or Core.
The Fuel Pool and Core Inventory Logs and the Storage Location Tag Board should agree.
After the fuel handling operation, the Fuel Pool and Core Inventory Logs are the official fuel assembly location records.
As a minimum A-44-3 shall contain the Unit Number, Fuel Pool Locatien, Fuel Bundle Serial Number, and Name and Date of person revising the form.
A-44-4 shall contain the Unit NN er, Core Location, Fuel Bundle Serial Nun.Ler, and Name and Date of person revising the form.
Both A-44-3 and A-44-4 should be approved by the
((g Reactor Engineer.
~
l A-44, Rev. 3 Page 12 of 14 KWH:rgs (hh 5.9.5 Storage Location Tag Boards - These boards are plan views of the reactor and the fuel pool.
Each fuel assembly shall have a tag identifying the serial number.
The tags will be moved as its corresponding fuel assembly is moved.
While the Tag Boards should be kept as accurate as possible, they are used for inforraation only and do not constitute an official fuel accountability record.
5.9.6 A-44-5, Fuel Location History Sheet (Form M-21979) - Each fuel assembly on site shall have a Fuel Location history Sheet after placement in I
the fuel pool.
The sheet heading has spaces for I
the following information:
1.
Serial Number 2.
Date Received 3.
Date Inspected 4.
Channel Serial Number - Date Channeled 5.
Fuel Pin Changes 6.
Location 7.
Date In j
1 8.
Date Out l {T.
Fuel assembly locations are to be logged only
.g for movements of significant duration.
For example, fuel. shuffling between two core locations may require temporary placement in the fuel pool.
The fuel pool location need not be shown on the Fuel Location History Sheet.
Only the final location in the core must be shown.
The "Date Out" and "Date In" entries should be the date the bundle is verified to be in its proper location for moves made during a fuel i
handling operation.
Non-outage fuel moves should be dated as performed.
Temporary storage locations and time of movement are recorded on the CCTAS.
5.9.7 Core Component Transfer Authorization Sheets (CCTAS) - The CCTAS provides a sequential listing of the fuel and core component movements j
to be performed and shall be used by the Fuel i
Handling director in performing the fuel handling operation.
The CCTAS is a Form (M-21965, 21966, 21967) that is referenced from the applicable PH Procedure. A CCTAS is required for all fuel move _ents following initial inspection and storage in the fuel pool.
A CCTAS should include the following information s'
l.
Signature of person authorizing the work.
E Z,...........,.
... -. -. - - - -... ~....
{
A-44, Rev. 3 Page 13 of 14 KWH:rgs
(%
- v..-
(see FH-605) 2.
Date authorized.
3.
Column for Step Number 4.
Column for Serial Number 5.
Column for From Location 6.
Column for Orientation in "From" column 7.
Column for To Location 8.
Column for Orientation in "To" column 9.
Columns as required for initials of personnel required to document the transfer
- 10. Column for Time of Transfer
- 11. Column for Date of Transfer j
5.9.8 A-44-6, Non-Fuel Receipt and Storage Data Sheet (Form M-21980) - This sheet is required when non-fuel SNM is received on site.
This sheet indicates the location of SNM storage upon receipt. As a minimum this sheet shall contain:
Type of SNM, Serial Number, Storage Location, and date received.
5.9.9. A-44-7, Fission Chamber Inventory Summary Sheet (Form M-21981)- This sheet is a listing of the total number of fission chambers in each MBA.
Whenever a fission chamber is received, V ',
shipped or transferred, A-44-7 should be updated.
The total fission chambers on site shall equal the sum of the MBAs. As a minimum this sheet shall contain the Unit Number, Chamber Type, Date, number received, number shipped, total on site, number in Temporary Storage, Fuel Floor, Reactor, Pool or Irradiated Storage.
5.9.10 A-44-8, Fission Chamber Transfer Authorization Sheet (FCTAS).(Form M-21982) - The Reactor Engineer or his designated representative shall fill in the form before signing the authorization.
The person performing the move shall initial and date the form and return it to the Reactor Engineer.
This sheet is required prior to any movement of fission chambers after initial receipt (Exception:
See Step S.4.4). As a minimum this sheet shall contains the Unit l
Number, Authorized By, Date, Detector Type, Serial Number, MBA presently located and future MBA location, Initials and Date.
1
-1
.. =.... _. _.... -
f.
A-44, Rev. 3 Page 14 of 14 KWH:rgs (3
5.C.11 A-44-9, Fission Chamber Location History Sheet -
(Form M-21983) Each fission chamber requires an A-44-9 after receipt on site.
Any moves of the fission chamber must be entered on this sheet within three months of the move.
As a minimum this sheet shall contain:
the Unit Number, Detector Type, Serial Number, Date received, Location and Date In and Date Out.
5.9.12 Retention of documents shall be as follows:
1.
Appropriate data sheets, logs, and summary sheets generated by this procedure shall be kept in the Reactor Engineer's office or when the Data Sheet, Log or Summary Sheet is filled up it may be transmitted to Nuclear Records Management for retention.
2.
The Reactor Engineer shall provide the Nuclear Records Management (NRM) Syste.T. with legible copies of the A-44-3 Fuel Inventory Log, Fuel Pool (Form M-21977) and A-44-4 Fuel Inventory Log Core (Form M-21978).
3.
Health Physics Supervision shall provide NRM
('_l
- with appropriate Health Physics documents
~'
relative to the SNM as per Health Physics Procedures.
l 5.10 Materials Control Management 5.10.1 Periodic audits of the Fuel Handling records are initiated by the NRB (Nuclear Review Board) using independent auditing agents.
6.0 REFERENCES
6.1 10 CFR, Part 70 - Domestic Licensing of SNM 6.2 A Procedure for Preparation and Control of Administrative Procedures 6.3 S97.0.H General Handling of Co.ro Component and Irradiated Items in the Fuel Pool / Cask Pool.
6.4 S97.0.C Transfer of Fuel from the Fuel Pool to the Reactor 6.5 S97.0.D Transfer of Fuel from the Reactor to the Fuel Pool
((h-6.6 S97.0.E Transfer of Fuel Within~the Reactor 6.7 A-46 Drocedure for Maintenance of Plant Quality.
Assurance Records.
1 ST-3-097-350-0, Rsv. 2 P0go 1 of 7
/m3v
/d PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION SURVEILLANCE TEST ST-3-097-350-0 ANNUAL INVENTORY OF SPECIAL NUCLEAR MATERIAL Tcch Spect None 10CFR 70.51(c) & (d)
Test Freq.: Annual TEST RESULTS A. All (*) Steps completed SATISFACTORILY Performed by:
(Sign /Date/ Time)
Performed by:
(Sign /Date/ Time)
Reviewed by:
(Reactor Engineer /Date/ Time)
B. One or More (*) Steps / Test Results UNSATISFACTORY
~
Porformed by:
(Sign /Date/ Time)
Porformed by:
(Sign /Date/ Time)
Roviewed by:
(Reactor Engineer /Date/ Time)
IMMEDIATE NOTIFICATION Station Superintendent Notified By:
(Sign /Date)
Time Notified:
USNRC Person Notified:
Notified By:
(Sign /Date) 1 Timc Notified:
ADDITIONAL ACTION / TEST COMMENTS:
If any entry is made in Additional Action / Test Comments Section, person making initial entry sign here (Sign /Date)
EXTIBIT 3
_ __ _.-_-_ _. __,_. ~
l ST-3-097-350-0, RGv. 2 Pago 2 of 7 JR,S/msv 1.0 PURPOSE This procedure provides the necessary instruction to' perform a physical inventory of all Special Nuclear Material (SNM) in the possession of the licensee at Limerick Generating Station.
That includes SNM for Units 1 and 2 (as applicable).
This procedure satisfies the requirements of 10CFR 70.51(c) & (d) for an annual inventory of all SNM on site.
2.0 REFERENCES
2.1 20CTR 70.51(c) & (d), 70.52, Revised as of January 1, 1982 3.0 TEST EQUIPMENT 3.1 Underwater TV System 3.2 Audio-video Taping System 4.0 PRECAUTIONS AND LIMITATIONS 4.1 Any item that is being removed from the reactor cavity, fuel pool, or equipment pool must be surveyed by a Health Physics Qualified Person as it is raised to the.
surface of the water.
4.2 If this procedure is performed with the reactor vessel head in place, the SNM contained in the vessel shall be verified by the most recent Core Verification ST-3-097-355-1.
4.3 Signoff steps marked "SO" in the left-hand margin of the body of the procedure require a signoff on the Procedure Cover Sheet.
4.4 If a step marked with an asterisk (*) cannot be successfully completed notify Reactor Engineer immediately.
L h
l
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]
ST-3-097-350-0, R3v. 2 Pago 3 of 7 JR,S/m0v 5.0 PRIREQUISITES 5.1 Underwater TV system with audio-video taping system available to view and record locations of fuel and non-fuel SNM in the fuel pool or reactor core as applicable.
5.2 Ensure all SNM (as per shipping papers that contain the item serial numbers) have associated location History Sheets (A-44-5 for fuel, A-44-9 for non-fuel).
5.3 Radiation work permit available if required.
6.0 PROCEDURE The first section of this nrocedure covers inventorying of all fuel on site, whi.; **
second section covers inventorying of all non-fs.1 SNM on site.
The third section covers the handling of discrepencies encountered during the inventory.
IT IS THE RESPONSIBILITY OF THE PERSON OR PERSONS. PERFORMING THIS TEST TO ENSURE ALL BLANKS AND DATA SEEETS ARE CORRECTLY AND COMPLETELY FILLED IN.
6.1 Inventory of Fuel (Perform inventory for both units 1 and 2 as applicable) 6.1.1 Obtain copies of the most recegt A-44-2 Fuel Inventory Summary Sheet f
A-44-3 Fuel Inventory 3
Log-Fuel Pool, A-44-4 Fuel i
Inventory Log - Core and A-44-5 Fuel Location Eintory Sheets.
/
l BY DATE l
6.1.2 Verify the fuel bundle locations on A-44-5 Fuel Location History i
Sheets to A-44-3 Fuel Inventory Log -
Fuel Pool and A-44-4 Fuel Inventory l
Log - Core.
/
BY DATE 6.1.3 Using A-44-2 vorify which Material Balance Areas (MBA's-defined in 9
I Step 4.2 of A-44) contain fuel.
/
BY DATE
)
\\
I l
'l ST-3-097-350-0, RGv. 2 Pcgo 4 of 7 JR.5/msv 6.1.4 Perform inventory check of applicable MBA's as per the following steps:
6.1.4.1 Fuel Pool and Reactor Core A.
Suspend the underwater l
f TV camera from the refueling platform, such l
that a good TV picture of the fuel assembly serial numbers is
/
j provided.
BY DATE IF THIS PROCEDURE IS PERFORMED WITH THE I
REACTOR VESSEL READ t
IN PLACE, THE SNM (FUEL) CONTKINED IN TEE VESSEL SEALL BE
}
VERIFIED BY THE MOST RECENT CORE VERIFICATION I
i B.
Scan all fuel racks and I
core positions (as applicable) with the TV i
camera and record on i
4 video tape.
Location and the serial numper being viewed shall also j
be called out to a second j
person (not viewing the j
TV pictures) who will i
record them on a blank A-44-3 and A-44-4 l
(as applicable).
/
BY DATE j
]
If ST was used to verify core record l
j date ST was completed j
in Additional Action /
Test Comments
)
Section.
1 t
i i
1 t
'l ST.1-097-350-0, Rev. 2 4
Pcgo 5 of 7 JRS/mev C.
Compare the A-44-3 and A-44-4 generated in Step B. to the Official A-44-3 and A-44-4 obtained in Step 6.1.1 and note discrepancies.
/
BY DATE D.
Attach the A-44-3 and A-44-4 generated in Step 6.1.4.1B to this procedure.
/
BY DATE l
6.1.4.2 All other MBA's as defined in Step 6.1.3 of this procedure.
4 A.
Visually verify contents of MBA to Aa44-5. Fuel Location Distory Sheets
/
BY DATE l
6.2 Inventory of Non-Fuel SNM (Perform inventory j
for both units 1 and 2 as applicable) j 6.2.1 Obtain copies of the most recent A-44-7 Fission Chamber Inventogy t
Summary Sheet and A-44-9 i
Fission Chamber Location
{
Ristory Sheets.
/
2 BY DATE i
6.2.2 Using A-44-7 Fission Chamber Inventory 4
Summary Sheet verify which MBA's contain non-fuel SNM.
/_
6.2.3 Perform inventory check of applicable MBA's as per the following steps:
l 6.2.3.1 Fuel Pool (LPRM's only)
.T.
Verify all tamper seals are intact and.have proper mark (RXE/ LGS)
/
BY DATE 2
1 i
- = -.
l ST ' 097-350-0, RGv. 2 POge 6 of 7 JRS/mey B.
Verify Perial numbers stored in pool to A-44-9
/
BY DATE 6.2.3.2 Irradiated Storage (SRM's, IRM's, TIP's)
A.
Verify all tamper seals are intact and have proper mark (RXE/ LGS).
/
BY DATE B.
Verify serial numbers stored in irradiated storage to A-44-9.
/
BY DATE 6.2.3.3 Reactor Core (if' applicable)
A.
Count the number of installed strings of non-fuel SNM.
If the reacter head is installed the number of outstanding chambers listed on A-44-9 (upon completion of all other MBA's) shall consist of 43 LRRM strings, 4 SRM's, 8 IRM's and 5 TIPS)*
/__DATE BY 6.2.3.4 All other MBA:s a.
Visually verify contents of MBA to A-44-9
/
BY DATE 6.3 All SNM Accounted For
/
BY DATE (*)
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ST-3-097-350-0, Rov. 2 Pcga 7 of 7 l
JRS/cov 6.4 Bandling of Discrepancies 6.4.1 If a discrepancy is encountered during the inventory, repeat the necessary steps to resolve it.
Attach to this procedure a written report giving a brief explanation of the discrepancy and the steps taken to resolve it.
If there are no discrepanices mark this step NA.
/
BY DATE i
So
'6.4.2 If a discrepancy remains unresolved after performing step a
6.3.1 the Station Superintendent i
shall be notified immediately.
SO 6.4.3 As per the requiremnt of 10CTR 70.52 the Regional USNRC office 4
(see 10CTR73, Appendix A for i
address and phone) shall be l
notified immediately (via phone) of t
1 any discrepancies found during the inventory.
6.5 Send a copy of this completed i
test to the Licensing Section i
of Electric Preduction Department.
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. SOURCE RANGE, INTERMEDIATE RANGE AND POWER 1-i thmugh 1-28
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SECTION 2 TRAVERSING IN-CORE PROBE NEUTRON HON!TORING 2-1 thrcugh 2-19 f
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..~.SECTION 3 PROCESS RADIATION MONITORING SYSTEM 3-1 through 3-33 I
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'.. SECTION 4
' AREA RADIATION MONITORING SYSTEM (OPTIONAL) 4-1 through 4-5 j
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r Ind detector wells which comprise any' portion of the pri-u "';' F.. mary pre.ssure.vess..el.and piping.
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Connector A'isembly Instructions, GEK-45754
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EI.'2,3 ' Reference Documents listed at the beginning of each section of the
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- jf.I.N::.;n:.;'iI.3 ? ; DESCRIPTION ' "
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.. Neut.ron Monitoring Systems 4
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Incore Probe Neutron Monitoring System
',3,..i. ?.d W...?!].jh.;hSeition'3(..raversng v
Pr'o' cess Radiation Monitoring System consisting of:
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Main Steam Line Radiation Monitoring System q, [.w..: $ q; " W..f i
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'. 7' Contents and a list of reference documents.
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.' GENERAL.. ~
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,.1.1.2 Reference' Documents List 1-1 1-2 i
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' EQUIPMEN. f. !NSTALLATION l-3 13 t
1.2.1 Prerequisites
! *"..., 1.2.2 In-Core Housing Flan e 14 i
l 1.2.3 Detector.TubeAssembIy 1-9 1 13 d
1.2.4 Detector Tube Installation 1-16 i
I 1.2.5 Detector Tube Leak Testing l
' l.2.6 SRM and IRM Drive Mechanism Adapter. Motor Mcdule I-I 7 i
and Preamplifier Installatien 1.2.7 SRM and IRM Drive Tube and* Drive Mechanism 1-18 i
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Installation l
1.2.8 SRM and.IRM Detector Assembly Installation
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. 1.2.9 SRM and IRH Flexible Drive Shaft Installation 1-25 i
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'M PRWCabl e' Ins tallatt en 1-27 --
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.T I.T LE PAGE 1-1 In-Core Flange Seal Test Plug Parts 16 l
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' SOURCE RANGE, INTERMEDIATE RANGE AND c
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.W8f"q'*IOi1.J.The Source Ranga Monitors (SRM), Intemediate Range Monitors (IRM) and 1
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Ponr Range Monitors'-(PRN) perfom different functions and contain different i
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.: types and amounts.of equipment; however, the installation of the three neu-l 4'
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..w Ni.S?iY1f iach' monitoring sy' stem.s composed of several separate instrument channels.
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+ f "
provides inputs to the reactor safety system; as such, the installation of the equipment must' fully satisfy all reactor safeguard sysi.em requirements t
'.3. concerning channel separations and equipment reliability.
s.
i 1-1.1.2l The following documents contain infomation concerning the installation i
of.the Source Range, Intermediate Range and Power Range Neutron Monitoring i
l
.P. System.s equipment.. The plant unique data sheets whien supplement this in-
- struction list the General Electric Master Parts List (MpL) number for each j
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Reference Documents
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Reference Number Descriction 4
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l.1 SRM/IRM Drive Unit i
McLor Module j
1.2 1.1 Dry Tube 4
1.4 Detector Drive and Shaft
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1.5 Reactor Assembly and Installation L
1.6 Field Cleaning and Cleanliness Control 1.7 Electrical Equipment Separation and Safeguard System Special Wire and Cable Specification
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1.8 r
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1.9 Startup Range Neutron Monitoring System
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Elementary Diagrams 1.10 -
Startup Range Detector Drive Control 3
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System Elementary Diagrams j
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EQUIP. MENT INSTALLATICN
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.m m$..;@'.9f..m1.$.$$ These' inttfuctionc. cover ocioinal equicment installation _ only.
Equipment removal and installation af'ter actual use will require i
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E'J ; ;.(radiationf exposure and the handling of radioactive equipment.
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NOTE l
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- i n.r.and ppd (LPRMS) detector tubes.are installed from the top of the l
9 ;.,y:., reactor pressure vessel..
It is also necessary to install the SRM
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. and. IRM. shuttle tubes inside each SRM and IRM dry tube before in l
. M:
- stalling the dry tubes in the reactor.
Except fdr the detector
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tubes an(, shuttle tubes, all other neutron moni.oring equip.ent l
- A " is either-installed 'in the containment, the reactor building or
'. 7; J f.. c'.7. - in the main;, reactor control room.
8efers cocinencing installation.
's.f.....
1.~ - consult References 1.11 and 1.12 for information concerning
'.l.; ",. i f the design'ahd arrangement of each SRM. IRM and PRM comoonents.
{
Ideally, to avoid equipment contamination and' damage. all tasks associated with asse1bling and actually installing the various J
i
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in-core detector tube assemblies should be accomplished in an 3,' 7.,'./ t.
expedient and uninterrupted manner.
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1.2.1 Prereeuisftes i
i 1.2.1.1 The following tasks must be satisfactorily completed befort installing
.' the SRM. IRM and PRM detector tube assemblies in the reactor vessel.
(
a.
The reactor primary system hydrostatic test j_
b.
The final installation and positioning of the reactor core
'im top gutde l
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l ing of 'he reactor vessel and all systems that flush QF t
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.i;E.W:. 5. intothi vessel per Reference 1.6 f., 1 "1l Q'y'
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%2C '. 2 1.'2.1.2 Due 'to task interferences that could oresent themselves later, the 4 r#5; J ' control rod I'. rive mechanisms should be installed before installing any in
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,1". 2. 2 In-Core Housinq_F1ance 7
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- The.following staps assume that blank flanges were used to seal
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ali vessel in-core housings during reactor pressure vessel nydro-1
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static testin If tais is not the case and the detec. tor tube l
' acceptable ing. core housing flanges were plugged and used, refer 1
1 f,v..
/
' to the core' plot plan (Reference 1.11) and confirm that the 1/
J-correct type flange is installed on each in-core housing, i.e.
SRM and IRM in-core housings should be fitted with flanges thi+
i have feur. threaded belt noles, one hole centered between each l
attachment bolt hole.
Conspicenusly label each housing, see Step I
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1.2.2.5, and then prtened to St&p 2.3.
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.. '. ~,1.2.2.1 Unpack the SRM, IRM and PRM in-core heuting to detector tute seal flanges anc inspect each flange for dar. age and cleanliness.
Verify that t
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the flange to dettetor tube conical
- sealing surface and the 0-ring sealing s # ace.are r.et scratched, nickec or marred.
Clean the flange and especially 1
the flange sealing surfacts with lint-free cloths and fethyl alcohol.
I. J. ".
1 1.2.2.2 Inspec't'and'banthetefloncoated0-ring,providedwiththereacto7 vessel for each flange.
1.2.2.3 Confirm that sufficient flange to in-core housing attachment bolts
(
i are provided, four bolts for each flarge, and if necessary cican the bolts.
ly
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1.2.2.4 With administrative coroval.t to peceed with the ;nstallation, tnns-pcrt the flanges',. flange 0-rin j i
,. room under the rea: tor vessel.g and attachment bolts to the control red i. rive 1
l 3
- l
(*.. 1.2.2.5 Using the latest reactor assebly drawir.; core plot plan, see Refer.
e
,,9....
'- 'ence
.1.0, identify each in-core housing nczt.le.
Conspicuous 1.y l uel by channel number each noz:le as an SRM, IRM and PRM in-core housin; estn, i
,@';a 3 acceptable adhesive tapec or by attaching tags te the ovtyide surf tc0 of j
?.-
. the in core tube above the tube no::le.
Each in-core housing ust!all) con-q 2:n. o.,
H.'
tain: a detector
. @m.:?:1.2.2.6.. x ' ::.$; tub e,
+
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With the"reactor pressure vessel empty and depressurized, c3rsfu11y 4(' VQc%re:Nye the blank flanges from all identified in-core tubes.
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'directly under the flange or positioning the cleaned equipment i.s..,2p....L.h.DM... ^ : u..n.de. rJ tha, flange being removed.
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.:M.u.W1.9. 2.7. Using a portable light source, carefully inspect the in-core tube
.and tube nozzle,for' cleanliness.
All internal tube surfaces and nozzle
. ^
.S;, e..:6 i.) s+.f n.ating surfaces must be clean and free of any surface a'urasions.
If neces-t sary, clean the rozzle mating surface with ethyl alcohol and purge the tube
.q'.*-
with clean compressed air, demineralized water or other approved cleaning r.-
- .! T method per. Reference 1.6.
The ln-core housing nozzle and flange must re-
. c main clean..
,-l7 1 ( threads. ';.;,1,2.2.8. Apply the lubricant specified in Reference 1.5 to the flange bolt lt.f.3.:'..M y L..:.':L;' Q.?
.'c.. a;% '.c.:1.2.2.9 ; Trial. fit'lthe' flange seal 0-ring to the in-core housing nozzle.
..).y.,; u. s
.. f t.
.l.2.2;10 '. After ' con. firming that the 0-rings fit properly, select the proper
" type flange., i.e'.".,.SRM, IRM or pRM to install on each in-core hcusing.
....u..
> ;e...
~
NOTE 1
v.
- k a
.(, If, rather than waiting for a vessel operational hydrostatic S...h' 9..;8... pressure test,. the pressure integrity of the in-core tube to
/ / '.
. P.:;L..c. flange.. seal1s.to be tested as each flange is installed, oro-r......<:s r;.u.- ceed as follo,ws; othemise, perfom only the applicable portiens
~
.Q. ';.... 'Jd/^ 7of. Steps' 1. 2'i2'.11.9 through 1.2.2.11.11 and pr6ceed to St'ep 1.2.3.
~
.....,o
.s
..,y..
f.s 1 2. 2.11. Fl a rg e S.,e.al. Testi ng
.' y-.
- x.....
(
s NOTE Because of'.20 in-core housing seal arrangement of the in-core
.. r.
flange seal test plug, see Figure 1-1, the in-core plug "V" ring
),.f/,
packing ' seal.. retainer and split washer mus t be assembled to the body of the pl6g after the plug body is inserted through the in-
~
.., ~,.x w... ;.L:.. core tube. flange to be tested.
This is possible only with the
- flange disc.o,'nnected frocn the in-core tubc nozzle.
J'.N. :..,
i
, ~.
~
.w
~
- IV.al172.2;11.1- '
Refer' to' Figure 1-1 in perfoming these instructions,
' M, 'Q2.2.11.2 Disass,%ble the flange seal test plug as follows a.q.
- 9.. q r,
.d:.
7 p?.. ~:.. :..q;[., T,~ Removell.ug (1) and 0-ring (2).
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iN-CCRE FLANCE SEAL TEST PLUG PARTS IDEhTIFICATION 1
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,,2A4211
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SHEET NO.
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Q?jf.(lk.5,'N l$?l
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. ' '. 'T.9-:
- b. l0$iNew' ~ it (3) and remove seal retainer (5,12) with seal (6)
Eg@giQgj?"
n
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r.gf~e41%
and split washer (10) from the test plug body (7,11).
. i,.
M i 7 1.2.2.11.3, A' 'ly.' teflon tape (8) to the threads on the test plug body (7,11).
1,
. :. : r;r.. -:
,, e.
,, (.
e.
? M.&[? '.;1.2.2.11.4,-. Place.the in-core housin I
With the in-core flan e disconnected from the in-core housing, t:
r.
f-
'. : thread the tool body into the f ange and tighten.
.I
' 1.2.2.11.5 w. v.,
? Q" ' :. c.1.2. 2.11. 6 ' Assemble the seal packing set (6) over the threaded end of the test plug seal ret'ainer !, haft and seat the packing set against the upper
.. ',,,,2.~ retainer stop in.the following order:
l
~...
'. ;.v.,.
a.- top adapter.
l 1
4:? ~ f,5-b.
split.V-ring l
i f M..1...
c.
solid V-ring v-1
.t 7 7
- d. 'sr. lit V-ring
- e. ' solid V -ing I
f.
split V-ring 1
g.
bottom adapter
.NOT1?
l l
The slits on adjacent split V-rings should be spaced radic11y, j
l 120 degrees apart.
1.2.2.11.7 Insert the seal retainer assembly into the test plug body and thread the nut (3) onto Me shaft leaving a gap of approximately 1/4 inch (6.35 rra) between the uppr retainer stop and the seal, j
1.2.2.11.8 -Insert the split wathers (10) into the 1/4 inch gap with the washer
... slits 90 degrees. apart; then tighten the nut (3) sufficiently to retain the washers.
"~
! A y\\;
r-go7g l
s.
Over-tightening the nut at this point will expand the packing set, making it difficult to insert the test plug into the in-core housing.
~ -
1.2.2.11.9 Position the flange 0-ring on the flange, then carefully fit the
' flange and test plug assembly including the 0-ring to the assigned in-core
' g '.. '
c.l housing.
Just.before the 0-ring makes contact with the housing, verify that
. L"!-l
..:.'.'the 0-ring is. positioned properly to the housing.
(.
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LIMERICK INTERNALS INSTALLATICH,
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SUBCONTRACT NO 8031&sC402
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- .~4mpiinnnred J't.
61 '.'. G E N !R A L Q L J CT R I C 2
22M211
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SHEET NO.
I*O
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.,...g
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f.
.I Lubricate the bolts per Reference 1.5 and hand tighten a bolt
.~
?>
- 1'.2' 2.11.10 '
J, ',, s
':r in h of. the four flange holes.
Observe that the housing and flange
,. 'es 'h: 32.2".'s. eacaling' surfaces femai.n parallel and that the 0-ring and bolt holes align
'MJL (!:,i. pro
- .M.m:i.::,M.%perly. with the housing.
l./;%:; 7 '2.T.11.11? Torque the attachnent bolts to the value l(M4 - W 1. tor. Assembly Drawing. Reference 1.5.
'P c.M.'- V. -
M.
.e M,.$..$// 19 1'.2.2.11.12. To' expand the v.est plug packing set and seal '.he in-core housing, A
h h.
..x.m;W;pw,m:c..t.en..te,. nut (3).on the bottom. of the seal retainer :.naft to 2122 ft-lbs.
., #. :..m :. e
.m
. 3E!'.".'".1.2.2.11.'130!nsta11.'.the test plug body bottom 0-ring (2) and tighten plug (1).
?,
s<
.., '.. :. w :.
7l.,a (;,;.
CAUTION i
..2..'
If not controlled, the pressure used during leak testing could
~
..f
,1...?..M.;;n... t.w_..
cause. serious. injury to personnel and equipment.
- ..v g,.
..-* a...,
.. g v.
l i d.}'i. W.1,'.2.2.11.14.'Using~high pressure equipment, connect a source of deminerali:ed l
?'.m':C.',@@ater to the' compiession fitting on the test plug body and carefully pres-MEiE 'l..s6ri:e.the. assembly to 1850 psig.
Verify that no leakage occurs at the
.5 't M.,...in-core housing, flange.
f r;. -
s ' - J
.t'.
. 3..p y51 2;2.11.15 7Ur
,;;m'* letion of testing s.m
.. C.{3-n--
.y,.-.
- omp
, release the pressure and remove the
's.-J,
',Y%ater source. om the compression fitting.
........ ~.
o -
w. ;..- ::;\\
..'PT. 5 1 2.2.11.16... Removelthe plug (1) from the test plug body and unthread the nut l
o
- k..
. ~ L (3).from the~sealtretainer shaft.
. q ~
~
r
,. v
, l H l.2'.2.11.17 ? Unthria'd' and remove the test plug body (7,11) from the flange.
- m. ~.
.:.l.2.2.11.18 Pull' down on the seal retainer shaft until the bottom packing
$..:0
~ .M.;y'0 ring in:the inh: ore flange.
~
- 5. '
set' adapter' of. the seal is approximately 1 inch (25 mm) above the metal g. '.
.or w
,-1.2.2.11.19-Tap the bottom of the seal retainer shaft until the shaft is (9 ~ '..i; fret in the pack.ing set.
c.
['1*'li2.2'.11.20 CWhile]1olding the shaft, insert an improvised wire hook into the flange opening and separate the bottem adapter from the lower split V-ring u
'. ' Jin the seal packing' set.
,v
.9 7
NOTE
(. > ? f;. ' :
'v.... t.;. ;
.k.. '.M.
J '. Hook the split'l-rings and the bottem adapter close to their re-7QL..@v.M.o.FO. spe.c.t..i.V.e s..li.t..s. so that they will straighten to simplify removal.
u.
..q....,.....,
=
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1.lMENICK INTERNt.LS INSTAf.4.ATION y'. D'g,. ;G.4:T.9.X ':7
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' $(h;I M.C.Q: "TRACT NO. SOEl.FSC 202 2'
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TF4&Ml.E Lf CTRI C 22A4211 W.b. fM4:~*
9 3HEET NO.
1-10 y
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~
.r c.f@?$p?lT l'.:
4 ili t V-a lile proViding adequate horizontal support, lift and position one bh.th'e dd' ered floor with the bottom end of the tube towards the v
tube ~eohtainer.
lapter fi YOU'
[G NOTE
...;h, 'g?.r' [J.
- 'W.%,
f.. of the ' detector tubes will be properly criented in the con-1ers.
Thsse tubes should be removed first, then rotate the I
tainer.180., degrees and remove the remaining detector tubes.
i
!bove.'t5e"detector tube protective covering and, using clean, lint-ths and ethyl alcohol, wipe clean the exposed tube surfaces.
from the
- 7. '.
seal test _
nspect the tube for damage and cleanliness, especially around and swer beveled sealing surface.
This surface must provide ~a water-al.with the,in core housing flange.
- 0-ring
- Nt +
rial, fit the provided detector tube retaining washer and nut to the
- d. of the tube.
y
\\
emove the' detector tube nose guide and inspect inside the tube for
.ombina-nd cleanliness.
If tne tube is a PRM assembly, reinstall the tube l
l iners in de and move the tube to the far edge of the covered floor area for l
l ting, ce testing.
Repeat Steps 1.2.3.4 through 1.2.3.8 Entil'aii'SRM/IRM d,ry.
f l e, dry tube without detectors, is located.
i ith an SRM/IRM dry tube nose guide removed an4 in position adjacent 2ntainer, adequately support and remove a shuttle tube from the container.- Wipe the ' shuttle. tube clean using lint-free cloths and ways cohol.,
y ling Inspect the shuttle tube for damage and clee.aliness.
Record the
.nt tubo seria1' number.
' ;trono-
~
When clean' and dry, insert the shuttle tube, tapered nose first, ly into.the' prepared SRM/IRM dry tube.
l ive the
.O iil tube Reinstall the dry tube nose guide hand tight, decord the dry tube reused umber tog' ether with the shuttle tube number as an assembly.
Pro ~pe rlyl.Yr:. identify the dry tube-shut.tle tube assembly by inscribing
, als t indelible markings on the nose guide and attach approved adhesive the tubes the' loiest dry tube outer surfaces just above the' nose guide.
Then
' ly and assembiv.towards the far edge of the covered floor area.
i
! ners.in C
/..
each con.
Repeat' Steps 1.2.3.4 through 1.2.3.13 until all dry tubt are removed container, cleaned, identified, and the SRM and IRM dry tubes all shuttle tubes.
^
].,,/.y[,
LIMERICK INTERNALS INSTALL 4 TION,
c",C' PROJECT No. LMI82 Koa,
. c, r.2h suscONTRACT NO. 8031*FSO*2O2
. s.
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9.i.'. h: p ara..een W5 apacon se No #M -
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<4 SHEET NO.
1 -l1
, v - 7 3.. : e..
a...
~ Q.:L ;.i :.~.
, O cs v;.1'.2.3.15 Remove'the remaining dry tube container packing and support mate-c.F~. :
,:ldW:.i.. ' rials and the albe.inum foil lining, 5.7 1.V.":.i.. l.2.3.16 : Clean the internal and external surfaces of the dry tube container, TME Allow the surfaces to dry, then line the yhp:Eq;./.then clean the"aluminum foil bag./.s ;p.. yy.7,inside 'of'.the,'c Do not reinstall any
, er.! other packaging material s.-
,$y!.y C.N;.iq.~/:~...
......' Rem'oveTa'ch PRM (LPRM) detector tube nose guide and expose the four
,.D V. 8 1;2!3I17:
All connectors must be identified Fc '
q$ 5 N. {[' internal'detectordstring cable connectors.
%? W.;. (etched),~ AT B*,' C-or D and be staggered axially in position according to the axial: location.oflthe detectors in the tube, i.e. a "D" detector is located 4.d.E[.Ldfy[itube.at the upper. e'no.~of.the tube, "A" detector is located at the lower end of the c: w See. Reference 1.13.
..a v
..;.. e ; ~
v
...v 25Q. f.i. 2.3.181 ' Det' cto,rfAs.sembly and Cable. Insulation Resistance Testing -
U l
e
.cy.r.g.p
...G;.m eG ;,.,
g"5hiSE;;hy;9.n.:...
$ ce
.3.18.lECarefu11y.~reinov'e each connector covering to exposa the connector Nm; metal' centerc6nductor and shell.
Do not tou e the connector directly: use
..}j[;[Qg'! clean'o16ve's1'plf%
-.;;. ;o,W ;: ~...;; W.'
. 7;
";;W } $ f'6t,ehu Nalent, resistance meter.e 112.3.18.2.9 Set up' and verify
..t.' ?h I
Review the meter manufacturer's instruc-
..,MrMi?.t]on manual'.for operating details,
+-
m ;.m..
~
~
i's..1.2.3.18.3... Connect the resistance meter measurement lead to the center con-
~:. ' -M' detector connector 'shell, and to a coed earth ground. With the meter test
{Nij.M1;;W;vl'h.ioltagii'sitl t610'v'olts, charge the assembly, then measure and record the
... resistance.. ' The. indicated resistance should exceed 10' 0 ohms.
P.I.;.m,... x M :
Vi Q.3 Q'M. ' N.li2.3.18.4M Repeat Steps
~
1.2.3.18.1 through 1.2.3.18.3 on each of the remaining
'PRM detector? assembly cabic connectors.
If any resistance value is less F',.than 1010' ohms, detemine whether the assembly insulation has failed or r.l;'... ' fli.t.he.', connector ':is ". defective or contaminated.
If necessary, clean or' replace
' ' i,'. (,'any faulty' connectors.
See the Connector Assembly Instructions, GEX-45754
'."., "N.xNew connectors 'must be etched correct 1,) A, B, C or D.
If the detector re-r
. sistance remains ?le'ss than 1010 ohms, notify the CE representative for i,.
. fins tructions..
. J.y; b.y;rW V"
'y-
- S;,c 4 0,1.~2.3.18.5. R6 cord the' PRM tube serial number (this number is located just b y,T;7below the tubefretainer nut threads) on the check sheet adjacent to the
.'$ ;t'ubs number, rec 6rd.the detector string identification, A, B C or D serial
,, y,%c.. (i ndnb,er,' a'n'd' the'Ye'sistance value of' each detector.
This information will d
.i.;b.e',revieie,d and'2'.*'.ed in plant administration records for reference. -
,s
-.fil -
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V. 'f,2 W,y."_ Q,;;@' l
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PROJEcy no, gyg,82
,. /.
SUBCONTRACT No. 803ff5ic 202 i
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7* ' -
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)
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CT R I C 22A4211 da.Mw.
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- u..%
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-r swser No.
1-12
_ p ge-
, g-ef w. ' -~ e-
.. m g..d....
'd, ' % a.
- M.
'Y-y.m.,e%
~..
n w-JMW1 B'N%.2.'3.18.6 ; After"satisfactorily testing all PRM detector resistances, reseal theTconnectors.intthe plastic covers.
Then carefully insert the connectors NA$7hlinto'the'detectoFtube.andinstallandhandtightenthetubenoseguide'.-
me&,p$ 11','2.L.19f.' Return the assembled and tested detector tuSe assam 4yQu:gn;. :4.. w.
e
.e
.o i
./.
l 4.
M. %k6c1'ean'and:Felided:large shipping container.
Orient all the tubes so the l
e ANN 6hF I
YEb$d$$.%&guideEc6nta'ct the same. container end plate.
' R.%. ~. :.WN 47/Q 1'.2.3.20. Fo'r'conseic'utive in-line core installation, stack the tubes in the
- [T'.hMcontainer.iif rows'of six or reven.
f Each row should contain one or two SRM/
j:%3. M ST.IRM' dry. tube' assemblies.
7 Do not reinstall any packaoine materialc, soacers
. r.n 4. -yyp sunportg,'
- c. + &. >..
- h..y- :'
5 NOTE d.y..w.c.7d, D Q.... Tot.' avoid damage, as the container is' filled or moved, observe that k,w.,.p.,f.6$.).pMthe tube sealing surfaces are aligned but are not touching each p
5"h:v.=.g oth'e r.;n.. ~. ^. ;
.?
a f,.h
.r*.. } >
- .my.9.. w, g.v.. ~..Q M1.2.3.21 ' Repeat St:eps 1.2.3.1 through 1.2.3.20 to assemble, test and u
w.
leg.KOQ4# shipping"container.ifnecessary, dLf E Wu.N... ~::.'.'
.gC.tl.2.3.22. When the large shipping container is fillM. fold the aluminum con-
- . '.L'& 5.(t'ainer. liner over~ the tubes and install the container lid sections over the
!. Y.'j.imiddle'a'nd; top ends of the tubes, These lids and the foil liner should hold "W@;cMthe. tube' assemblies.. loosely in place-with the lower lid removed and without
.y
'!/"addition,a1 support, or packing material.
This should be verified as follows:
,; n.a.oD m.g..s.
~
1 JQ ( ).1 '. 2. 3. 23 Usiag an overhead crane fitted with a spreading, bar sling assembly, l y ".4& properly tached to the container-side cross members, slowly pivot the
!.4,:
s covered end of the container up to an angle of approximately 85 decrees
~
M.:Jwith the floor.
The tube nose guides should remain firmly against the
~:E.!? ( ~.'. lower container end plate.
Depending on how full the container is, it
.may' be necessary to. bolt a two or three-inch ldp across the end plate 2
' Nopening to stop the top tubes from slipping out of the container.
l 1.2 3.24 Inclined at'about 85 degrees, lif: the cortainer'a few inches off 3
l E.
r~
the floor and verify that the container adequately supports the tube assem-
+.;...
bites and that th;e' container angle remains constant at about 85 degrees.
CAUTION
.g Avoid positioning the container vertically beyond 85 degrees.
/
This could cause the tubes to shift position inside the con-tainer and possibly damage the tubes.
~~ ----
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W PROJccr no, L.MI.ac
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succogy
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7 ELfCTRIC 22M 211
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.M.5 GENERAL.
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swerT No.
1-13
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m.4.
7.*J
.3'.253 With the~ container suspended a few feet above the clean floor area, y (W@;.tgW{'all"th'e 11d ' covers,\\ and rearrange or rem onfirmithat'onettube assembly can be removed through the provided lid open-E i
lly, remove
- .~l.'$@[;!'f".pp. in~gN If..thislis. not' possible, r n
~
v.-
I
'J.
MTh'eli repeat' Stepf'.1'.2.3.23.through 1.2.3.25.
Repe'at this"pr:ocedure for each
.y;f:9 l!'m:y. i:ontainer.,,'
-W.
3 M*
I r:. _ -
j
' Y,'
'.1c2.3.26..If : crane other than the reactor building crane was used to confirm l
4'.W '!:.. ' ' ~."that the containei supports and detector tube arrangements were satisfactory
,W.M ffFor, if the' detector tube installatien will not comence imediately, install
- 5. w..the fina11 container lid section.
o;
.3 2
~
, 7
".1'.2.4. O_etector Tub Ins talla tion e
?
n.
m NOTE tr 4; m.
e r-
".fdi,t:...:,:n..
.'nt least five men are required to install the detector tubes in l
',ln,t.. H..
the reactor. pressure vessel.
These men should be stationed as j
. J.
follows:
j
.n.
'/ I
- OnecraNe'Ioperator on the refueling floor, f,V ".:
I
.~
Two technicians on the top guide, f
P One. technician on the lower core plate, and One technician directly below the reactor pressure vessel.
~
i
~
Good comunications mutt be established and maintained between the in-vessel technicians, the crane operator, and the under l
ves'el technician.
Also, a clean source of demineralized water l
N-
^
s should be made available under the vessel to flush the in-core
(
housing flange and detector tube mating surfaces as the tube is inserted into the flange.
1.2.4.1 After receiving administrative approvals to install the detector tube assemblies, verify that the in-core tube flanges have been installed properly and are. clean per Steps 1.2.2.1 through 1.2.2.12.
Then, carefully transport the
. ;- J filled detector tube containers to the reactor building refueling ficer area where the reactor building service crane can be attached to each container.
i
^7,
- ~:.
!26... O,:1.2:4.2 Securely attach the reactor building service crar.e. using an appro-f,".,- J'.q: priately rigged ~ spreading bar, to the selected detector tube container.
c" l Again, attach the crane to the container side braces in such a fashion as to position the container at a fixed angle of about 85 degrees with tne t
.t.
'N '
floor when the container is lifted.
Verify this before comencing actual
'~
./
- in-vessel work /P '
?_Q,.
- f.., Y. '%. )' ':- l 7 -
i t.', 9 '.
3
'e 3 LIMC AlCK INTERN ALS INETALLATION n, a..
$'.'.c'g' i }, h). ;
PROJECT NO. LMI.82
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SUSCONTRACT NO. 8031fDC 202
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.d CAUTION
.Y u
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.c, "...
Review and adhere to all rules and precautions concernino work
.wn. :.%:. :.'n.*, inside or directly above the reactor pressure vessel.
. v c,.c'. g M. '
Before..comoncing in-vessel installation, it is imperative that
['? 3;;[ ~,.thf technicians have the latest certified copy of the reactor
,0,' 4.;?:..i,.
core plot plan (see Reference 1.11) which correctly identifies
' C ' '.. "
the~ exact core quadrant location for each type in.-core dry tube Th'e technicians will use this document together with
' t the previously; recorded data to verify by serial number where Of?. 6 l:c,:c::.? assembly. /:
- , each detector, tube is actually installed.
. t:;,,k1 h.74.3 'Be oh moving the container over the reactor pressure vessel, clean iF' F.V the' external container surfaces and runove the one lid section covering the
- k 7.@ tubef. nose?g'uide's. W... '
..g
- f. w.:.cp :ns :.,.:;; w.~;,e. m.
S-EM,4.112Mu....-...c.
- , n. 2
- ,:. ~. '. v...
.c.,tu..:
.4' Li/t'and. suspend the container a few inches above the refueling floor M-M,f:f. tto verify that,ths' container and container supports are adecutte and correctly' 3%$
.ag:- pos i ti on ed.' '-
oc
~
4 $.%p;,g.,'." ~ ~
W.91 2 4.5 Slo.wly mov.e..the container over the center of the reactor pressure
- u. e...; a:..
m.,d y..svessel openirq and then slowly 'ower the container into tne vessel until 9
[l5..;d.,;;gy.6
~...
norg.
,~... mf t g.
r n
~...:. :
1,... ;... e., m. L:.,.To avoid. excessive,ho'rizontal crane movement and to promete
^ A.Wi@'Q[.L'. easily /incitiilg' and reenrding in-core tube and core coor-".,g -
f dinates,'finsjall the dry tubes progressively across the core
. in an in-line;' eaving pattern.
"' U.
c:
w 1.2.4.6
... c..,
Using the core plot plan, de:emine which in-core tube to fill and
. the exact core coordinates where the detector tube will be installed.
.r.O... :..
J
- l{.4.7 To minimize detector tube handling, position the tube container adja-
[centto,and1 plate hole thmugh which the dry tube
,:F will enter th,nclined towards the cera.
e
.. reactor core.
....n..a..
. p.
J V.cl.2.4.8. Locate'the'orrect detector tube in the container (SRM/IRM or PR
+.,a. = %s. and ' record its seiial numbe" and the core coordinates where it will be
- . ihs tali ed..'
- y..
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y LIM ERICK INTERNALS INSTALLATION a.
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NOTE Vfgoh
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- '.?
- '.iT.:
- 0.?,.)g;g$.,.m Itfis.nportant that each detector tube be identified and that the
/t-h[gv.dcf[%[; ic 4 identification serial number and its core locat
- O
$. k. ',M [$+./ SRM 'and IRM detector, tubes must only 5
Q pds'itions.IJ;This procedure should be double checked and verified
,h;k:$th. +(.l.by.'.tfe "responsible engineer as being correct.
fih. '
'..l.' '.
CAUTION _
QNW%:k.,tv.% $WY'. ::.:Ub WMACQ The heaviest de'tector tube assembly weighs about 40 lbs. and their I
Do not droo the
.a #p.wG.M. ;;.., smoo'th external. surface makes handling difficult.
?!P.V,q.y
.. tube into the core or into the in-core tube.
- .--i.P..P,i' 7
..g eb ;' 1.2.4.9 : Us.ing clean gl' oves, carefully rermve an identified tube from the con-
..t t
Keep the tube fl!y$c5 ?T.tainer and'. lower it by hand tihrough the proper top guide hole.
? 'T:das'sembly.Jas' verticali as possible and free of obstructions.
9.3E..@@ A.T. f.;Z.' McWlQ -
i.id V2},.O.J,th'e assig'n'ed"y lower the. tube by hand thro
- l. ?.,1.2.4.10:1., Sl owl
- p'!4.d'
.h.
T c6f6' plate hole.
Carefully align the tube with the.in-core
ftube and ledrFth'e tube slowly into the in-core tube until the detector
$;~..M? tube seats' gently.is come together, flush demineralized water thro
~
in the in-core tube mating flange.
As the flange and
',p... yKM.ube mating surfac
, y,-nL..:. flange o.pening and' between the surfaces to remove foreign matter.
- N 'b-
- g -
.~.~'5._1.2.4.11 When the tube is properly seated, depress the detector tube spring
%. ;4 loaded top plunger and position 'the plunger in the proper top guide hole.
.It.is important to observe that the plunger is seated properly and thtt the
.ube is perpendicular to the top guide and lower core plate.
t r - ry.
._w
, '.3 ;. ~.,1.2. 4.12 From below the reactor vessel, lubricate the detecfor ' tube retain.
- ing nuts threads, retaining washer and nut with the lubricant specified in
. Reference 1.2.15.'
..L l'.2.4.13 Before installing the detector tube nut, observe the. nut part numser and that the net is correct for the tube.
SRM and IRM tube nuts do not have
.s external threads as do PRM nuts. Also, the detector tube support washer must enclose the nut raised face.
See Reference -1.15.
1.2.4.14 Hold the detector tube stationary with a wrench on the tuce flats located just abov'e the nose guide connection.
1.2.4.15 Slowly. tighten the detector tube nut.
A torque value of 50 foot-pounds should be adequate.
Do not exceed 60 foot-pounds; this might damage the tube or flang'e seal surfaces if dirty.
- f.....
LIMERICl! INTERNALS INSTAL' ATION
,pi, PROJECT No. LMI.sg l
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SUBCONTRACT Pjo. pogggg;;,ggg
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n 4, 3;1,;2:4. 16 e.C.h'e."clP.the tube nose guide.
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Do not
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remove.the. guide /-
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W 1*.2.4117 BInstall a111the remaining detector tubes repeating Steps 1.2.4.8 8.s p $.
3 gk.W,,. Ethrough11'.2.4.16'
GYl?
?..Gf;.
t 4.'
phr. :.Ll~;2.4.18 '- Af ter 'all the. tubes are installed, review the recorded data and con-N(h/.
!.:q..w..:Y.g?,. firm that the dat'. cre correct, complete and agree with all requirements.
a
%:t. is
.m '
'D@lh'f EMi 6Rl'.2.5 Detector Tube Leak Testinc
/.. b
.t.+
?;'.
- 1.2.5.1 When c11'SRM, IRM.and PRM detector tube assemblies are correctly J,i. 4 talled,;1eak test 'the detector tube to flange seals.
If convenient, t
- 1. -
rform' a vessel' operational pressure test; otherwise, perfonn an interim
,N '$.f'w'eak test by filling the vessel with demineralized water.
1 Either proce-w.. -
. M dure requires advance planning and administrative approvals.
During this
.ri '
i
.,:C.:.y'.Xy.Q y.crotect under-vessel equipment from water damage.
test '
t$M:;la2.5.2 If. tube seal leakage is observed, depressuri:e the vessel, loosen
- .M/' J4;.thd' leaking detector tube nut about 3/4 of an inch, and lift and rotate Q?.Nthe' tube momentar.ily.'.This will flush the seal with vessel water.
- f..%.e
..o.
', :.p /.... 0.w,..
v..~
4:
The tube should
'.i.*y @ c N.. 1'.2.5.3 Lower the"detector tube and rotate the tube slowly.
. rotate smoothly;:if. not, ag.ain lift the tube momentarily and flush the seal.
~
t.s. '.h {.D Repeat this prccedure until minimum. leakage and maximum smooth tube rotation
^.
,I,." !? ;'.a're atta i n e d... : '"
~
~..Q 2 :
.....:~.
,.~2 '. @y..c:..1.2.5.4 Toiique th'e tube retaining nut to between 50 to '60 foot-pounds.
If
...' :...r a.1,1eakage. persists,' repeat Steps 1.2.5.2 and 1.2.5.3.
c
~...
i S.[lU2.5.5 If after. numerous attempts, the above sealing procedure fails to
' M'?:n#u. seal the leak, cirefully increase the retaining nut torque until the leak J:N f
.l seals or 100 foot-pound torque is measured.
If tube leakage continues,
- ,,g/.[
7emve the tube ar.d flange for repair or replacement.
.o erg.y. y,.
CAUTION h/ -. ;,'ykh*,'r...
^
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t
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LIMERICK INTERN ALS INSTALLATION
'I
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PROJECT NO. LMI82
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-l.p.C.*f 1. 1'.2.6 SRM and IRM' Drive Mechanism Adapter, Motor Modules, and preamolifier vg*53;. h;-
Installation
- o. -
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..y
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W ::H.:
Adapter Installation
&.Ql%;1.2.6.1
~-? % * : ?.': ~
'.W Y G%.e. J'1.2.6.1.1, Remove the SRM and IRM detector drive mechanisms and adapters TM.i.p,(shipping'and storige protection and inspect the equipment for damage.
, ay a.g ?.r.y...
.v..%
'.1"2.6.1.2.. Pair each drive mechanism with an adapter and check for proper 4 9.Di/% fit." Inscribe a number on each mechanism and adapter pair set.
Do not
~
j'
'._ ^ connect.the' adapter to the drive mechanism at this time.
T c.
- . w
.t Mi'e lW.'.112.6.1.3[ Transport:the adapters to the CRD room and install one adapter on MC;TWthe'bottoli*of e'a'ch identified SRM and IRM lower in-core tube flange, see
?
4 g ' pgqR,eference'..l.l.' 6; Install the four cap screws and washers and torque each 6% : 'O,..i,g.,W:+m.,.rew to about 30, foot-pounds,
C sc m..:.v. t.w.,... e r.ca-
.r.n-a c.n
.y P.2;6:2!. Drive Motor Module Installation O} g.w.rr.
- yQ.:% 7 shipping"contain'ers in a clean dry area.
Unpack each moqug and inspect
..,jy.-Sin it for damage and proper identification.
See Referen':e S'6 c 9.1.2. 6. 2. 2 Verifi that the motor modul.e support brackets inside the drywell p a it' Yare properly installed and located in accordance with the containment g...n: Mr.equipmen.t. location'd'rawings.- Each bracket must be ori,ented 50 that the
- b. A. mechanical' output: of.the motor module taces the reactor pedestal wall and
.T; :.t.'. Sth~efelectr.,.i. cal. co.n..ne. cti ons f ace away from the. wall.
..,a.
i.1.l'.2.6.2.3i Tr.ansp'orlt the modules into the drywell, and bolt each module to Eth'e correct support bracket.
Do not connect the flexible drive shaft or
~
- 4the electrical connections at this time.
Provide adequate module protec-
. tion to avoid damaging or contaminating the modules during the construction pe ri od. -
.,v;
?./
lll~
.'.cl.2..6.3 P.reamplifier Installation s v.....
4 c.$.*u.; $1.2.6.3.1. Assemble the SRM and IRM preamplifiers and enclosures (panels) in
. 'c,iB. Wra clean dry area.4-
- Fi..v.., W. A u, -
.c
.~
s@g.EG. l..,2.6 3.2" Unpack 'each preamplifier enciesur Q*; -
.N.'. tr'c plifier.for' darig"e and proper identification.d'."p1,1fier~ and th The SRM uses a pulse pream-
.i.
. 41.,
- i. T S.t),pr6.3.3
.M!,Og:. 1.2 Verify.that the preamplifier enclosure supoorts are installed operly,in the. reactor building and that major construction in the area
.(.R;m;,,i,scompiet,ed.
,,. 5 i
LIMCRICK INTERN ALS INSTALLATION
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SUBCONTRACT NO. BO31.r sc.202 1
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6.3.4aTrans' port the preamp 11fier enclosures into the reactor building I,5>g.j %d'and; ins'ta11 Peach"enclosure on the correct support in accordance with the I; As M'a'ppFopriat'e equipment. location plan drawings.
Protect the preamplifiers I.;and;the connections from damage and moisture.
.p;;$N:n1; yO p g;..
, w:... y r. ;,
t W1.'${7.ifli?.$7.F.. SRMand -IRM DriGe. Tube and Drive Mechanism
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2.'... ??:.'.c;
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NOTE
"'@.F.k.dp.M.W.,)7.
S.',,
'w
.. :,. ".- % r. ~ -
%h. Befofe inst'alling any of the SRM or IRM drive mechanism, drive
?#@$,N?7'9 tubes t.i..ctoi.assembliesi.:a11' major under vessel construction I
M. ;lla;1.n;.w.y i'. wotk'.T. n..dTd.e,be' completed.
.q,,,
.bc W.
should.
The. area should remain free from conta-c-
RTWiBr.?.minants?.s6 chias concretr dust, welding slag or flushing fluids KW.p rg lI;.d; Mich;mightEl contaminate or damage the mechanisms, detectors or1.?.A drive cablis 9t h;:z.a:
idM'd..Y:d.M. e-e..w.: vy@ke"all> SRM/IRM drive tubes fro
- 6..4.. and con..nect a,l,l P_RM detector assemblies per Step 1.2.10.
?
.m l
' M* f,w..a g, W.x,: ',.-W.
^. / yt,, d.* ;' '.
..M'
.i Wh$1'.2.7.1J Remo i
MO#IW.t'ectivelo'~eriEg'?.3 Wipe each tube clean with lint-free cloths and ethyl v
I @$.N.M.'! alcohol'0 Place!th's tubes on a covered floor area adi' cent to the container.
l dh6hiSiYEe.'
...l.4";$s. '
N W 1.2.7.2. Inspect each drive tube for damage and cleanliness.
..%,.pspp.w.: r:,
4l.y.p,?;.v.. 1.2. 7. 3 Ob. s.. =.rc3 w, s.. +.;.y.
..y.
.: w.
serve that each drive tube to shuttle tube coupling and particularly MM.?.,W;;:,the; coupling threads are clean and undamaged.
. ',.,9 -
.e:. C, q....,:p
~-
f@...,.. m h..1.2. 7. C Return the drive tubes to the container so thag all the shuttle tube
.. '.. ',,,.'.. "couplings are against the same container end plate.
- w. m,.
l
.e..
7
. 1.2.7.5, Repack the drive tubes tightly in the container and install the con.
I tainer lid.
l 1
I l'.2 7.6 Transport all SRM and IRM drive mechanisms into the CRD room below l
the reactor and place them on a clean covered floor area.
'.. " 1.2. 7. 7 Position the drive tube filled container adjacent to 'the.CRD conveyer cradle chute opening immediately outside the drywell containment wall.
Orient
' ' c, the container so'the drive tube coupling to the shuttle tube is toward the con-
~
tainment wall....-
NOTE At some plants the drive tubes can be transported directly into i
J. :-'
the CRD area below the vessel.
If this is the case, proceed to
, '. ? '.
Step 1.2.7'.12.
5
.,;.. 3.;..
G.'
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LIM ERICK INTERN ALS INSTALLAT10H g mM C.y h, yC.,
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PROJECT NO.
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I SUBCONTRACT NC. CO31 F3C 202
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1-19 m nw.n
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'. 7.8.Pos i tio'f;g.WZi:&a.y%.a;....?. W.a "fft;.'
9
.Wy l_
5 43
~, ~..,
w i.,
n he.CR0 cradle in the full OUT position and. cover.it with
'9:N lb' 1'dstl'csheetin'dg ~WPP^-_
i W F.:
l5 y
M.. q-j yr p..c.x r s..
7 9 t R..-emove.ithe...conta1'ner lid and carefully remove the drive tubes from jg
.~~9 a
eTds'. t'owaFds thi co,'ntainmint.tKeMon'tii~n'eFaRd place the~ tubes ori the CRD crad lA l g,, -g #
Cover the tubes with clean plastic sheeting
~y.z y indiecurd the.: d D.h...
p,e... s.w.;s,....i..r.iV.e' tubes to the cradle wi th the cradle tie-down straps.
'1
..u;
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...y. n -
M.".2.7.'.10 -l0b'sdrVe 'thTt' the cradle access into the CRD room is clear and dry-p e1
$4dM.
l
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..a
- .:'m m
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l.jiky;. jl 2.7.11 Station' three men in the CRD room to receive and install the drive l. g ;;.;,W..b tubes.t'o:shuttleitube'. couplings are nearly against the far reactor pedestal wall.
.Then. slowly. move the cradle into the CRD room until the drive tube l
5
.p; e..
1 a.ff.QQ'1.# '..2.7.12 ~t h. Y.L. D -l:
i > m:.pMy I'?c(Referencet1.11)Yand verify that the location of each SRM and RM dry tube
. Consult thetlatest revision of the core plot plan assembly drawing l
l Ahf.".-
..gh,'if.:.fy! tion ~ coordinates.T. All; SRM and IRM vessel housings should have an attachednose l
'.. Mt.T&i
' - 'b' y ;r..ousing to' drive' mechanism adapter.
n :p z.;- -
s.
';Y:c
,. - q... :
NOTE
'.,.;, ' u
.To avoid interferences with installed drive tubes and drive tube
, ' M. '.'J:6 mechanisms, install the drive tubes and drive mechanisms one at
.L../..,fchhh.
,c away from the CRD cradle chute opening and work progressively
.,.....'... '..,-towards the CR0 cradle chute opening..
g..
~
li -
CAUTION
....s.-
Beforc removing any SRM/IRM nose guide, prepare to support the
~
locse internal shuttle tube.
a 1.2.7.13 Unt.
.he CRD cradle tie-down straps and uncover the drive tubes.
1.2.7.14' Unscrew and carefully lower one SRM/IRM nose guide.
The internal i ylM, 2
l.
Wsh'ut'tle tube 'shoul.d' follow the guide.
Using clean gloves, grasp the shuttle
';.@.u.+f.d;/' store the; nose";uide.Vtube just above the shuttle tube to drive the coupling, then remove and r.e.
' f:Q.Q,.N.ti.2.7.15.R'T.
':%g 'Qf.
.L*n h f ? M 2 *
~
Confinn'that the shuttle tube and coupling are clean.
Then install
.%;,; > s:*$r..W.y,m.e,d properly..s.eit7 t,he"provided 0-ring.
n'.
r..:.w m. ; - u.
See Reference 1.1.
~
. j.y :....
.ip.Yn^P1.2.7.16', Lift.onedrivetubeofftheCRDcradleandpositionitvertice11y h*,T*@id.% v ;o..t.'...
MUlider' the'shuttlitubs so the shuttle and drive tube couplings align with -
..;;D..'.~a /$5fch other?.. Firmly'h'and tighten tne couplings.
.,b.T7[f.Q-^,j.'k.x.*#7."g,.4hp$j.'.
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I LIM EHICK INTL'.RN ALS INETALLATIO,N v
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GC2.M'5.,G.;W PROJECT NO.
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SUBCONTRACT NO. 8031 FSO.RO2,-
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LE.K.flyij T.21:7.17.. Insert the shuttle tube / drive tube assembly into the dry tube until
.. +..
b'#R?fino'nly a' few. inches'of. unthreaded drive tube extends below the drive mechanism
- &t.?." ^
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- $*.$O'".5kU$l adapter.* ?? 'UW' d.1 s.
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Wi.%.g. d11'12.,7.18.',Prov.ide'. support for the drive tube / shuttle tube assembly B..
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.. r.1.2!7.191 Removelth'e' gear box' from the assigned drive mechanism.
k
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. m x.
.U. enc..V;P'h'51.2'.7'.20 ;Positio'n the', appropriate detector drive mechanism vertically
..k r'e^ctly undeW the 'open tube assembly.
Orient the drive cable connector T.ik$;Mt,opard the.hactopjessel pedestal opening for the flexible drive shaft.
~
- wa,; :.%;G y w;w. p. u' ; '.
.'.jiS;f.1;2'.7.21' Lower.Ethe' drive tube assembly into and through the drive mechanism
.until a.fewiinches'of. unthreaded tube extends below the drive mechanism, Te% WN3
- s. gw., N..v.;.) y<
.e.. g..g, r
? sg.9..s.b;...
.. a
- l. 2:7.22. Support.the tube assembly; then lift, align and using the four cap e
r J'". c.* screws.and washers provided, attach the mechanism securely to the vessel
.v';t.h. @l?:6.hous ing. ada
>:'y,::Q.yl5%B*..r.@pter.6 Torque the cap screws to about 25 foot-pounds.
%.s -
? k.qdd.1.2p 23.c Apply the provided gear lubricant and making certain that the gear E-WlWQ;fls teeth.matet propbr.ly ~w'ith'the drive tube holes, position and attach the M'
nfechiniFgear 6dx.to the mechanism.
One inch of drive tube holes chould be 1
W. F., mechanism..-
.:;.',: ::.;n.d. < b'el. d. th.e". : g e.,a r -lls.. Abo. iJt 31/2 inches of wive tube will extend below
..~ :e :
. : ~,. :.
.u ;@:,:m..-
., p.
. %s ;,n:,.. n:.C::.c.. '. -
.: r.
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CAUTION
..n
~.
._w-
- .e.;
w..
a..
.v. ;;g,w;a...w t' Do not rotate the driie tube after engaging the dfiva sprocket.
,;g.c
- - Q.-
- .C;. 4 Such: movement could damage or break the sprocket guide bearing,
.a s t. h ~ ?:. W ; y
~.
.:t
'd. -d :.1.2;7.24 Before remWing the tube support, confirm that the gear box mechanism f,6 Y. '.s fsupports'the drive. tube assembly and prevents movement.
. ut :.ru..... - -
,m*l V.
- ...e m
.,l 4..y, *. ;l. 2. 7. 2 5 Repeat-Steps 1.2.7.14 through 1.2.7.24 until all SM and. IM drive tuhes S 'n 9. f h
..s-s, :.._j.Wa~nd. drive mechanisms are installed..
l
'lJ' W;a. m...
- y.
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. ; 2. -
1.2.7.26 Pressure test each SM and IM drive tube / shuttle tube assembly as
- 7 W'.. 4..c< fol l ows '.S,u.
) :.
.. %..... w. ~.. L 1
.c t
. $.f...J.:1.2'.7.26.1.'. Attachl'a'15 psig dry nitrogen pressure source and a 0-15 psig
.4.%%7 pressure gauge. to., th-lower open end of the selected drive tube, v
- u. m.
....... w.-
. Slowly increase the tube pressure to 5 psig; then, close the pres-
.~.'. 1 ~. 2. 7. 2 6. 2 -
is s ';.D, e!.%+... s u r, e. s u p p l y v, a l v e.. '
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LIM ERICK INTERNALS INSTALLATION
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NW2WCOFT*W.D File No OM --
?h%*Yh%ie635?ry(:@h,4:.. -
!.7 N N M NNERIA Ibs0TRIC 22u211
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1-21 ph, v, ~;;;,:~2.cpW 5%
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. W V+ s er; 1.2;7.26.3M. Monitor.-the ~ pressure gauge for.15 minutes; no pressure loss should m$
> 7b7a..cep'ted'/7/If;1eakage.is detected, remove the drive mechanism gear box, 81.'Mm
'lliise:;.thi t'ub'e. assembly,"and check the drive tube to shuttle tube coupling A
' j.1.1 en kse^*9 *':.*?.1.
i
%j&s&
- c.f,e u,y?:t,.m".i
.v Yt!'
eT
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..n yNe+h.217:26.4 b Tightensthe coupling, if ne'cessary.
If this procedure fails to fA Q. PlZsjop~ thelleakage',< disconnect the coupling end check for a damaged or incor-
}
W@:s..].$rectly positioned' 0-ring.
~
37..l
%:.' : a.s.: 4f.i :
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'2'7 2625;7Di'connettithe pressure testing equipment
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s N$.h@:m.!QQ.W.':s'.,y:;%gf,Y ". '
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~ wriA;r:Tw.2.8:"SRM and IRM Detector Assemb1v Installation 1/M 4%:
.-A
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n CAUTION
.'a:Q h,? y @A.x;.. d. :?,... f.-
'. rg:;.2.'W 7.,.
l
.. u.
- ;..m e
%.$@#.an;e/., '.- All/ SRMFIRM',and PRM detector. tubes contain small amounts of iW w /.t:3ra' dica'ctivs This' material and its radioactivity
%':@rh@d.F,.% is' Wehnetic'luranium 235.
ally' sealed inside the detector tube and unless the
.s YS In tuWis'al?isEdamaced or the tube is exposed to neutron radia-l
.:tt f % f-U M M i Wat'erial does not pose a personnel exposure or con-l l "*~ % W.U.t en,':thi W.'-
tamination Vroblem.
However, before handling a defective or l
l
. Md. 'J4. irradiated detector,' request that radiation monitoring per-l
- t s ';. g y,g.}.y;{j@P.7 sonnel survey.the detector vor radiation and radioactive iP contaminatio6,q.,
H.4 9:QiM,'?
- l Q.*
N OT,.
.::.-;.r..,.
?
m e' ifl,'f ;&:.....
?
4-C.-
The detector is a delicate instrument.
Use care hnd always l
- p".g;27,L..
- . 6
. ear clean gloves when handling and installing the detector w
assemblies to prevent damage and contamination.
All d'etector s'
L. L _ :,.;.
assembly bend. diameters must be greater than 5.5 feet.
,:..-..- <..?
g,',-,s_""
dssemble the SRM and IRM detector assembly shipping containers in a
. 1.2.8.1
' clean, dry lay-down area.
Remove the container covering and packing mate-
.. rials and inspect each assembly, including all associated parts for damage,
, j, cleanliness and possible part shortages.
All assembly parts, such a: drive
.+
tube retainers, cable connectors, etc. must be accounted for per the sup-plied parts list..- If necessary, clean each detector assembly and part.
Do not use any solvents to clean the detector assembly.
Use clean lint-free cloths and clean dry compressed air or nitrogen.
' ~
1.2. 8. 2 Using the procedure outlined in Step 1.2.3.18, check and-record the insulation resistance of each SRM and IRM detector assembly.
L.
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LIM CRICK INTER N ALE lHSTALL.t. TION
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SUBCONTRACT NO. 8031*FSca202
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' 22M 211 4:
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NOTE sun
~.n.y..
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- .
- t,.:. y, W.i Because. connector shells are not installed on the assemblies,
..@W "y' 'n
. -.....,. +. e...
(
'E' t,;. care'not' to ' damage the ceramic to metal seal at the connector pin (4h4 d'ndjf,theide Reseal the cable ends, r; after:testin,g,tector cable during testing.
3 e
.@A-WM.W Wn~-:G-
%@@eh.m:1El8.'3' If"the CRD%om accessibility permi
- ?['sisimblieli
- ,inf th,e?. clean shipping container, install the container lid and Otherwise, each detector assembly 35Veg?.Ttransport1the container to the CRD room.-?.l.M.T'?must be"un'coiled
~
The latter procedure is tedious and requires
@M M#" drive tube 'one' at: a' time.f y. : careful planning;gnd additional
.,R
~.. ;Y -
q.y 1.2.8.4 Identify the' drive tube and drive mechanism furthest from the detec-C e.. Jt'or. entry'or container as being an SRM or IRM tube.
Refer to the latest
@dj..:w... identi ty..F.Y ' core plot plan assembly diagram, Reference 1.11, to verify the tLbe g q. ;,,
- 4. n yw. g.c,g -l.1.2.8.5 If the drive tubes or shuttle tubes have been installed for consi-
- q'.4 4.f.
ig p g-a derable time (over three months) or if moisture condensation inside the tubes is' suspected; use clean plastic tubing and purge inside tubes with
.;,;9..... dry nitrogen.
. n.a.
- m..
Remove the lock nut from one of the provided detector retainer i M.. " 1.2.8.6 n.'
Jassemblies.
See Reference 1.4 c.;..'....
r.
1.2.8'.7 Apoly tM approved lubricant to the drive tube ' threads and while
~'
E
- %....." firmly holding the drive tube, install and tighten t.he retainer lock nut i
l1
'on the drive tube.
~
=
1." ;.. -:
,1.2.8.8 Select thb proper type detector assembly, either an SRM or an IRM detector..to install in the identified tube.
An etched metal ring on the
./
detector assembly gives this information.
The detectors are not identical
)
' to each' other','do not interchance them.
Record the detector siirial nueber
. c ;., '.- .,' land, the; tube's. core location.
g,.
ye
. 5 *.1.2'.8.9 Using clein gloves and observing detector bend radii limits (2.25 P. ', feet) carefully lift the selected detector assembly to the vertical posi-
'":n tien directly,. unde' the identified drive tube.
r
- J;..?
- QQ:: :
../
. %y.Tl1.2.8.10.jWith' the' detector assembly fiber-glass covering intac
.f. f.
^
'.,q#.1. '/
,a
- c.c...v.s.Eid, _ tor. and cabling.. ', few inches at a time into the ide
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LIMERICK INTERNALS INSTALLATION,
i
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PROJECT NO. L M l'O 2 y4,g:d.c,CE'G4, y,e;.
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SUBCONTRACT NO.0031fSC203 /
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) ELs CTRIC 22n211 w% agh.?y.:wl w.* v.s+. u +(,,.u.
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1 M>f" t /? A. T
-W/CM7.If. there are,any projections inside the drive tube or shuttle b@. MMf& tube',)]the' defector. assembly fiber-glass sleeve has a tendency Wr?. g,vnm;.,f tot han8s'.w.GVg.u.,; 'yp:*.1.
up.7.This must be avoided.
5%
- Tfl.2:8.11/<When the detector assembly nylon sleeve boss just enters the detec-
.QT,-M.'fGr'~retaine'61ockinut.. the detector will be properly positioned inside the
- c. $ d.e b shuttle'.. tube;..See Reference 1.4.
y :p %
M 1.2;8.12 c. Insta11.~th '.
t.
.a.
nJk;*. x..n..
w.w w.:.... n
.... e remaining detector assembly retainer parts as followst' M.W g lSee Reference 1.14..
I W :,.9 %'.~i ? M [..
- N;' Q '. > ':.%
$Q;S'F-i?.1' bpicant.^ ~.See Reference 1.5. 'd$;1;2.'8.12.1Lubricite the re
."?;,X u
1
.v.:., m.
4..".b@D.,%&. ;
a.%. m
- t. v.-
.s,a. +..w...:
9F
. n 1.2.8il2.2'.' 511de.the'grorxet, :he conical washer and the retainer gland over I
.'the'end'of th'e det~ector assembly and position them over the detector assembly L
S. t&riylon bis'sNThe'Vetainer gla'nd must mate with the lock nut on the drive tube.
W. y.
.mi. '.n : QD.W;..
~
'9,N d l'.2i8'.12.'3? WithdraE*the detertor assembly from the drive tube 1/2 inch or far M
l
,'".',$'W:.enough..to.. install.C the split insulating spacer between the boss and the end
..ww.A of..the:deteh. tor'. assembly fiber-glass sleeve.
n
.%... 1.r.r.e..c : v. ~.,..
.m.. e... sr-v
- '.Q.
a.. n
!.'pf';../.1.2.'8'.12.4% Again. insert the detector.assevbly fully into the I
.J.47.ightenithe deticitor, retainer gland to the lock nut compressing the grom-l
,n.d.44 met to(gr.ipithe detector assembly boss.
- w.",.'.-:9.p m_..
- ..a..,. 4..
t
.cyD...J.:1. 2.8.12.51.Slida the retainer nut lock screw over the detector assembly and
,;.. tighten ~the lockf's' crew into the retainer gland.
^
\\
c'.9.<.o *),l'.2.8.12.6. Using an ohmmeter, measure the resistance between the detector
{
l_-
7 F.X. assembly ~ metallic' sheath and the drive tube. This resistance must exceed e
,,4.
10.5_ ohms.v.If the resistance is less than this value, check the retainer
.:.. asserrbly. insulators or the detheter assembly fiber-glass covering for 1r-li,'.':'S Q: regularities; ~ The resistance between the detector assembly center conduc-
.i W tor ~and the' sheath must' exceed 10H ohms.
f; &.,..
n.
d. T.
. k l[ Y,
2.8.12.7,c RemoVef.
s.W.ve-;..,conriect the p"ress,t,he pipe plug on the side of the drive tube lock nut and ure test equipment and a 15 psig dry nitrogen pressure 9
4::W.lource to'the dri'e tube.
%.P,Mtly,s';,
v
~
y.
jg$'$.,1,.2.8.12.'8 : Slow 1.y.' pressurize the detector drive tube assembly to 15 psig and q, p.f.c, monitor. the assemb.ly for leaks.
Then close the supply valve and observe f.@: r.W.:,',% the. pressure' gauge.
Tha 15 psig pressure should remain constant for at bl:least 5Lminutes..)If leakage is detected, reduce the assembly pressure and p...t@sw..makerepairs.
./ '
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Lf M ERICK INTERN ALS INSTALLAT? ODE I
$tM./:', h.;.4AS. s e
PROJECT NO.
L M I.8 2
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$UBCONTR ACT NO. 8031 FSC 202 m.
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W 7 g # G..E.N,g.E.r RAO tELeCTRIC 22x 211 p
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' W SHEET NO.
,i
- &@f90.?%'?'f' E
Wh
' ^ :.
D...,. %.u w % S.%..
~, '.
7 r
.12.9Y Aften successfu11y testing. the assembly, remove the test equip ~
ment *a'ndyiirist'dl,$th'e; pipe plug us ing' the approved thread lubricant.
'. et
.ReYird[th'iletectoriserial. number, adjacent to the SRM/IRM scrial number
', ~
M /A andiits'coreliosition on the data sheet.
. Aw9 r W.A s
. n.s Yi2Y851'n m :m,:3s YsTa10M.' tis't1the remaining SRM and IRM detector assemblie if _
5 2:8144.Wpll111. the:iNlKkl'.'
L..
%'2 Insta SRM and.'IRM detector assembly cable connectors.
See
[.,
e C5iinectorJA'sle'mblyilnstructions, GEK-45754.
Again, measure and record
~~
- the]vdesetdr'aiseinbly resistances._.]The' resistances should not have changed.
b if
,u
?3 W i M D :. ? X s E...
M.'di&{f.142.8.159If: the detector assemblies are not connceted immediately to t QOfTelt'eiisi6n[ ablesiiseal the connectors in plastic and protect them from kj.'
'.f, Pp;Mf,damige".I@, c
.... re$.n.*."
Eg.
0.v y,,r,w.m..
Y - [R:~1'.2';8'.16h Ins' tall.a'nd test the wiring and cable between the S d;D" f
det' notiissimblie's,' the motor modules and the containment penetrations e
per.'Referincis51?701.8 and 1.9. -
L
-a?.mBGi&WW
(.
giVjdk N Q;$ Wq'll(l."
w
!?@',
NOTE Ql
?.Mc'A T' E
jNMTo avoid'i,nterference' witn the CR0 room service platform, the h.i' :ggi4%p.dit'edthn 'est'ession"cables should pass through the reactor yg,h, -f,dp9.ria " t :pedest,al pelnetyations located above the platform, M'd Sc.t'. W c..
u,@S.kl.2'.811740bserve that the ca ble guard supplied with the detector assemblies
. (!I,@fR.first,; over thei detector extension cable, see R'eference 1.4...E.U.fisf.i l
~ Ww
.. O A.m f
). :.. > - }.n T'1:~Wf.278118# Insta11' thV cable and wiring connections per' Connector Assembly ZufInstructions',GEX-45754 Recheck the cable insulation resistances after
~
.:. 4.,39;!the connectors arelinstalled.
Slide the
- c. :n.e::,; ;n.
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l,.;Y. g' ^y(1.2. 8.19 Connect the extension cable to each detector assembly.
- l.,-
ug,;g's...icable guard over the connection and screw the guard tightly onto the detec-p.'. tor. retainer n.ut threrds.
Then tighten the cable guard cord grip.
This ky.lq,6,;mustinsulateandwaterprooftheconnector.
d.n.y
,A
- ;$ ' ' ~
1.2.8. 20. ' I ns tall".the remaining cable and wire connectors per Reference 1.9.-
i nInstall the supplied waterproofing kits on all exposed connectors.
' v..
1.2.8.21, With'.the equipment deenergized ' install, test and connect the cables
-l and.' wiring between the containment penetrations, the preamplifiers and the v1 contre 1' room SRM and IRM equipment per References 1.7.1.8 and 1.9.
i
- ?..' * - lSRM detectors are connected to p'ulse preamp 11fiers, IRM detectors are con-
~
All cables and wiring must be correctly
%:.'.;,6,.3'.nected to voltage preamplifiers.
. identified.
To avoid adverse signal feedback the presmplifier input and Q.. vi,.M'J. output cables snould be routed separately and ret in comon enclosures and
~
S.
C.!h-h:,l.
l
. cable trays.
1 M*.;Oj$.[?: 3 L!MCRICK INTERNALS INSTALLATION
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SUBCONTRACT NO. 8031 F30 202. - ;
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.D.S.*Q;F'1.'2'.9 p SRM"a' rid'IRM Flexible Drive Shaft Installation N?%.$1Q:..~.'..5C>V'T'
'^
g/Wm12191S Connect the assigned flexible' drive shaft to each SRM and IRM drive l Ye.GQd'.
9me'chanism' gear (bo'x.,;,To avoid interferences and incorrect connections, start a
M-W;.p!'with the:
hd3.4AW6dule'sMUsing;.ainia. closest to the pedestal penetrations to the drive motor SRM or IRM rked tag or taped label, identify both ends of the cable FN.N T.%.@a'nd'.insta11'each"cableoneatatime, f
- .n n.... n.4 't.
"p g. = 4.. *1.2 9.2 ' Route the shaft as straight as possible through the pedestal pene-
. s f..+h.@3
,.tration' most nearly in-line with the assigned drive module location outside
!.tJ
- .'9'...g.: the: pedestal. wall.cc Use care not to bend the shaft at tighter than an 18-
~
..,..'v,., f. flinch diameter o.r eice.ed a total of 540 degrees of bending per shaft.
3.. y..
.s.y.. -
- 3. "'. Eld.9.3 l Support and clamp the drive shaft hssembly at least every 4 feet
.',;throughout the entire shaft length, including the shaft grooming loops.
- P.
&.Do not secure the.. clamps too tightly and crush the shaft housing.
f.. %
- C { y~:,'. ~
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h.
.1.2.'.9.4. Before conriecting the drive shaft to its assigned drive motor module
.fg'.,;s',4 per Referance 1.1.1 ',.
obtain administrative approvals to energi:e and check
.A..'
/
the motor r.edule' operations as follows:
.T:
,.c.
1.2.9.4.1 Observe.that the control room located SRM and IRM detector drive
_T..
units, the drive control circuits and all field wiring are installed pro-
. 6;.'
perly and are openable.
See References 1.7 th rough 1.11.
. s.; ~
.':T '
,.1.2.9.4.2 Establish communication between the drywell motor module ar ea,
- -. " ^
5 tha CRD room, and the control room.
~
5
.;1.2.9.4.3 Select a' channel to tes:, apply power to the circuits., and con-firm that the equipmer.t is operating properly.
'1'.2'.9.4.4 Actuate detector INSERT.
If not already at the insertion limit, the motor module shaft should rotate smoothly clockwise (facing shaft) until the LS-4 limit switch inside the module opens the circuit.
If this opera-
) ion is unsatisfactory, correct it per References 1.2,1.9 and 1.10.
,t
..,f
'11.2.9.4.5 Attach a revolution counter to the motor module output shaft and
. s.T'iset the counter to zero.
l'.2. 9. 4. 6 Actuate detector WITHDRAW.
The motor module shaft should ru'n smoothly countercicekwise until limit switch LS-1 stops the drive motor.
~
.This should occur' aftar 'about 640 shaf t revolutions, depending on the i d "reactor *,essel size and the equipment used, see Reference 1.5.
If the drive motor fails. to stop at the correct value, reset the LS-1 switch j
' G inside the drive module.
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The LS-4 switch should open when the
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3 revolutions.
~ ~ - - -
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' M w M 1:2'.9.4.80 Repeat:5teps 1.2.9.4.6 through 1.2.9.4.7 several times until the opera-4:kfl.d :
t t W::'tiin'is s'itisfactory.t Then leave the; controls in the fully inserted cond'i-
~ ~ ~ ~
e M %:4l tion'and' record the results.
'Elhl55.4f,klk '1.4 vj?m*:;;
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$*~i;fr'"# W~"motor' modules !.$i.
a.. Repeat Steps 1.2.9.4.3 through 1.2.9.4.8 to check all the SRM and I.RM -
)
?hh?.f?h4%. i..:' 5.
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~
~
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wE.'.M.:.91'.2.9.5. Attach the flexible drive shafts to the assigned motor module output shaft,'see. Reference 1.11.
Tighten the U-bolt and adjustment bracket to
'M,lJF.G.falign eachshaf tiroperly.
Any excessive drive snaft lengths must be looped MM...;p' ga'nd phoperly.. supported at least every four feet.
9.; M.,n,h.,.v.u.a..
Observe the bend radii
- y ilimits.Qs.
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- "N$$ &[4. h CAUTION w, a."v-y.
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_. r. Before
.n.r a. ing a'ny detector drive mechanisms, verify that the n.
\\
.e operat DSDM C. CRD:' service ~p'latformiin the CRD room is positioned properly so i
,W'@,'./Ml ? he detector., Eables and drive tubes, when retracted, will clear t
.< r..rf. :.'@.,. _%.:..~ th.e.' platfor.m a The platform should be locked in this position.
.p w
- u. p..a,....
l.. Av'.. 21.2.9'.6" While' observing the selected. detector drive mechanism and flexible W'-
7%.7.h l
%.q':.M'. dr.ive shaf t. actuate the detector WITHDRAW.
The detector drive should i
Qithdravi' smoothly; about 120 inches and stop.
Adjusttpedrivemechanism
-""43c; bearing-load adjustment screw, at the bottom of the mechanism, to prevent 9.t
!y.
fa,1ve. tube'.chatteEorbinding.ils to"stoplitf(ih the specified' distance, deenergi:e the d dr
'See Reference 1.4.
If the inechanism 5.N.p
~...:..,;..S.Wreset the LS-1 s.w~.i tc,h to open properly.
x.c %
.. s...m,...
r
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. 4
.s
..s,.
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e;.p;.6,'.. 91.2. 9. 7 'Insertithe ' detector. Again the detector should move smoothly and t..
.? 'stop when the lock nut is 3 ::1/2 inches below the drive mechanism.
Adjust f f Ll% the LS-4 switch.to' achieve this.
.,..'. :... m..
3
.r
...r.
d d'., Q.. 1 1'. 2'. 9. 8 Repeat Ste'ps: 1.2.9.6 and 1.2.9.7 until the drive operation is satis-1 Q. %;;@or. binding,.especially at shaft loops,factoryF' Duringitihis *.est cbserve and correct
- t.'.7.G.. '..:fA;.O.ON q.
~
d;',y:o.@f..9,il.2.9.'9. Repeat Steps 1.2'.9.'6 through 1.2.9.8 until all SRM a
. b
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~
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.'..A. ;w,n.7 drives opeVate'prope'rly.
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-NOTE
.i. ~..,. s :
M.,G,.,.,.wt.
i
,s... * *..*
.f.
es A
.it @.i..
When the SRM and IRM detector drive tests are completed, leave
- Q.< FtrsCJ. the ' drives. fully inserted and deenergize t.hvWui+s.
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,'h, RNA18 INCTALLATION k$.((5
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l'.2.'107 PRM Cable,'Insta11ation
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.T yt.1:2;10'.17: Insta11cand test the PRM extension cables from the' PRM assemblies I Ys,4%Kth:the containmeni penetrations.
See References 1.2,1.8 and 1(14.
-Alli cables"must. remain above the CRD service platfonn.
d,,-.WM~n %m. '.,s W$,.:
- v..~. ~. p. L ~.. ~. ~
v-N ll2110.2' Provide' easily removable cable supports and protection under the
- 3%Yvessel'tB' avoid ~c~able interferences with the CR0 units, SRM and IRM drive NMMWehanisinsD,the. TIP];:t'ubing installation and'the CRD service platform.
h* 2;:.3.?. :'q 9.h:..*::..
cX-it.)$^M.K2.10.3.. Install"and. test the PRM extension cables between the conta
'ft ' ' Nlf l.
~
7 1.8 M.
.* pe[netrationr ahd.y.th,e"contr'o1 room PRM equipment per References 1.,
n..A.. vand 1.14s........ #..e.,.
m,p.-.e.. s.
- u.. r.w:.;.c.,<
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, c..
. r.,. ~, ~:.
See g.l
- ,:F, 751.2.10.4 Install,'J., test and connect all PRM extension cable connectors.
- 6. F e1 Conn'ector. Asseinbly Instructions, GEX-45754.
y W q;& " 7 W 51.@g.t. '
wQEl' '10.5;.InspectitheTdrip skirt, sleeve and PRM calibration tube to traver-
[gs%,0.Referen}ce 1.13 'and.!' action 2 Step 2.2.7.3.6.si'rigi.in co're phib~el u See
.i wN If necessary, clean each Jd
- .? !W TJfem'id LP.-C.V. M G:
S 4;4. @W:?.w..,,.
% N"a..' -(g.5.;...
y/ $...c. c ;
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NOTE g s ;'
T'O H H 915.*1M.WWF.Do' not'use"solvents including Water to clean inside the g M.9'I
.M/.~ ' tube adap' tem Purge the adap~ter with clean, dry nitrogen.
- w. i.ww w. c.
. v'.r;...>.3. <:. ~
%. 5..,"R }; n1'.2.10.6 Starting. -...;at the PRM detector tube nearest the *PRM extens 2..
h.
' W.Whreactor'/ vessel pedestal penetrations, install the guide tube adapter, drip y.M._ ::t '. skirt and sleeve 'as follows:
-:;.. c:,.::...
Remove 'the PRM detector tube nose guide and inspect the tube and 3.S../.1.2.10.6.1 If necessary, using dry nitregen, purge inside l
.. + connectors for moisture.
'c the tube and aro,'und the connectors.
.: :1.. ;. n.:e;
, J,
- ' ;';".1.s.2.10.6.2 - Hold ths. PRM calibration tube firmly; then securely attach the s,
Cap the open and of the adapter.
),
- f....e TIP guide tube adapter to the tube.
.,m.
v.
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u
.,1.2.10.6.3 Slide the drip skirt over the end of the PRM tube assembly and
".9 Vposition.the. skirt flat against the shoulder of the tube nut, see Refer-
f i l
'~
...... '.ence 1.2.13.
1 3.10.6.4 Remov'e the cover from one of the sleeve assemblies and inspect
.,the, sleeve threads for damage and cleanliness.
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LIM ERICK INTERN ALS INETALLATION 1
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<'fL 'Qgli 2.10'.6.S.. Apply'ipproved lubricant to the PRM tube nut external threads.
y.@gj~g,fciFe'fu11y.: slide the sleeve over the PRM connectors
- r....w
~
'.hThen screw the sleeve securely on the PRM assembly nut
' tub d t M,..,.r.h.. 5gh..aj{e a ap ers.
,u p.,,agajnstthe".dripskirt.
M. if.
1'. 2.10. 6. 6 '- Repeat 1 Steps 1.2.10.6.1 through 1.2.10.6.S until i guide tube adapter, M@y. 3,e t7. j-M.Tdrip skirtTand sleeve are installed on each PRM detector tube.
. N.n ? -l
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... ~
d #q:,s,F.%Tx1?.2'.10.7.. Remove'the ' plastic covering from the PRM detector tube connectors.
- d%!Yf$ce;iThe, connectors must be clean and dry.; parent or'.if the,PRM detector tube If connector contamination is ap-i (.
'*y?:,.,7'.0< resistances,seeStep1.2.3.18.MM;, period of time (th
,.,.o-.,,,
' 1.2.10.8 ' Using the provided silicone lubricant, install the provided water-f.'.. )'.'
."*.y proofing kits on all connectors.
See Reference 1.15.
When properly twaterproofed, the connectors will be insulated from each other, the TIP J:/."-.;$.-:.6' calibration tube' adaptar and the PRM sleeve.
&d
.~ LC.XG*TQ-l.
152110.9 Properly identify then connect the assigned extension cable to
?!@ :f:fiesch PRM detectof.. per Reference 1.14.,
14U'.,'.fi
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~
.,... u. ; -
norg
?..
,e
.?
If the traversing in-core probe guide tubing is not installed irrediately per Section 2 Step 2.2.7.3.6, install the PRM sleeve
.s-covers. See Reference 1.15.
1,. 2'.'11 Confirm that. all SRM, IRM and P'RM equipment is deenergized and pro-
,. ~
.tected in accordance with the In-Plant Storage See: ion of Reference 1.16.
.l.2.12 Submit all. requested and pertinent recorded data for administrative review and filing such as SRM, IRM and PRM detector insulation resistances before and after installation, SRM, IRM and PRM detector and tube serial
_...,..;_. '. numbers and the core loration of each.
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"hMS$ 2'.2.2.7..'dn Ch'a'mbEd'. Shield
'2-4 WyF.2;2.3?.' gGuide. Tube. Valve Assembly 2-5
.@'r'qQ.-2.2'.4'.'; '.N.MIndexirig/ Connectors
%f;NIN2:2!5F 1
- Mechanism 2-6.
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.Mul ti3Wa 2-6 4 Mid$2'.2'.6;'J.. s.r2 Guide'.; Tube' Fabrieation -
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WW2~.217;1" ?d,' Indexing: Mechanism to Contiainment Penetration Flange 2-11
.0;F.Th?>:212:7;2 3 Guide; Tube Valve Assembly to Containment Penetration 2-11
' h.$ h M.i2'.'2i7;3 T.IndexihP Mech'anism to PRM In-Core Assembly 7
2-12
%";e.Pj'yn2.2:7'.4,.nDrive* Mechanism to Guide Tube Valve Assembly 2-13 i
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N@Yp::P 2.2'.10. -
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~Guidi Tiibing'and Component Clearance Testing 2-14
' Guide Tubing Purge System.
2-15
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PROJECT NO. LMl'B2 A
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.o monitorin.T..r.av..e.r.s.i.ng'In-Core Probe (TIP) System consists of several neutt'en
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g.. instrumentation. hannels similar to the channels described in
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.d detector' tubes,ithe TIP system uses totally different detector handling
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r.~w.o.: ha,,.rdwar.(d,,.s:..; ~.. e..d,u.i r.e,s',special ins tallation instructions.
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The TIP! system iio'rmally consists of the following major pieces of equipment:
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Instrument Rack containing:
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5 - Drive Control Units
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" ?'.5 3 - Valve Control Monitors
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1 - Flux Probe Monitor
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1 - X - Y Recorder l
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Traversing Neutron Detectors l
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Multi-way Connectcrs 1
Junction Box 1
Dumy Detector
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Purge Valve Assembly 4
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~"' 2.1. 2 : The followin'g reference documents contain information concerning the
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. installation of the Traversing In-Core Probt Neutron Monitoring equipment.
- .. The plant unique data sheets which supplement this instruction list the c
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LIMERICK INTCRN ALS INSTALLATION 5
S PRO. LECT N O.
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Reference Documents
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. l nG.$fMMixlM Reference Number Descrietion r
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Neutron' Monitoring System IED
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Data e
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Neutron Monitoring System Arrangement
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Neutroi1 lionitoring System Design 9
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Specification and Data Sheets m
.2.5 TIP Calibration System Elementary
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Diagrams 4
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Drive Mechanism
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Indexing Mechanism
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Penetration Fiange 3:,C..Wl '.E ~ :
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Valve, Guide Tube
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Multi-way Connector
'2.10 Chamber Shield
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2.12' icecial Wire and Cable Specificatien
. F 2.13 TIP Purge Equipment
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2.15 Power Range Detector
.- '.c-2.16 Equipment Storage Requiremerts
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ECUIPMENT INSTAL!.ATION
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CAUTION
. These instructions cover cricinal ecuicment installation only.
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Equi; ment removal and instaliation af ter actuai use w111 recuire
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special inst.uctions containing cautions concerning personnel 7
radiation' exposure and the handling of radioactive equipment.
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use of an'y. solvents including water inside the tubing and compo. -
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. nents i s prohibited.
Keep tubing and component openings c")vered
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If necessary,
?{Ti4' &j'h!"' purge.'.t.4if tubin'g with clean dry cr.cpressed air before insta' lim.
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LIMERICK INTERN ALS INSTALLATION 4
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T.W>~f; h2:2.4'.1h Confirm'.that the index mechanism mounting facilities inside the
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'%Kp'iif.aVyc'entainmEnt.have been installed and that they satisfy the con-W6@/9_D.2f7h.
Cid M.tainment and indexing mechanism manufacturer's drawings.
See Refererce l
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- The immeciate area adjacent to the indexing mechanism mounts
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sh'e'uld be~ clear'and remain free of major construction or operational
'TC'C.Effj'ffa2tivities'that'might damage or contaminate the index mechanisms as well
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If mechanism protection is
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.?winacequate.,insta11' splash guards and missile shielding above and around
'f 7;;$the equirmentXThese barriers and the adjacent aopurtenances must not 7
U'l(nectio. interfere with in~ place mechanism cover, guide tubing and electrical con-
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n removal f.or routina equipment servicing.
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. 2.2.4.2 Recove the. indexing mechanism shipping and storage protection and l
(, inspect each index mechanism for damage and cleanliness.
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'. 2.2.4.3,Pesition and align the mounting bolt holes on eacn indexing mechanism
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- to.the succort bracke-holes.
The tt' radial guide :ube holes on each mech-
i.i.,17.anism shculd face the reactor vessel v.destal wall penetration wnere tne
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'T 5 2.2.4.4 Using four 1/2-inch bolts, loosely f asten the index mechanism in
. P 't place.
Cc no: tignten the mounting bolts until the guice and purge u:ing
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are installed.
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- 2.b.5 Record the identification ad location of each, indexing mchanism.
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- 2. 2. 5 Multi-Way Connectors 2.2.5.i Confirm that 'the multi-way connect:r supoorts are pr stalled
.beteen the index mechanism and the reactor pedestal wall m
ie con-3r succorts satisfy containment and the multi-way manuit - -
drawings.
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!aforence 2.1.1.
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.2 Remnve the multi-way connectors shioping and stortge pr:tection and s in
~ ~ i v spect the.mu.l,ti-way connectors for dam.sge and cleanliness.
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2.2.5.3 Detemine frem the drawings which type connector is to be installed,
.. o~way, four-way or both, and where to mount each connector.
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' 2.2.5.4 C:nfirm that the unused ports of the two-way connector are prope ly
. plugged..
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Position each connector so that only the single connector cutlet
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SUDCONTRACT NO. 0031 FSC.TJO2
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TIP GUIDE TU51N3 BENDIN3 PATTE?.N
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7m+.".n..%.-.,,.>,g:,,<;m.y+3 t.ngi cutters or nther tubing internal diameter reducing
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nventionalibench vis'e' to clamp the tubing directly.
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'C" f-f.,3)]O qp-2f 6'.4..2.,.U. Us..e'. t.he.",fo. :llowing procedure' for bending and flaring the guide 1
tubin
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'of the'p'roposed bend.
If an entire 16-foot tubing length can O.f.'."tcN u9:. -
be; handled easily, do not cut the tubing prior to making the
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bend. '1.?ll'
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NOTE c
.* g '.if "7..,).hIf guide tube support is needed, as during cutting, clamp the tubing M
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.$'$.OW?f7 with the'fla' ring tool dic; then fix the die in a vise.
Do not apply y AeQc.,,,37.2.a7,.? vise, pressureidirectly on the guide tubing.
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b.. Ceburr the external and internal tubing surfaces using the y h.,+.
~ file and. 'd.eburting tool.
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l Position the tubing on the appropriate bending pattern, so that at.least 6 inches of tubing extends beyond each end of 26 fWL 4
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the proposed bend.
The center of the bend must be aligned
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with the center of the bend pattern.
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While holcin-the tubing at the beginning end of the bend,
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- carefully,be'a the tabing around the pattern in a smooth arc.
As the cesired bend degree is approached, remove the tubing
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from the pattern and determine the required tubing spring
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back correction.
Use care not to bend the tubing beyond the desired bend degree.
Donothttempttostraightenbenttubing.
This practice will e.
cause kinks and flat spots.
If the bend is not satisfactory, I
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di,scard,,the. tubing.
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After 'nfirming that the bend is correct, cut and deburr the
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Each cut m s* be at least two
.inchec fr.ert. the beg'.nning of a bend and perp%cular to the
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.. tubi,ng centerline.
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- g..Before. installing tube fittings, pass the GE Part Nu-ter N-u/ 7%.W
-22iA6220p a 0.273 inch diameter measuring ball, through the Q ' l'.T,_ ',
tubing bend to confirm that the tubiag internal diameter is l
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adequate.: Do not attempt to force tne ball through the tubing j,.- ML). %,,
or otherwise straighten the restrict 3d area. This will damage
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G/;-h and. kink the~ tubing.
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UM ERICK INTERN ALS INSTAL.,1.ATION
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u, 9.i e 2.2.6.4.3' After bending the tubing, dressing the tubing ends and checkian f
Ch 1 v. internal. tube. clearanca, trial-fit the tubing to confirm that its length, 2.[,'.:.y {@,.f.
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R. bend'and connection alignments are correct.
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2.2.6'.4.4'. Determine from Reference 2.3 the type connectors to install f.y& 6iVand how the connections are to be made up.
- Connector fittings and tubing
.Ne WPU!P$ flares'must'not' restrict internal tubing clearances or otherwise obstruct
.SdMdti4TIP detector assembly movement.
Use only the furnished connectors.
Do
,M...a pi..not use.' compression. or inverted flare type connections.
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f Position the nut and sleeve far enough up from the tube
( y.p.y,(.W,.S J. over. the tubing.' :
?
.E end so as not to' interfere with tube flaring.
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p42.2.6~.4.6;.0bserve thTt the fisring tool and die are in good condition to r
4G 2.3.
p h. W.,g n..fo.rm'st..andard 37.;rd.e' gree flares in accordance with Reference A
. s... t,....
...,6.
.MT f
- mr
.'.;'v*,%
naig '
1
- 7. w
..ah q:::,-
2.?-4 w
-w w V
\\
~
l
?-$'W&htG;&en:V5WW g.,.rh p;;.3 Wh
.used. extensively to flare stainless steel tubing, flaring
%W.Eteolf.'espicia11y the 37-degree tool surface angle, will 5 cdually
- 43fg' 'O.4,Mear:large*4 If a larger angic flare tool is tightened against a i
.F,;.
r 1
..WJ$. g;' ' ' 37.degreidie'..the tubing will. tend to deflect inward reducing and DC.'fi: g@w... obstructi'n'gM.he TIP detector passageway.
This must be avoided.
- th g..
. ;m..w.;.?.
. s..c
... s.
1 7.p.~.""p 2.2.6.4.7 ? 'Insta11. the correct tubing couplings per Ref -!rence 7.y i.e.t 2.3 and check I
the internal tube. clearance through the connection and fitting. This time i' gs.'.n.huse'.the GE Part, Number 225A6220, a C.273 inch diameter, se'rvicing tool red,
- d..[p. 'Q.J Witch wil' We check the connecter joint alignment.6through tight or incorrectly mad l
Do not atte.et to pass
. Q ld f.d.Lt ~
l i q $ ;.g m.he too
..b.o'o W y&i.yN 'ght damage the'.. tubing or become lodged in the bend.
i I
Q.
- &'.?
a cm.f:::s. 2.7. Guide T'.'be' Installation e-
- 2 w<
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- a,
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Before starting to install any guide tubing, consult the Neutron
- f.,... F..
Monitoring System Arrangement Drawing (Reference 2.3) for spe-W c. y 4; cif,ic detaily concerning guide tube installation, especially the recuirements ' covering the maximum allowable total bending degrees
, h w i..,
and the mini. mum a.lowable bend radii for specific guide tube sec-
,,3..,
?.
tiens.
Because of ecceatric equipment location and interferences,
- O - g ;
P.'..
straight ~gilide tube runs, especially inside the drywell, are seldom
{C.%.f y,@lg.#yi{R.j. achievable $.Thus, it is recorrended that the guide tubing in these
" W.,. n w. areas and'especially at and inside the containment penetration be
, J~n.We2;pM.inytalled ppior to installing the straight ouide tube sections.
o
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LIMERICK INTERN ALS INSTM.LA?lON 1
9
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PRMCT No. L M t.8 2
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ELECTRIC 22A4211
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gu
.y -
m.t;s'M. g c..
w.n 2.27'.:1. Indexing.MedanismtoContainmentPenetrationFlange
.$@QV!;. !ph ;c.?MM,q:dr9well penetration guide tube flange removed, U@h6pc3jjgmine the tubinKberid locations, the connection 76 2.2
- 7.'1'.13 Wi th : the :
hiCstraight".ssetioRof./ guide tubing into the assigned penetration and deter-Vp.et-,r6~, sections:,necessary,to connect the flange tube coupling to the single index-
- ., bj. ?lNJf;1 h g ' m e chin i s tit ifo~u p,1.i n g. - Provide enough clearance betwen the drywell end M of.the pe'netration
- and the first tubing bend inside the penetration to allow Mr<M.'.9 +.he: tubing toeflexand be pulled out of the reactor building end of the pene-
'yhl6.N.$tFa ti o n f a bou ti.th r e e'l i n ch e s..;.VcT-b;1!o' the fla~nge t'ubing: conriectio This will facilitatt flange removal and access
' % d.1. ?.. Reference 6 2.8 F '
y
ph[WNO*..WN O,9
'er.jp,.:2.2.71'.2nFabidicate and install the tubing from the penetration' to the c
l.W:
F l
Wv.: ::in'd...... h ' W:
1
- .r N
- g $c.
- .....m.e.xe.r., a.,u..ax.e...
a 7..
. r.
...r
.a
.;y. !2.2'.7;1.3nInsta111the; flange 0-ring seals in the containrrent penetration l
3 M M flarf Q ^ Q % % *?.?ge"gro3ve's M @ -
\\
?.'. i :..'.'.'.Q..
- %$rg.2.2d 1.49 Using.leng. bolts for support, trial fit the flange locsely to the l
Pc.ph.< penetration then. connect the indexer tubing to the inside flange tubing con-
- McM*Mrletionf Obsers.that flange and tubing movement does not' unduly stress the
$,$DMonnectic'n's' or' tubing.
!.'M8 $s@@7.1.5 Insert,the; bolts through th'e flange and the containment no::le
@ %.. l-M..
W3Tp.C2.2; l
l !!;n.lGQhKles<to'suppMtit,h,e' flange about two inches away from the noz:le.
Do net
.r.s:4 5 n comeress the flan;e 0-rines, t
t
.,L b c N :;a.
e r.u-W '.;l.:.E. 2.2i7.2 Guide Tube' Valve Assembly to Containment Pe*netration l
.~.. x.
. -2.2.7.2.1:? !mmediately outside the cenetration, fabricate and install the
,' guide tube section. between the penetration flange and the guide tube valve i
assembly such that sufficient tubing flexibility is provided to pull the
{
Q
'X;.
flange away from.the noz:16 about tnree inches without having to disconnect n or loosen any of the tube fittings.
This is necessary tt. facilitate leak
-.y
- ff !
- .d.3.,_ysting the tubing run from in;ide the penetration to t" valve asse.dly.
t l
" 22.7.2.2 With the flange valve assembly mounted securt:1y, the ball valve
~
. closed and all tubing connections tightened, disconnea: the tubing at the
... c indexer. '
- e
. x. :..
' 23.7.2.3 Connect.the indexer tubing connection to a 100 psis clean, oil-Lfree dry air or ~ nitrogen su; ply scurce.
The prassure source supply linc
, f,].,,shor1d contain an' isolation valve, precsure reducing valve and a 0 to 100 P' E psig pressye gauge. -
l&.c.;';:G.+Q T.':.
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v LIMERICK INTERN ALS INSTALLATION l
no
$. 97.9 W.9..
~
st. ocON*; RACT NC 8031.FSC.202 J
r CncT NO.
LMI82 y.,. h.
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mamaconwennthis File No fm/
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ELECTRIC
... n }:.) y@,. %.A 22A4211 ediH.s.3 V'
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s d. nav.d'0h,TPWT.W+ k"-
swarr wo. 2-12 l'
.i*
$, x N...... v g A,,,y y.-5' te ut {i-A {.,
s
.k,
hM@p212?7.;2.4*) Slowlf pres.suri:e the tubing to 80 psig and,using an acceptable
.k. M
'b' bble~so,1utioni(Snoop), leak test the guide tubing connections and valves.
.u QJ[m%Ei (guide tubefsections from the penetration flange to the valve assembly, A11
.k.~m.
g%Ip 4..
ISDhky'ce.u.st. b,.e.l.l.,e'ak, t.i ht.' a..t 80. psig.
did$ 3w r %.$.
~
i-NOTE x.
Y.t.Q*Q~*Qi:y.%'A~a 3.'h." '
- w. t.v W'M..
,q' :O w.r-Do inot pressur.ize the 'indexar or any other TIP system components mw CJIfNr h?g? d,urfn~g' thisJtest..
- y 2 ~.., a.
e.a.m.w
'Te.32.2'.7.2.5.: After. satisfying leak test requirements, remove the te.t apparatus,.
WP:.r'.S.'? inspect the flange' 0-rings' for danage and reco"nect the tubing tightly to
. $ ?c..% the indexer'. ' use' care not to loosan or stress the leak tight connections.
- ...'. s
- . ~ c.y.
..n r,'-
' 2.'2.7.2.6~ Obs'erve'th'at the 0-rings are positioned prr.,perly in the flange
/ A. o k grooves and that the flange and penetration no :le su-faces are clean.
Q 4.; hen l
- 4. 9.L a:
.,.-.-.3, T.w, bolt the.fla'nge securely to the penetration no :le.
-.6
..Z.
..+..t.u2l2 7.3 Indexing Mechanism to PRM In-Core Assembly
., w.
..v.......
o..d 2.2.7.3.1.. Refer to th'e containment drawings and References 2.1 and 2.3 i
E a to determine guide tube installation detail requirements in this area.
One l
l
,. %:.,. indexer. output ~ connection, usually number ten will be connected to either a 4 two-way or four-way connector input.
A varying number of the remaining nine l
,.... indexer outputs and the single fouriway connector output will be directly j
' connected to an assigned PRM in-core assembly.
See Reference 2.1.
.j.., 7.... c..
NOTE l
,l.'WM9 M r.
)
l
. s.. /..w All cuide tubes which pass through the reactor pedestal wall pene-tration: must be identified properly and have readily accessible l
3 ?:
' C@. "ylyi connections tr=ediately itside the pedestal wall penetration. This
~.
"Ma-is necessary to f acilitate servicing other equip ent. To avoid
'e 9..c-y - tubing damage, the CRD mechanisms, SRM, IRM, and PRM assemblies j
- i '7.T and their connections and other major under-vescel equipment instal-
{
- .: f M0,.lations should be completed before installing this tubing.
l
.l.;
- C Eh
' + 1 W 2.2.7.3.2 Fabricate, install, and identify each guide tube run from the in-
,',v. N dexer, or multi-way connector outputs through the reactor pedeaal wall
< yi~
y; penetration.
Use the penetration most nearly in line with the component
.: g j ;g a.nd.the assigned'PRM in-core assemoly.
Do not tighten connectiers until
',Q f[RWy qJithe:cceplete tubing run is installed and all components are secure.
. c Q-.
...~ y 3 2;2.7.3.3 If used, the single two-way connector output is connected to the
,7.
3 3r 3p,
'. reg.aining four-yay connector input.
Using flare fitting caps, seal all P -runused pcrts'3n ihr. indexer and multi-connectem
( q @:y,,7. h. m
<rn
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.z LI ERICK INTERN A S INSTALLATION i g
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PRCJECT NO. L M I*8 2 a.:
y.
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- l SU B CONTR ACT NO. 8031*FSC.*t02, na...
i me..
$:bLkk
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...- p ). ELECTRIC
- 22A4211 W.. M.J.q..V G E N E R A L ( &
.':.3 'ikR6T M M
. D M.%~ -
swtrT NO.
2-13
.N. iv'
?'
WG@. -. %d"! 0
. n.;w.; ;; w:c..,..
%M M.;'@ y..rQ' f.e *. ',[.,'
j,7 hb.D.hWWf.nO. ?M'.
c c m.'t d 2.2.7.3.4'.4,.Immediately inside the pedestal wall.ut all guide tubes and in-lc; m / r. ~.
if necessary, offset adjacent
- 5;'; M ? s"<.$ stall accessible tubing disconnect fittings.
connections to, improve the accessibility to each fitting.
l
.$.7)3.
Verify t t all the PRM in-core assemblies and the extension 4D T.Weabling are properly installed. A drip skirt and sleeve should be posi-M?[ht::.Y '. 'C..V, *'t.
??
0%r.dt16nedoneach: PRM assembly..
l
- r,*
? -*.* t."?.. M. * '.*'. :,.
- l
.d[?M.. e,;gy
- 1..
f%'.M.2.217[3'6:. Ver. f 'that'the PRM calibration tube to TIP guide tube adapter d
if l
..chnnecti6ns:'are correct, clean and. that the connection seal is properly
)
N9.9 ;W
,qp.
L:;., ini tall e.d ',on' e'ach tub e.
a.
1
...q-
$'@ ;.12 2.7.3.7. Starting at the PRM assembly nearest the guide tube penetration
- i ;J ;.~;T. connection'and progressing radially outward, connect a section of guide W;.,.Yp. tubing to"each adapter.
See Reference 2.15 and complete the guide tube D%rM/.rurs one at' a' time.5
- ~rQW:w ~:$l:l:]
- Q, ::.<,
., k.
%;.g,hn.2;7'.3.&. p..ere.g.s.cessary, install easily removable guide tube supp
- t 2' 8'iWh "ne 3 '.
i
.~y., f..
13,.
- g.. p..@ff@:6hni~s'mTaid'7..x.1uide' tube runs are installed, tighten the indexe 2;2'7;3.9#.Afte'r a11 i
tp.4 multi-way connector supports; then tighten all tubing con-
.:cW{.,ne.c..t. ions".".T..U,s.'.e *th,e.'special wrench to tighten the indexer mechan. ism
-y gf
.o.,u.
. con ne ct.i,o ns.. 'm.. :.-
.ns tm:,%.2 2:7'.4 Drive.;.,,a r
. ~w.:w:s e3.
c: W s
- m:
Q'f:f
%. Mechanism to Guide Tube' Valve Assemb1v MhMl.;.h Y2.'2.7' 4;1 J Fabricate' and loosely connect the guide tube, sect ons between the 7yy;.;
i
'* : ' '" Wdrive mechanism 'and'the charter shield and between the chamber shield and
. k,. @. o.k.. tfe f. v a l v e.' a s s em b l y ' E M
l
,t.
p4..
1 q.g A* 2
.w:.p:.;b.,. n.,'.2-7.4.2.t Tighten the mechanism and chanter shield mou l
tighteM the guide tube connections.
De nnt twist tk. chamber shield tube.
n,.,,. t.,Q. -. r..., -,..
v..
l
.J %...:.2.2.8\\ Coseonent Wirine, Cabline and Connector Installation l
n 11.c-9. u.
l
~ K;?': ;g v.-
i.:22;2.8;1 Using the-specified wiring and cables per Reference 2.12, install,
...:;, c9. continuity test and conspicuously identify the wiring and' cables between W.?.)?.(,;;.the' indexing' mechanisms, guide tube valves, chamber shields, drive mechanisms.
Q 7.~. and the TIP system in,strument, panel in the control roem.
See Reference 1.5, l
V *!.?5J:7. elementary. drawings..
1,..n...,,.....s,.
W J M 2.2.8.2 Install'all wiring and cable connectors as described in the Conr.ect:r 0.; '. T ; Assembly Instructions, GEK-45754 All exposed connections and connectors N;1%qdfl,ocated in areasisubject to high humidity and contact with moisture must be h.y
,,l made waterproof.'.s. See Reference W'
2.2 and Section 3, Step 3.2.
g04f'-Q UNEmCK INTERNALS INSTAk bYIU [
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PROJECT NO. LMl*B2 v.
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- .f.. ~ -. c.,,.a... s.
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.'c g gJ M.,s.-V..*-f*'. '.C,'k 8031WSC'202 w"'
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L LELECTRIC
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22A4211.
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2-14
+:
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h{h:%b #f.:r,u,f..'nWQi 5%.5$;,'
.. m..: b.:,N.,.W' '
.c;, 4,5 n
g2h@M.9..
-y 2.2.8.3.,Eious.,'compon~egs. -
M.
Withrall.: components deenergized, connect the wiring and cables to ttislva
. ;...:iw. '::+-?.
p,f.9%.N,5..... 4.p.- o..,,,.y *.:/..
.,s..
NOTE J
&. #?
~... -.....
C?
p.?.
y.
L Dornot'energiz(e any corrponent without first receiving adminis-3
'F 4Ctratik ap~pr6vals' to do so.
1 T'
s.P '
o % y**d, u.ff..<.3 rt;.*<.
t
. wt; ~
l v..- e.-
NN#M2.2;f'~:nm..p.g and comoo'nent Clearance Testing 9r' Guide Tubin.::en
"?l.$$lM~S}9 1' 2
.g 7 Mil!b.,,':^1.M 2.2 Aft'eV allithe TIP system components and guide tubes are securely N.
.++ installed and connected, check the internal clearances of each component M;$R6daridfallith'e}conne'eted guide tubing as follows:
dW z....v
,Qp@*p;21.2;9,.1.13.R.::.: w:.y' dumy TIP probe assembly, see Reference
' M.
c..
Inspect'.the 2.14, and'
.Md V il
- p%yqfifo necessary, u iigimethyl ethyl ketone and lint-free cloths, clean and
.y..w frepare t f?s'es.5T&2: ?&o, i ns ta lli. the p'ro be.2;2.9;1.2hSelec&acTIP h@Y[ghtc 'wh,.ii/e;r6echa61sm7 electrical pow W h?.*7 '
t 4%.Rgdr Remove the mechanism backing eelc assembly,r and the drive chains from the drive motor and the position.
....W I
- 1.,d.M.45/ h'elip'otM, See Reference i2.6.
! M W :- F.~ @. W '
/
Ohi,2;2.9.1. 3! Cleanithe' drive mechanism take-up reel using methyl ethyi keto'ne.
..?, M Q W f i.7i'k.'
' 2 :'
l 5.%..y.2.2.9.1.4.f After.the probe and reel are dry, carefully lead the dummy TIP l yf$ hec 14~ probe; assembly'on'to the drive mechanism take-up reel apd drive module.
^
.:W.ST.PThen replace the. backing wheel assembly.
Use care not to contaminate the
., f, f f.. *. ). '. ".',- j -
y.......
c.:.
.ff..;,.
- C 2.2. 9.1. 5 Using. the hand crank, insert the durrny probe TIP by hand into the l ' o i'..L W.TIP"channel: guide' tubing until the probe trips the charser shield linit
~., fs_wi tch.
The prob'"should reve freely and smoothly with a minimum of resis-e l
'n
.M tance. At this' point, the mechanism take-up spring should have a preload
,' of about'1;1/2 turns equivalent to a spring torque of 5 to 10 inch-pounds.
7:
.. ff -12.2. 9.1.6 Connect i calibrated 0 to 300 inch-pounds torque wrench to the j r. c-/. 7 rive mechanism hub...
d
.... ' :y. :::.
=
Apply electrical power to the appropriate guide tube valve asse:.bly 1 J l y p@W' y 2,.2.9.1.7 j
.i, and open the shear and ball valves.
. n.n 9 : ;.y
~.....
2.2.9.1.8. Apply pcLer to the appreoriate indexing mechanism.
Start at
s-
. '...,.e ?i'ndexer position'nu.ber one then pr:gress through position nu-ber ten as K J rMthe' testing proceeds.
Record on the system check theet the identification I eig.j,:.$of. etch TIP channel and the selected PRM assembly probed.' To confim this, I W.?
- r. carefully uncouple'the guide tube connecMen at the selected PRM ass'.mbly
, K4.,.i. /...,. ". and observe that the dumy probe is in the correct PF"--ti.
,*!. q'..i
. f Ll RICK INTERN ALS INSTALLAT1
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k,I@&. -}.Q.i 1 c[..
PRCJECT NO.
LMI.82
. ',' - ?,
s.
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f; s,
,.-&, 3,. -
SUBCONTRACT NO. 8051.PSO.20 i
..v...
'C 3pm -
F D No A A"#
.Q Ly:.n'.
y.. y. e,y.aswQW m.s Q:y-j%g,Q.E N E R.A L d.E Ld CT RIC
.eg 6
22u 211 iS p ;&, 4 GM4* Ti ' E'". -
%1
.%4v -
eg.ot,:g' $ -
SHEET NO.
2-15 tidhe gpceyC t.
~..:. v..:..:;: =. : -
W.,vp.QM....
.m.
- G,....a
. w....c.s.-
El*$ s%M.%'.'.%,*:..
- Q,fl4.iW R -~
CAUTION Vh w If1$3.Y4*Aha U
(N0i&QPc M::<T l
'.*.TL T;.Q!'EW den ~o't' forcEthe probe through the tubing and tubing components.
2$i'/
r.l. Note ~restHition areas and attempt to adjust the tubing and com-
@!W4%,E'.,@%f ponent' position' to keep torque values well below 150 inch-pounds.
~
ff l
yf@.9416/WIf this'i/alu'e'is reached, locate, disconnect and if necessary, '
j;6d
.@T rep.1(ce thelfestricting component or tubing section.
Sometimes
_?j @1'sPE '~l:. ~ tubi.ng' connections and bends must be remade and/or more uniformly I
QM,4y,M.{ a' valve, or. the irdexer mechanism, the component may need adjust-l w:
. k i' cistributedQ If the probe stops at a specific component such as h
O.
.e c.P ment: for' proper oparation.
Never apply more than 300 inch-pound WC.Wlyh !$ ' torque which might damage the TIP equipment.
. Q' i. f f li'Q :'
Q
..... o.: 2.2.9.1.9.Using the torque wrench, slowly rotate the drive mechanism reel to 5,f" Mnsert the' probe'.into the selected PRM assembly. Observe the torque wrench hQ."@ readings..& The readings should slowly increase as the probe is inserted.
' re..q.wp:After verifying that the dunny probe is completely inserted into the selected q
. M c ' g ~.-e ;
38
s n.- -
- f;C S.2i9.1.10' Slewly withdraw the probe unt11 the probe tip again actuates the 2
"A..
u chacher shield limit switch.
y '. - f.U.'.., -
- . C '".- ' 2.2 '. 9.1.11 Select the next indexer mechanism position and repest Steps 2.2.9.1.9
'. 'and 2.2. 9.1.10.
" W. _.
'. 3 2.2.9.1.12 When all. TIP system channel clearances have been satisfactorily
. ; -a...:-tested, remove and store the du ny TU' probe.
Then, rgeonnect all drive mechanism ~ drive ch'ains and electrical wiring.
Also, cioso the ball valve
%. R ::n.n the va.lve asse.bly.
.s I
2.2.9.1.13' Comolete the' system check sheet and submit it for administrative
. review and filing.
2.2.10 Guide. Tubine Puree System 2.2.10.1 Remove 'the purge. valve asse.bly and indexor mechanism prewire T.
'L i centrol valves (PCV) and inspect them for dam. age and cleanliness.
Refer i
~ to the building and containment drawings and References
.. 3 ano 2.'2 for information cencerning locating ano installing this equipment.
.c$.I.10.2 Mount the purge alve assem.bly outsida af the chamber shield roca
. V
- 1. on the wall adjacent to the purge piping opening ttrough the na11.
l
\\
.3.
. v.
2.2'.10.3 Install a PCV at each indexer mechanism in the drywell.
Do noc M. ?... J : connect the PCV,to.the assigned incexer mechanism until tne piping up-
- 9..w(N Gst.;re.am of the indexer is pressure tested.
- gy
( & Q Q "'i: -', *.
IN';'~("lf.N.((N.#
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$ LIMERICK INTERr4Al $ nN$TALLATION 1 tfh % :: Q, :. ;?,
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. PROJECT NO.
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SUSCONTRACT NO. 8Cr.lfCC 302
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W Fe. d,. 2.210.4..Usi'n'g: stainless steel tubing and valving, fabricate and install the.
.v i,k.Q pu'r'ge's'ystem pipihg manifold and the tubing between each indexing mechanism Me.%@fM,.. PCV andithe?assi'g'ned containment purge piping 00,[3
.p. f 3" ;.3To' avoid: particulate and moisture build-up in the purge line, pro.
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f s:.V.,.s,d.,4 vi d..e '.l o.wi. ~l i n.e,,; po..i..n..ti d ra i n. a nd fil te r* t ra ps.
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- .;Q,1..,.6% +. :.lmmediately outside the penetration, install ; check valve.
1
.cm S R.2.2~10.5 i Then i
n~.R[dO' complete ;ths tubing'run through the chamber shield room wall opening to
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purge valve ~ assembly.
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yp 2.'.10.6.z. Guide Tubing Purge System Pressure Test s.
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NOTE t.rA M ) FM.s.'/ ?h. FM. f.H e;.df H..
+-
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. Use onlytfiltered, oil-free dry gas (usually nitrogen) with a dew '
I 7(@X$i.QppointilessRhah'.10'F to perform the following test.
l thw te.m:w.: n. s..w<.\\.
w w..a. a d; )40: dexer:mecha nism' PCV n -M N, ym.
.e.,Close.- ' purge valve assembly inlet and outlet valves and each
.M
.10.6.1tn th e,
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9
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I,$$,$+.2'.2'.10'S 2G Conne:ctia;'.125 psig dry gas pressure source to the pu
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1dji'ser/ sly': inlet"p,o,(ty. The valve assembly pressure relief valve trust be
~
.w.m % e.7 upstream of.<
fpp.
- W.'.h.fN f.'2710'.6'.'K:the rotameter.
.~ p t:. 4.
'gm. :;
~
35 SloN1y'oyin' the pressure supply valve and the purge valve asse-bly I
9 AM@udw? tin 1'ec valve?, icf'.I shy. r m :
f y.f h
.K@d.@.42.2?.10.6.4? Slow 1?in' crease the pressure to 100 psig and adjust the valve h W ir?'a nembl h.c:,".v;.%.-. y:pressuri relief valve to just open.
~
a y r.'y,.,. ;.....g; ^, 2. 2.10. 6. 5 Decrease the pressure until the relief vr.1ve close
,. y,4r;.should be'about S5fpsig.
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, f.. f.2 2 2'.10.6. 6.1 Close the.rota:neter flew control valve and open the purge valve
~u...y.n a,, a..s.m.sembly..di scha.rge' valve.
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Us ing$..1hcal power or nor.a1 remote power, energi:e the purge j.'/
.WD.;.Jh.F.' 2,'2 i10.6. 7W-~~alife assk.blyriniet' solenof d valve.
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.:g@em? 2.2;10.6.8' Slowly 4 pen. the rotameter flow control valve.gf. low surgq. t'o. pr Afte* an initial l Q@.,,p;e.g,(rotameter shoulgindicate 0 CFM flow and the inlet pressut e should a
, W.,.;,4,Ju.j.e abcut.95 psi
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a%.w 6. &,. p.2;10.6.9..Che.ck for.'a.nd repair any leaks.
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LIM ERICK INTERN ALS INSTA' LATION Q, '. ' p -
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PROJECT NO. LMI82 v.
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SUBCONTRACT NO. 8031.FSC.302 -
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5fY'Y'".f?~d.%.bli$V',)$$i'Nl.T kTT) '2.2310.6.10Murgf the' piping and valving by slowly opening each indexer PCV.
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,dqd..y%y,w0 bye'r'yetthat,the'gurge valve assembly rotameter responds.
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2'.2110.6.11 4 Depressurize the purge piping and connect each PCV to the assigned m
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2i27.10.6.12.S@ Clos' eta 11.? PCV's and repressurize the piping to about 75 psig.
vElWNtr@h a113the'TIP guide tubes installed and the guide tube ball 4,3
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t 4
~ % 4 a,10.6 13 W
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. slowly open'and set each PCV output pressure at 7 inches' of lve's Eliised.hYh. Y. s...
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8
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NOTE
'$hh, )M su?~ 'ot ex I
Do'i
.this value.
Each indexer mechanism contains a pres-
, Db+L;ll.W..-
re r'eliefhalve which is factory set to open at about 1 psig.
- .i
.hd@,Qyi[iWith),theif,CVjfadj0sted for a maximum output pressure of 7 inches 4;;4..of. H 0 thei.i,ndexer. pressure will. remain considerably less than 1 h^d.'.@
2 b'
t.eaking l M'Wi % :'A psig'.".!!T.his,tayoids: actuating the indexer '.aelief vaive, Kg.nMc,&::. relief? val'vessust be correctly adjusted or replaced.
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'-)1;. fh.;,?y0 Do' not attempt' to remove the indexer cover or work en the ir.
%TE M.
h.:.'fd /'M" fwhenj i: ii'.lyressuri:ed.
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a'y T'A,Q~C(.n.q:. 2J2;r10.6.14(.With.'all the PCV's set at 7 inches of H 0,imeter should in
.l&:..n,..M !.b.'v.alve assembly..r.ot.ameter flow control valve. The ret g
. c. m 9;rx.'etW.(,less i.han a.6. se,f,h, total system flow.
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Tw'TM),I2 i2'.10. 6.15 If necessary, leak-check all guide tube connections and guide gq t'ube components'."especially the unused indexer and multi-way connector-
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E
. Repair anyc.. leaks. Total system leakage exceeding 6 scfh is not
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Because the guide tubes are open at the drive mechanisms, it is not practical. to perferm a leak rate test beyond the guide tubing I
? '.
ball valves; However, all the guide tubing connections and com-s
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ponent mounting bolts must be tightened.
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an: purging the drive mechanism and the guide tubes up to 4TN Eth'e'.'chamb'eV shieldilimit switch opening, tne drive mechanism purge system M
iiJon1ffused to~ reduce the guide tube purge system leakage when the ball
-- valv'e.is!open:3To\\ achieve this requird considerable gas flow; thus, the 7"'Vy $d/ rive mechanism 3' urge system uses plant instrument air rather than nitroge k
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il-free, filtered and dry with a dew point less than -40*F.
3p. A.yj,.p.,}his air %..must be; o.~w...
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CAUTION' NCi C:n %. y:l.:.::.C,):
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,.,. :. fa Do.not attempt to remove the drive mechanism covers or work on M..,.:d@.';.fc?.
',,7:
th.e drive' mechanism when it is pressuri.:ed.
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W,:.y m.... W.~W.
. i 2.2.11.2' Close the ' drive mechanism rotameter flow control valva..
The guice ii.'ipgilh. ~, tube ball valve.,must remain elosed.
$;f.s:: : :N.,
Install.y :1 purge ano connect nonferrous tubing an'd a shutoff valve m.
r.~7l*.h.:-Y.:c 2.2.11.3, the TIP drive area instrument air supply manifold and the AIR
.j
- ' 9,between c..
'; connect. ion on the drive mechanirn.
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~ 'EM 2.2.11.451ewlfopen' the instrument manifold supply valve and thi drive t-d.v; i.:.umechanism.11ne shutoff valve and preriure test the line to the rotameter
. :." 4 ~
S.fl.e.w. cont.rol.. val.ve..
.u.
' [. ?.,-[,. t o
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, drive mechanism cover securely installed, slowly cpen the En
.G-.; y..:. 2.2.11.5 ' Wi th the(flow con *rol."vtiye,and adjust tne flow tt 3 scfh.
.. r...
n
@, y,. ;;[2.2.1.1. 6.; Verify th'at the major purge flew is through the TIP guide tubing, c.{ 7._ ;.E. If 7necessary.'depr,essuri:e the system and seal any other major leaks.
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The drive mechanism does not contain a pre:sure relief valve and gy no7;
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,......i ^ is not designed to be leak tight.
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~i. 2.11. 7E After'a1.1 the guide tube and equipment mounting bolts are tightened
,.CC.m cGand the leak. rates are acceptable, close the instrument air supply shutoff
, '9 l. ' c f valve and allow;the equipment to depressuri:e.
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4'... ~
2.2.12 After in' stalling and satisf actorily testing the TIP system ecutoment, o. b... gl.- * )
~
$.Qus$ffg, fill,all: the.TIR"charcer shield units with the provi r
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. ( [ n.... chrI;j,,i,'ngfe is high purity lead icw in HW W mee,. content.
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LIM RICK INTERN ALS lhCTAI.L.t TION
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PROJCCT NO.
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SUBCONTRACT NO. 8031.psch202
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2 19 continued on 3-1 J.v%y7....a.e
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NOTE
'$m..a...2.Q;p:'. Installing'.and testing. the actual TIP dei;ector assemblies and the
.WiM associited ' electronics is normally performd during the TIP system W,.f4 94i,5 @; d.i.P 7.
preoperatiorial testing.
If preoperational testing of the system
'd
.0:E..':g 'is not ' scheduled' to start for sometime following ins tallation, Q. r.NM"N.,.U ' provide' adequate equipment protection to avoid
. M'l.i...'J.
W
^
If the system purge flows are not maintained, n.
.".E:^ and contamination.
..Z. n...w1 :+% S.. ' all'syste..m. v.a.lves should be closed.
'.uc t.-..:
...
- r A :
E*' 6O d.'9...s firm that all'of the TIP system equipment is deenergiced and pro-
".-g* !l W. 2.2.13 ' Co nA tected in accordance with the In-Plant Storage Section of Refer 2.16.
+
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i
[.x..,,...,j.Tf '.K,,2,2.14. Submit'alMequested and pertinent TIP system installation and testin
.~
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- < rea recorded data for. sdministrative review and filing, such at
the identifica-f 3$$,$ti,cn number anditlje' installed location' of each drive mechanism, chatter shield.
stff.Q.?J r. and.indexin'g meetianism; verification that TIP channel selection o f P M*a D blies is' correct?.:?t{fghest torque values o,bserved to probe e3ch TIP channel,
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LtMERICK INTERN ALS INSTALLATION
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PROJECT NO.
LMI82 J
4,
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SUBCONTRt.CT NO'. 8031.rSC 202
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SECTION 3
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.p;;.pr.p.. s..yt k~;.1 TABLE OF CONTENTS t.
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s:. -N~ t,. 4; 3 3;1N..
33 s
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k:fym:..E y.1.2..iis Referen'w y.~
13 ce Docurnents List 3-1 33 QRlG'.0l(l' T22.i A. ~C COMP,y.T... PREPARATION AN
.%:. r..Yiv rQya....
t/- M?
ONEN 34 b
N f 3i2.1<G'Q>.b,A MG"iR..
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. l.
87$!3'2.l.3bp; Gamma-Sensitive Ioni:ation. Charter 35 4
" ~
i
- ,W Chainb'eBInsulation Resis tance Test 35 i.
.L' :i$, "fl3 2' 2 3%{.4 Scintillation and Geiger Muller Detectors N.c C3;2' 2'.Gi; 3,5cinti11ation Detector Resistance Test 3-6 37 i,'
t U-iW312'.3E'3.% Con,ne'c'(ion Wiring and Cables 37
?i.906 axial ' Cable Connector Insta11atien and Water--
3.o b.e 14P3;214P:XW'offi6:g}d Detector Connection and Waterpro
~
TCfgMht.94l f h.icharifer an
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2.'S.'. t.,2. R.a.d.'.i.iii.. on.' Shi el di ng 1.
3 16
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4.fW:;9y.w,%%yy:AIN: STEAM LINE RADIATION MONITORING SYSTEM' s
M 3 17 c+ 3.3;c
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W 7 c.y+ 3.3.1..;,.-
.Ecuipment.
3 17
- 3. 3 '. 2
,' ' Ion Chambers and Chamber Wells 3 17
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3.3. 3 Radiation Monitor Panel 31g
.s
., G ' W... ',.,3. A, 0FF.G.AS. RADIATION MONITORIN3 SYSTEM 3 18
... ~.
...,m....
MA' 3.4'.2 ~
Prc-Tre'atment Off Gas Radiation Monitoring Subsystem 3 19 lJ.Ii.%W 3.4.2.2 Sample: Chamber and Piping 3-19
.p6; '. "< L 3.4.2. 3 -
Off. Gas. Samle Panel 3 20
{lp.1 3.4. 2. 4 Off Gas Vial Sacler 3-21 E;.;
'. 3,.4. 2. 5
,, Sample' Chamber Ion Chambers 3-22 hf-3.4. 3 Pest-Trestrent Off Gas Radiation Monitering Subsystem 3-22 3.4. 3. 2 Post-Treatment Off Gas Sample Panel 3 23 3.4. 3. 3 Post-Treat:nent Off Gas Vial Sar.pler 3-23 w;[{... t. y,....j'd,...
3.4.4 Radiation Menitor Panel 3 24
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3-24 L
q 5:lte 4M 3-25
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-W[:3;513.i.N;[' SampleLLirns 3-25 r.?p.W.6%r,3.5:
- 4. :r 3-26 3.5.5;*7@d. 0ff. Gas:;Vp.t Pipe Sample; Panel 3
Radia tion. Monitor 3-26
~
-A-t?..*P:u#.Wn. i Y 2.. f,f q 3.6
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- fG.
.)l REACTOR 3-27
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.3.6 sly." '.y Equipment?
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4 9/. CARBON BED.'YAULT RADIATION MONITORING SYSTEM ty y
.w...*.p,.. - e Equi.f.t.pment.'
3-28 I
/v., A,. p 3.7. 2.c
>r 2
r r
@i;(' **M13.7;4 '9M3.7 3 7
'. ' Wiring',' Cabling and Interconnections 3-29 l
$. Sensor Converter 3-29 M,.if. -: 3.7.5 J.
. Indicator Trip Unit 3-29
.T*.: Yf,y.,3.7. 6.
Operational Test l
3-30
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- PROCESS: LIQUID P.ADIATION MONITORIN3 SYSTEM 3-30 l
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- y. spv.r. 3.8.1,.. f.. es ed p Men..
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- r. qui pment _
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,. ::. ?J.' 3.8.3 c Detector Wells 33*i i
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3.8.4 -
Pulse Pre-Amplifier 3-32 1.
l.
3.S. 5 '
Cetectors' 3 32
=
~
LIST OF FIGURES I
l
' FIGURE NUMBER /.
TITLE
. b.
PAGE a.
l. s,v.:w.,.
t.,.
' G..<..bi ;.,,.., ' ' 3 -1 insulated Ion Charcer with Waterproofing Kit 3-10 M... E...
....w.s
- i. J 3-2
- ' Ionization Char 2er with Waterproofing Installed 3-11 3.._.
- c,e.
.. Q f,;; c,'.
3-3 Sci,ntillation Detector with Waterproofing Kit 3-12
~...
w.i.h. 'h,.. N 3-4',
- + Installed I.i 1.' Scintillation Detector with Waterproofing Kit 3-13
.C.
.v.
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uMERicx INTERN ALS INSTALLATION
~
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PROJECT NO. LMI82 3;'
8M20-.NM#@.u.f...y.J.,'Nij*a.y; SUBCONTuAC7 M. 803k rSC[202 p
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.N SECTION 3
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.l. PROCESS RADIA. TION MONITORING SYSTEft
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1,' Although' the"exact name and number of radiation monitoring and scmpler
- y: NM.'y ia typ'ical.'systemM. include the following:
~
7.'/.'
yiystemi in'the:Prycess Radiation Monitoring System vary from plantf te plant,'.g.
will
. :.. M s W.:::. i ;. A.a.'.
.V:.M.,,.:, Cip JN Main Ste n Line Radiation Monitoring System v
".. 7
+.
- ".< 79.Q;
..,.1
. a...wOff. Gas Radiation Monitoring System
pb,.h+.3l38Y.,5'.':l 0fbGki Yeht Pipe. 'or Stack Gas Radiation Monitoring System s
.; q,.g.e.
. t...... s ~.m
- ..--W
- .,e :C:w,.pf,.t. Rea. ctor Building... Ventilation Exhaust Sampler I
c
- %.s>
- 2.. - ~
(y...,. N
.a e.
h 6" M;-;. h Reactor. Building Ventilation Exhaust Plenum and Carbon Bed
?f:I' Vault ~ Radiation Monitori.ng System A.,w:.-;em:@n ;: - u.
w-n.;T.ilt) Radiation Monitoring System l
...s.
f[s.:h.. ? ;r Linear.'.(,F. lux, EM.g m.
. v.
... uu...-
. s.:. < p..
s.
O.
Procetsl Liquid Radiation Monitoring Syster n.s:;.* s:p,.w.f.
...q.,.,.
- f..
'*d"..l.$3:12.2 i The-followthg'.~ref'erence documen#ts'contain information concerning the d.S in'stallation'ofithe; Process Radiation Monitorin System equipment.
The l -w$@7.MCplant ' unique' data"sheets which supplement this knstruction list the General l,N:
+46.V E1Fetric' Master' Pari;s. List (MPL) number for each document.
M I
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- :'r.c f.a u.. "
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1 y.:.. w. e '.,
c' Reference Documents v
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- $,,..h@.#.w;M..m.
- .u p m. + Reference Number
+: e '.: '
l Descriotion
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l W,.:.'. 3.. e.. C '
~ 1'E 3.1' c ' -
Process Radiation Monitoring System IED
'~
- 3. 2 'c.,7.
Process Radiation Monitoring System l 5 c:;,g..sj/., v..
Elementary Diagram i
s;.,.o. g. c. -
- 3. 3 : ;. '.:.
.s Process Radiation Monitoring System Desien s
dra..Oht fc.
Specification and Data Sheets W.a G
3.4
,t,.-s. '../. ;g... e..;
Process Radiation Monitoring System Instrument Data Sheets
,.;, m -
M.'J.? ','
3.5
.Special Wire and Cable Specification 2.':. 3*M.l'.f'J.E.
~ ' 3. 6O -
Solenofd Valve S@$dl y..yy. : ' '.
.3,7,j":'
Blank Assemb'ly
- 3. 8.$..
Shmple Chamber (Off Gas)
Sp%fi.*il&p.,.
Ql2J
.i F-
- 3. 9 r.U-Off Gas Sample Panel i3%'f.
i' ' $ 3 1 Off Gas Sample Panel (Poru ust) 5
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LIMERICK INTERNALS INST L1 AT r
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pn0;tcT NO. LM182
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SUBCONTRACT NO. BO31 FSC R
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g M $ GENERAL
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Harv No. 3-4 i
$1fff.*/M3 T M. Q P,.i '
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3 4 4f REfEeni:e Nu'mbe'r ',
Description y-b c'
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Off Gas Sample Panel (Connection Diagram)
.T
$K,w-Md,9r3.13r$l*.i,H.'. >13 MSF% 3','12 off Gas Vial Sampler X-g. g.f. ' Detector Well (Closed Cooling Water).
6 1:,:,
s w h3,14,.p.s. V 4 Detector. Well- (Liquid Sampler, Rad. Eft) '
.g Mk3;15.TS"//? " ' ~. Isokinetic Probe
?
,c 77r.t
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Sensor Converter / Detector Detector.(SteamLine)
?g *?;f $.?p' D.' 3'16fg?';;',, -
37./.h." V(ej 3'.18 b"d.'.-
3 Detector {ServiceWater/RHR) 0ffGas)
.f. Q4RW; " *.p' 3',193-@ ";f k Detector'kClosedCoolingWater) 4
'J.d 4 $.;G "h ['
~0$;3.21 %,.
Vent / Stack Sample Panel 5.T
,O.3.20M'"
nttector r@FS'?W g:hMe w;%yMt i;;
75:
w.. 4,.w w " 3.22:2.
Vent Pipe Sample Panel 3
..leS3.233'.b; Vent Pipe Sample Panel
..M: i 3.24 JV "
Indicator Trip Unit / Radiation Monitor p
6 eW ;.- M #.e9ti3.2539..Electrical Equipment Separation and p %f[$q.;.g3f(:;:
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. Saf aguard 5ystem ft'P M
?'" W1,.%p,' 3. 27&;L.
B'dR Equipment Environmental Interface Data
-s-e s
4.W.<a w #.,-3.2699 Equipment Storage Requirements Q%# L' t:r.
.c C
3:1!3'.tDe'p'e' ding"upon"; plant design, plant location, the owner's selected op-n
$l66iis'. andYgulat'o'ry iroup' require.ents, the Process Radiation Monitoring
- Y.,.o.: w.,.SfstemideWritied fn this instruction may contain additional or fewer sys..
S o %,,tems"and monitoring. channels.
However, the additional equipment, if any, Q$g$1 siimila'r.(to, th'7 equipment describe'd in thir, instruction.
l 1
e For details MMDh;concerning additional equiprent, refer to drawings that specifically apply J..w:
l.w'r. ;; 6.t',o'Tth' "e qui pi,.en..t..T:'." "-
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r
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.. ' ' 4 31.4r-Although' the*various systems which comprise the Process Radia'tio,1 * "
$Nl;5.'@h the system linsta11ction and operating methods ma nitoring Systid contain similar equipment and perforti similar functions.
i
,jppfy$JBeforeattemptingito'installandcheckeachsystemanditscomponents
- d$
l
.( d t ? g'., review the Ra.ference 3.1, 3.2, 3.3 and 3.4 diagrams, specifications
.;.F.L.gnd'datasheets..~
'['..',
l cr,.
mg:...
3 2.,.CCM.PON.ENT PREPA. RATION MC INSTAU.ATION
.3
~..:..e c
- y..
cAyiton
.:. c. f.:... j.
'k.fi.h ' ['j
. These instructions cover orteinal ecuiement insta11atien only.
. :s.i Equipment removal and installation after actuti use will require
' P./.
special instructions containing cautions concerning personnel i
radiation exposure and the handling of radioactive equipment.
?b.'/ /
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LIMERICK INTERNALS INETAMT1cN Mii%yx:cc.,
PROJECT NO.
L M t. 8 2
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- SUBCONTRACT NO S c,31.F S C.2 02' ~
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ty",3.2.1'.1?cRemove1 tfierionization chamber (ion chamber) shipping and storage 55% nt'-fp'rotection andJdaiefully examine the chader fc. damage and cleanliness.
.k'E!.T NTheTcharfeFa'nd{ cable ~ connectors must be clean and dry.
Avoid teuching '
- . N_ N., w' e.t.he' corine.c..m'or.'.i.ns l..a. tor. s.directly wi.th the fingers or contaminated t
equi.pm.....ent.
.u.
y
- y.-a.
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.w m wp.c m.m.. * <.r. s. + p'en m..q -
}
.c W.,M. t;l13.2.1*.2 ;Ver'ify that.the. hamber' typ'e' and its ch teteristics satisfy the c
'd
,T aisigned' usage and'specified requirements.
See Rs.'erences 3.2, 3.3, 3.4 G
q,, f..?.N,:
../y/ a n.di 3.;'.16.VN ".et. "C
. w:< y.7.
- 3. 2.1. 3 Chamber Irisulation Resistance Test l
.pM
.:s -..
.7:
M:g%qy.:
a
%9 NOTE
%.g.& ~,
. a ?.:... a. -
hid.?M6%.The accurac7Af. the.following described resistance test can be l
%ti./ adversely [affe:ted by many ambient conditions such as highly j
%glr.@h.b.W
.%; O
'p,T humid or, unclean atmosphere, touchir.g the connections or che,mber
.g.
during testing or ele:trical noise. generating sources. To re-f g e;4Nfr?.u.
duce measurement error and unne:essary connector cleaning, use
.T enly ' accurate test equipment and the recormended test precedures.
' T.i., 3'. x ?..'?q'Conduct. the tests in a good quality environment.
1
. :;. 7 ;,
~:..
l
- W ~'.e 3.2.1.3.1. Following the e:erating prBcedure given in the test equip ent l
M. -(
manufacturer's instru: tion manual, set up and verify the accuracy of a l
> ' Tr-e crecision high resistance measuring test meter, such a.s the Hewlett l
- .;, j. h, -.Packard Model 4329A test meter.
. g., ;.:..
- ~...
-.. y...-.
NOTE
.r r
.p.,
..y Do not set the test voltage switch.'.bove 10 volts or apply
.r.
voltage above this value when testing the various char,ters, detectors, cab.ics, and associated equipment.
,9 ' '.
'.,'3.'2.U 3.2 ' Check thh charter ec1'l ector: (C) electrode to high voltage (HV)
~
~
electrode and charcer case resistances, as follows:
.;n;
- c. *
- *cg,' g,
.g a.
Conne:t the chaser case to a good ele:trical ground.
?,['.
,; c,.
b.
Using ' care not to touch the connector ins'lators directly with' u
.the fingers, connect the resistance reter cirmen lead to the y'.
1Wf.
1>,
chamber. connector shell marked HV.
Then, s. ort the HV ccoduc-f y 1 g '..' A ter to;the chader case by inserting a wire jutoer into the HV
/
W.h c...6..
., ','.conne:ter center conductor jack and fastening the wire'to the.
.i
- c.
Q.:rt -e;; 2. & n.3 e.
- 7... '
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LIMERICK INTERN /.LS INSTALLATION /
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b-5 suBCONTR ACT NO. 8031.F'SC,*202
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9 ;(.
- x.i.~..d H;. ' *
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..%. C..:
$'W7D...
~,
%%.i c.[j'ack ofc.the C marked connector.
Insert the measuring test meter lead into the center conductor L-t Do not short this conductor EM+./$a,,N....Ap'.. -
i h
.,.A..J.5. 6.. r3.t,o,,the' connector shell or chaser case, t
s y
,.q,w w. :..; d l
) E'h@ds/?k.W2i'.'f;'i d.niWith the meter test voltage set at
.O.
'trodes?/ !f. necessary, allow the meter to stabilize and then M
N.R.?..
read and. record the resistance value on the chader check sheet.
l 3'% afwW.'J."To be ac'ceptable, the C electrode insulation res N.M.DMP.e :.. exceed.1.:x.1013 ohms.
3 j
)
h:rw..4.w'2.1M.3NToMaiu'r.i'the insulation ' resistance between the c
.v
~. i.g
.J 2y3'.
/
f
,gv.oltage(HV).' electrode and the collector e'ectrode and chamber case, con-t
, rg N : yMgnect the meter' r5easuring lead to the' center conductor jack of the high ' voltage' l
[Me.
e y.f.j,Q[J to the grodnded'. chanter case.
d conductorJjac'Cofs.the collector (C) connector and short this connection
- h......
~
The hich voltage electrode insulation re-
.b. W @dchai,'t e r., 'c.h e'.c. k'.s hTe.+.".
~ '.
l MW.Wsistance ni0st'eicife'd l'x 1012 ohms.
Aecord tne measured resistance on the 1 - b?
c Q u o m.u,.m.~
.. w:;.
'Mbj%m:n..
Mh
.2:
a.my c:
$~ikp;p%,3.'.2.'1,.3.4 lIf the; charter electrode resistan it may be.necessery. to clean the connector insulators.
After cleaning the b c$i. ins lators,'alletthem to dry completely before reassembling the connectors u
i
.W and. rechecki n'g' the. resis tances.
If the insulation resistances enntinue to
, MW.Wbe uriacTephble7l Vet' urn the chamber to its shipping container and contact n-7<M.U.8 the' charter mahuf'acturer for repair'or replacement instructions.
Kcg *,gg.-
. f' Ve *y g,: *,..
- r 4,Vi. ..'.';
W noTg 4
i,;L*!,r.M...W., %.' ' - \\ - Q%. -
,5
... w:...C l2..... Do not waterproof or install 6 defective chamber.
For charter
' ' ~ " * '
,gg..
..,.c.
and connect 5Pwaterproofing instructions, see Step 3.2.4.7.
l
$l'"t *."<: 3.2.2. Scintillation' and Geicer Mulle Deceeters f'@}li::: C.
j
?.
N37i
.,. r. w. a :~
Geiger Mul1'eE (GM) type detectors are similar to scintillation C.n..
. m':v...L 4 detectors and should be similarly insoected and installed. How-
?4 M,..C:D..c. -
ever, unlike."ion chambers, Geiger Muller and sc5ntillation detec-l
,. e.
':Qf-Q ^'O
. tors' are' very' sensitive to physical and thmrmal sheck.
Handle i
,QJZ f.,:
these detectcrs carefully and avoid ex;osing th,;.m to adverse J
., f; envirohment's",'especially whore temceratures of < 32'F or > 125'F
'4 ;*
(' T " +n i ' minu. experienced or where temperatura changes exceed 10'F per are
- c. A..
te. N."
i
.. - : %..L,., -.
r>.
u :s
.i
- 4
.?yg%,v/ a 2.1. ;temove'tse scintillation detector shipping and storage protection 3.2
'u
. l.
nd examine the' detector for danage. The detector and especially the cable y$@'*R:%co.n.nector and?intirnal parts must be clean and dry. Avoid touching the
. 's..q f rconnector insulater directly with the fingers or contaminants.
~
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LIMERICK INTERN ALS INSTALLATION,
r 4.C.
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~
,4,.'. -. h'..
PROJECT NO.
LMI32
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sua oNTRt.OT NO. C0ol FSC 2C2 a.v...=.
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.:- O.im... i nt 52*%;.Gs d
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3-7 W..
- <~
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- .-Q.t:;g%.
a
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5,.t e.
q M,A.
1
.+ "
',g+.....,?.y A. ~ '9.. : P '3.2;2.2. Verify that'.the detector identification and t
.D.,
(M' $* ij. 'Fulage' and s'pecification requiremnts, see Referen
~
h'N@.,' 04,W%.V.W5-M.6.'.
l 1
$.,7 3:2.2.3 Scintillation Detector Resistar.ce Test f M.S.7!! E i M $.77fT h
.(
W. 3' Model 4329A or
$ %.C.2.2.3.1Econnect+ the measuring lead'of a Hewlett Packar d
l' iqui. valent!iesis'tuce meter.to the center conductor of the detector con-j d.O:. 'nector.'t.Then' connect the comner. meter lead to the connector shell and
{
M)U,W;. 3.2.2.3.2" Set.the.neter test voltage switch to
' @Th. th'e'deteito(' :ca's'eh.:$.T'".4.. 5 2 '
7 '
Oc and measure the. resistance.
...?,T.c.B.f.4;
. 1;' %b. ; '
TN meti'should. indicate the total resistance of the detectur, M.';D'M.3.212.3.3
'd e
- d. MDy.w.g.1 series connee'ted,'# dynode resistors. This res1 stance should be about 6 x N 'lo sfohms#.>.R.c..sdi.t.c,e. detector serial nunter and the measured resistance.
ec h
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Inspec.t.the ' component connechen wiring and cables provided for er.ch
.i 4 '7 F.33.2'3.1 Process Radiatie'n5ystem' application and verify that they satisfy Reference Qhp?[2rioise, anti-mic, hist.High temoerature, humidity, radiarton resistant and low 3!2.5'rf4uirese
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rophonic ty;e wiring and cables may be required for some in '".
snWm.Y s ta11 ations. ' See' Refe rence 3.15.
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.;.3.2.3.2 Cea. firm that wire or cable conductor continuities and the insulation 4 ;.y'?'Y resistances for.each are acceptaole before installing the wire or cable.
t<.
i
!-J Wiring or cable conductor (s) and shield (s) must be splice-free. The con-
~ductor continuity resistance should conform to wire gauge ohm per foot re.
f sistance tables..When not connected, the wire or cable insulation resis-2..
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- tance between condubtors and between conductors and earth ground should be
..s follows:
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. Non Coaxial? cables and wiring
> 1 x 10 e ch:3 5 ' :." '
Stai1dard teaxial Cable
> 1 x 1010 ches
.Q Low noise, anti-microphonic ceaxial cable
> 1 x 1013 chts
' ' The latter cableP especially when used as the signal cable (C) from an icn R,.
g j charter, is extremely sensitive to insulation leakage.
/.lse, observe that r e. satisfactory quality assurance data is supplied with all cable and wiring.
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(h...1If/this inferr.atic'n is not supelied or if cable and wiring resistances are l
. not satisfactory, do not install the cable or wiring.
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PROJECT NO.
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F 1'n'giir stallation,focedures as outlined in References 3.5 and 3.25 and l
.Ysirig 'dWibnatid wire: ways' and wire and, cable types per cable schedules and
- b. < ?5 MS*y Referencejyf 3.2,Ein'sta11. the wiring and cables between the respective system l
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.'c~oinp6tients%' corinedtions and designated terminations.A11lc'able. lengths mus
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'psnetratioi1, Ion chaders usually' fequirCtw'o' co6f al"cables,'a low noise enti-micrcphonic coaxial signal cable
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if fyM.'and*,s ' coaxial high? voltage cable.
Scintillation and GM detectors require
.F wp.-TO only one"standard : coaxial' cable, m t J.h.w:W. '
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%'3C.I'iDiength. isTprov,ide~d to facilitate component movement for service and testing; N
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Chader and detector
' "$).M,pjthout having to"disconnect the wiring or cables.
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.:ph. minent ho.ould.be',lo'ng enough to place the chamber on the floor or on a pro-cables sh rizontal support structure which can be reached while standing on
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Q.d(in ecisture-proof p*astic bags.
tors are not installed imediately, seal the cable ends
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'"*j',? T..; equipment cabine,ts'. - Wiring and cables in wire ways must be protected toby fast 4.t,.
y.i.4./. y..: prevent moisture and contamination.
Before installing wiring and cables
- u. 9;.'-s.c;;in wire ways tnd conduits, nake cernin that all passages are free of meis-
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,.,j:.3,.2 and 3.5. '..%.
~3.2.3.8 After the cables are installed but before installing cable conne:-
tors,'reche:k the cable c:ndu:ter continuities and insulation resistan:es.
~ The insulation resistance of the conductor (s) and shield (s) must remain
,. satisfactory and frae of grounds.
See Referen:e 3.5.
Before ir. stalling u
..E the conne:ters' at the charcers and detectors, determine if special cofine:ter
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Consult Referen:e 3.3 and 3.4 G.g spe:ifications and data sheets as well as BWR e:uipment environmental require-
.w'ments in Reference J.26 for information covering the spe:ific application.
'..'fJ If the referen:e specifications ce n:t define equipmant environmental condi-
,4,,,. 7 Ntion limits,' consider these limits to be frem 32*F to 140*F (0 to 60'C) am-
. tv f. 3. b.ient temperature and 0 to 95 percent relative he?.idity.
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scint'illatioit detector are similar, the fo110 win 3 instructions Ng' -.dn, Pap' ply (t.o;all:three. installatinns, see Figures 3-1 through 3-4.
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12, $nspect the 'provided cable connector assemblies and water '
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These components-d ' i Mb@s'aFe"usuallf shippediseparately from the charbers and cablest
$@@M3:2!4!2' Confirmith~W'sthe? supplied connector asse
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[ pqreJc6mpi,tiblNwfthjthi"assigned cable. 'the charter or' detector and the cham-y bar.4 detec+or and: monitor hardware.; Trial fit the equipment to the appro-
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See Rn ference 3.2 elemen-
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-r 6ry; dia' grams. W.i..
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axial and' triaxial cable-end jackets, clean about.'
JU.[?M'*q./recove th'e f.the[ identification markinescable ja.cket surface with ethyl alcohol.. Do il 21;:1,nchei.,o Vf*%lh cable i
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These resistances must be acceptable.
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l i.p.,3 J.,in ConnectoCAsserbly-Instructions GEX 45754, first install the connectors p
b.,y. at the acr itorin y.:p'Q.? Carefully-}adnereg. equipment and at the containment penetration if any.
l tiij to,.the cable stripping, cutting, and cleaning procedures.
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M,NMT Instructions, GEX-45754.
Carefully clean the cable inner insulation and
'M ' W alcohol to remove graphite and other contaminants.
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'Frfb")%Yeonductor and shielded' conductor continuities through the connector are I
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9.3.2.4.7.8 Hand tighten each cable connector to the croper chamber connector
'q per.Referencetogether wi th -i.ts..lo. elementary drawings.
- 3. 2.
Record the chamber serial nu.ber cation and service.
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3.2.4.7.9 Confirm that the cable connector center conductor pin makes fir: '
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'.iy pg..;..1 S'(;rQT ^."Irmediately after heating, check that all the surfaces seal C C.)ro erly;'s;~ hen ii. sis,g. ace. tone, carefully remosa any excess epoxy ad
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monitoring equipment'. cable connectors as described in Step 3.2.4.
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With :the on. chaser ncw connected..the cable insulation resis-tance'betie~e;niconductor and shield may have changed.:but the 1..
s Jsi~gna1*' cable r'esistance should still exceed 1 x 1013 ohms and
~~thefHVicable}Fhistance should exceed 1 x 1010 ohms, cIf. cable w'.
W Ireliistances?liave' deteriorated significantly, inspect the cables
,yi foFJ*damaelT~e[s'p'ecially at their entry to the waterprooting adapter 2
g
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k asse 1y;whe,re heat damage would occur.
If necessary and before sealing adhesive has dried, disassemble the watar-h r @.te. [. h @i Q.the'adap,te
'kd p' roof,fngTt njF.* disconnect the' chaser cables and recheck'the" ' ' N ' %
f, Mo..'p. 6 cable!.Weilt*[the"cables a few inch'es ahead of the adapter cable, i
insul ion resistance. 'If the resistances remain unsatis-
- ~
g<.J5 'M fpsfact6r 3,
&['[ MMM tubes'.? Aftitry' obtaining satisfactery resistance measurem
" ~..
4.y i!!..'t above'.Y Thiittime apply less heat to the cables.
For additional k"...:f. 4:
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2 E.' info' rih'ationTeencernin'g installing chaders and cables in specific '
C'. : M.
9 pr32'e's'siradiation monitoring sy' stem applications, see Steps' :.4 f-
>l'..d, fMR@,. $gh7 3'. 8W '
! CG' i thro'u M
8Wd t-W 3.2:5.2 RadiationShTeldino.
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If$PD-r;,7 ?/.s.-..
I ' M@d32iSi1'..'B'e$mlieTU.fradiation monitoring system componen 8NS M
- PJ1M's'dethetors',',wiHny'o'~d' cabling, connectors, sample piping and filters are ah UdirectlyTexo'ssidit radioactive materials, special care and protection may
~
NNWbi'requifed to"redu'ce personal exposure to these radioactive mhterials or
.YP.Z e Also, cos t
'iUB.'.,k. to,' the eq"uipfent[ contaminated by these radioactive materials.
radiation chim6Er.and detector adient background radittien levels must be
&G.WiiiinimizedJin'ordeFto detect small radiation changes in the process sample W:3nf biin'gWiitor'ed.6To reduce undesirable radiation conditions,'all sample 67.*Wessel' integrities ~should be verified during equipment installation.
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$.';':c. ' 3.2; 5. 2 Several; process sample chaders are constructed to contain lead-shot 4 '.:J;l ;.. type shielding.Qn most cases, this shielding is not installed until after V."_.. the sample' chaderJ. installation and system testing is completed.However, A9. it'.is important that the' sample chader supports be constructed rigidly
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enough to' support.the total weight of the sample charcer as well as the m-requi, red shielding.,
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3.2. 5. 3 Detectors 'or' chambers not installed in shield type sample chambers
*? /.1may be shielded with lead bricks or sheets.
Use only nonradioactive
@ N..
shielding material, i.e. 99.8 percent pure virgin lead.
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- 3.2.5.4 The tiype Setecter or chader used and its viewing geometry, as well 9.<l
- . as the' locations and. intensities of anticipated background radiation sources
. ill determine th~e.. type, amount and arrangement of shielding materials, e.g.
4.0 <.
w
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, ;, scintillation detectors frequently require at least a 2-inch +h9U*
LIMERICK INTERN ALS INSTALLATIO M.....
PROJECT NO. LMI62
'I '
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duBCONTRACT NO. 803bFSC 202 I. n -
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EN E R AL e,E L.s CTRIC 22A4211 Q
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'"2i5'.5. All'. shielding materials must be self-supporting and not unduly laden ~
h i*:
thefchambeY;ithe' detector, the detector supports or the sampling vessel.
Hructural"s'u'pifrits'.". '.. - '
u-
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'"3:3EOMIN' STEAM LINE. RADIATION MONITORIN3 SYSTEM s
% 5 k;'Ecuiement T.SS: :.:.'Y.:.fV.
3j3;1V
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'This system. consists of the following major pieces of equipment, h 3.3.1.1
%;' R..gt.Vsee.Referencer 3ti':'.t.*C ' :
AM J4M W.W.iTGWN ~ ~
m.a?:N' l.'%'.'8%l2::f' M%% Chader WellD
.W
.h u,, s.::: ~ :..-~c
- Ga.ma Sensitiv.,Ioni:ation Chader 9.G :
p.
e
...1.
r.
' $c. i.5.e. I.
Q$,.%.n..!.F.i.. Loga.c.ithmic' Radiation Monitor and Alarn Trips r
..n..
au@i2..W,c.:A." Record.sr S,igria. l. Selector M
. v. v ; b - r c.?. s ~..HTwo Pen Strip Chart Recorder
.g.- x **...h#
3,
- ~.m' -
bt =
... pa.,,
.S 20cd/1:.@. 3.3.1'.2n The squipment is arranged in several separate instrument channels, "CfT@' ' h of %hich'coEpr.is'es part of the reactor protection system.
As such,
, M,- W;;$ eac the.insta11ation'of. this equipment must fully satisfy all safeguard require.
bit
- .,3.. gM.v. ::%.* ments concerning:' reliability, redundance and separation.
e Ion Chartiers 'a' d Chader Wells
';T '.. :*al.?. 't.3. 3. 2 n
s s., 3.:.. r>.c,
. w:.
?.'
3.3.2.1 Because the steam tunnel area is usually inaccetsible during reactor
~*
coeration to f acilitate charber servicing, it is recomendsd.tnat ion cham-m
~
?..F T*ber~a'cet:ss' ports and oversi:ed chader wells be installed through the ' steam
- tunnel shielding wall.
~
.-l.
2
.r
- 3.3. 2. 2 The turbin,e building erector must arrange the chanber locatiens or W.'" M wells so that each ion charber views all four steam lines with approximately
~
?!.#;.. i. the' same but alwafs the maximum possibl*, viewing area.
T.-. &.V' c,'.f;, -
- t..... r.
g: 5b-l/ 3.3 2.3 'Chader wells, if used, must be made large enough to contain the ion
.f;;"..? -
.' chamber when~ wrapped in a several-inch thick thermal and shock prctecting lQM.f.p g{adr of.; electric,al. insulation (fiberglass wool).
- a w u..
~
..n.
1.i.li W'3.3.2'.t The ' sealed 'end of the well nus t project into the steam tunnel area
.;-$[N,
. cnd.be supported'pr, the seismic requirements of the steam tunnel wall.
..:.v:
. 3
. ;5 %
12.' W,l'.
3.3. 2.5 J.vWt., cf bot @ durinpriac,end'of the well should be accessible for chamber removal, The o' pen tor; operation and shutdown.
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o L1M ER1CK IN7ERN ALS INSTA'.1.ATIOF j
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PROJECT NO.
LMi82 ir
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s
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SUDCONTR ACT NO. SO31 FSC 202
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... says*$ifNERAL ELECTRIC 22M2n lWp n.o m
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8Harr %.C 3-18
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m.]:<'m p!T;s =%,. Wy..
z
- ins M. y%.:.3','3.2787;foyetNeye[the chuber from the well, rigidly fasten a tcrperat i
"t.he"chantion. in'.4 th.'ela;to each chamber mounting assem resistant. pull-pole R 'E -
a h;j....,rp~.g. u-.s signed well., -f f' NOTE
,: f ',
fjhu Jm
.,/ p 2
n ull-polie;...
.O b. @ Thej %.,....
=
A@ case.-2T? -.>,]nht be electrically insulated from the chaser
.N,.., 9
.b,p. r d:v' ' v.. *..eje. i.'...
m,
... a. : e 3.3:.7.7 c Before. install..ing the chaser in the well, waterproof and wrap each
$e w
fc.had. er if th *pr i'd d th.ermal insulation.. No lead shielding i,s required. ' ".' t, '
',.-vVM.,.18/ 3 3 2 8 2 y. *. M.,
......,.c.e.....ov..y.e 4
n e !.: w.:~'u...
a
... Protect: alp. ion' chaser cables from thermal and moisture damage.-
yd.d.
ble length to accumulate inside the cha2er well.
M.\\7 i!,M.Do* no
- ~y&, p,.+,n *Y: t allow excess ca
- V s
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v v. n..-..o' ?.r' v,x~.t:.;..
T go y yg.
.n.g 3i3i2.*9^ Instal 19 protect. and separate chamber cables as described in
. 4.-dis u.
n
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Refer'esdesj'3:333i5?3.25.andStep3.2.'
. ' 'i '. W2.8' K%3 ANTS $
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. Ui':'.
- 1
- p!.gry, "3/3E3 6. Radiation [pMNdi' D
- . '
q.
. Monitor panel
4 GO.t, c.37.3'EEy...#
T..
/ t,:.
id?lN@'M3I3v1.TThe1 radiation;. monitors, recorder ~ and other equipment associated i/
Pjy+$
Mith"monitoiing.' steam line radiation are~ provided, panei mounted, for 1
5/@D'p!fdirect inst'allatib'n' in the ' assigned. control room lo-ation.
This panel
?.WJ
{b&9YMients. ' 7%M5+Y:3Kf$.Eddst be' bolted'in olace and supported in acc "I
r Wpp%A.MM.
V
...: i.:....7.tL-r M-3!3f3I2+A1122inteN668ections betweerF components must be, completed per Nkh.:N.R,efe.'rer'c'e'sM.2laddJ,3,.5 and as described in Step 3.2.
" ~
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NOTE
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e~ the monitoring system or any comoonent in the
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.. m..
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s yc 4:1v and
-lJ1 g.:.MIpQ6f,flgasTradiatiFn'.wi.11 vary depending ~ on' the plant (of i
yp.w. equipmentiill{]a'nts"with straight-through, no hold-up or gas cond ghf acilitiesT f P usually monitor off gas radiation levels only once.
Plants 02iners? sample hold-up and carbon bed filters will usually mont-
- @MhC.i. 'with rei
- 'fpWi- ".1Io][theToff ' gas.'Etwice', before and after the gas conditionin W.%s.pqgto;;simplifv:dese,rjbing the off gas radiation monitorin
%9#
zhj s e p;:ar a te d ' i n to# two7 ub sys tems :
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r LIMERICK INTERN ALS INSTALLATION
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- ' ' - 1, PROJCCT NO.
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e-Treatment Off Gas Radiation Monitoring Subsystem
... r.
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Q
?
7T.1%%?)WWV f 3.4*'2s pre-Treatment'Off Gas Radiation Monitorine Subsystem
- ^M'%,;. :'m:n.;ls pre-treatment or straight-through off gas radiation moni-
- v>. v...
3.4';2:1.J A' tjpica T
t'ori.n. g,.s.u.b.. system,w:cBnsi.st.s o.f. the fol. lowing major pieces of equipment:
~
.. if
- m ':. :.r; g., k. s. :.c~. -.
M Sampl
-i/
_ P.
- .e.ey (Pipe) Charter.
, 3;$,.. ~.t Ion;'Chambe.rp., y?";;'ll v.
1
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- r. wgn
.a w.y.&:.:.. w.-.4.*
s r
G..w.,.,#m'r-y:. / Sample Pane.l',.,containi.ng:.
.c a.wn n. e m....
- a_y'&y. 3 st.M:(.:.
n'.
fj$.Md@r:m..
Pressur'."an'd, flow. indicators'[ alarms, reIays, svitches','
e
.J.:..:
p.iping' a,n,d ' valving and sometimes the vial sampler equipment N
-Q,. :. 9.f
$Q ' '.be1 ow ~y;.'.?l' ' ' *
.,u y; 3.p.w;T:Vi a' re Panel: containing:,
u v.
~-
c% z "grap.m..li Sarrole.
..p...
m Vacu:um; m. n.:. pump? pressure gauge', switches, piping, valving and
.g.,;
-9 ijm *:
3%r.d. $fMr.p%.c...:.:saic l e'.v.a.y.'.l'.F ]_.4.iilsp >.
. a.
99yg W. q.8&rt.og':. Radiation: Monitor. with Alarms and Trips f H [Et.;
G.h T:.. e.
N.T!vy.I D.'"
%2,.T'.T-Fit:c 'lyC:WM[,.I. Strip)n.yw:.
Chart Recorder
~ 7-NC..
3'.4.2.2L Sample Chamber and Piping
. & % g;. & 7:
'%W$::E1-V.Q:
^
F L.% 3;4.2.2.1?:To: reduce radiation expesure from pre-treatment off gas samoles, M.C%fil'ocate-tt'e's' ample #charterrat an elevation above the tur ine steam jet air er;W.
M.S'YRf:]jector.'(SJAE)[,wherif thtlsarrele lines and charroer can be easily shielded
+:y,w$;.gi.th'.1 e a d ; wlz.wcr.n: ~;T.c.
. ; J f:-
t da:x/.,w.w.M..
.g $t3.'4t.2.2.2'..To' reduc'e r[adiation plate out and rnoisture build up in the sample yhf **R: lines and charte@[ mount' the charter vertically and slope the' inlet line
..: E k's.f continually, downh4 the SJ AE take-off point,
.7 e.:,
.. ~;,.m:,
?.
T... C 3.4 2.2.3.Both'cha,r..se,r.end flanges must remain accessible for sample line I..
.I' # connection and.r'emoval. The bottom flange as indicated on the Reference
_....Z.J.-; 3, 2. 8 d rawi ng mus.t. be d c.<n.
. ~...
The... le c$ art'er should be supported independently from the 3.4. 2. 2. 4 samp sample lines' ' Both the chamber and piping supports must satisfy seismic
- c..,c support requirements. Also, the charter and piping should not be used
- '. J.w ~. 7...~..wto support the required radiation shielding.
..w
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,~
q.;. }i'.y. 3.4. 2. 2. 5 Following Reference 3.1 diagram, connect the SJAE ~ discharge dg;4:.f; sample line to the:SJAE discharge 'line where it will pull a water-freeConnect the w
?g representative' gas'.'samle'.
p;s;..M valve to the bottom samle charter connection.
d. -... y -.
(hl;;h.
UM CRICK INTcRNALS INETA:.LArgog
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"no. seer no. i.y;,,,
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.$h SUBCONTRACT NO. c039.y DO 2M. L
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's I4 2:2.6'p/v.'4.&.fily...
4:.W.h.. s.L.c J
- n...
m Ifde'fe f to. reduce con'densate build-up at a sample line lowj.
p,.oint! ?ohdeia' ]ine chiller, condensate drain traps and/or. heat trace. ' -
.,. -. 2
'l 1
ndtinsul ate..th sample lines.
'.'.s'" -
5GT.%L 2 6 : ? R..'.
m
'2'.217, Install the; purge air entry three-way solenoid valve and connect.
' Tsa'm'p1'e'.11 n7p Ta1Way'J....cip'enTon,9tng between the sample cham
. "..+.:,:d the valves see References 3.1 and 3.6.
~
s 3.
2.2'.8E. Connecti, %...w.
n.e...
n u,..m...
the' purge air filter to the normally-closed, when de-i.7[ ue,,v.Q.g ;g..} port of'.the solenoid valve.
ener ized J
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n.:-
m
.y..:
%,T;,, y, f. '.9Ti-e- '
..: a
.v.
NOT-e
- J,...
-l
, %.ww.ywu....
w.-.. ;;
To redu....u.~..ce moisture 'bui1d-up in the charter, continue'to slope
.y.
., h..
t
.W w. -
OhEh,[d;h f.h.: y-
?. ::c _.;;g 9ff'hj.p';hth'e+11ne,downjr.d.away fr be Li fq possibl.e.; 3,.;
$w*,qr.c.
N,'.%3.4'.2~3",i?Q..:.3tg-Off Gas 1'SMnple Panel
' M.%yh*:
M.gu 6.l.. :
4:
'..;R W +l4 2.3.1 ; Remove' the1 panel shipping and storage protection and examine the 3
panel cceponents' and piping for da. ace and irregularities. See References
' - S?.M;; 3.9 and. 3.10s:' T.he sample"panel may not be 'c' nstructed as self-supporting; ~~
e
~
' - ~
.$..y,. 7..l3.thus, after. unpacking the panel, it; ediately provide support bracing.
/... -
..p ;:..q.
,7
-g*
.. -.f 3.4.2.3.2. Becau'se the' panel ecuipmen; must be accessible during nor-,a1 and
@'T d.(abnorral of.f gas. activity conditions, locate the panel outside potentially 12... p";# radioat.tive enclo~sures.
w
- w.
t
.e,;,.M 3.4.2.3.3. Bolt'the'. sample panel to the floor or a sturdy wall structure.
'~
".:W :.',P".This instal'latich%stisatisfy seismic requirements.
- v. ::,..
,g ix,3.#eA 70p flange outlet line to the off gas dQ.ig_3i4.2.3.4 ' Connect the sartple charter fpanel inlet connection.
M.1
- p. m....
'.'S;'l.3..,4.2.3.5 Wrap the inlet line with heat tracing wirs and insulation.
,b q.y ; 3. 4. 2. 3. 6 7.:.-.
Connect the appropriate sample return line tubing and valving i
. N.,,9."'.:
i,T ;--
.4between'.the sample.. panel outlet connection and the SJAE suction piping.
. Qyg*:y7
".Q.
r
.':14'.2.3.7. Install and connect all field wiring to the pane'f as indicated in.
m-
'?I-D.T' Q U iferences'3.2,.3.5 and 3.11.
.This wiring cust be identified. Also, Mfyi-J.plfthe' wiring must be checked for pr6p'er continuity and insulation resistance.
.gc ;; v. 7..
V3 :..-
NOTE.
%y g;-)..; t.,s. -4
..v
&* t'6i-J.:.w::;c.. Do. net energize the panel components at this time,
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- h.3..'o'h$f LIM ERICK INTL i tNSTALLATION
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,t, SUDCONTRACT No. 803bFSC 202 m..."...'
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. 2.-. 4',.'.O.f. f :, Ga s V.i,ill '. S.a mpl e. r -
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a
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n s
~
,$I.4h.3:4'.2.4.1..Ramovejthe'sa npler shipping and storage protection and exa
@f' f
d d irregularities. See Reference 3.12.
- if tn ".~ i lf < %'M.:
j'.fY&,.e sa np er., o.r.. amage an
~
n
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3:4.2.4.20LocatA Tsolenoid? valve'a,the sampler in an accessible area between the three-way"c'.
i ndtthe SJAE discharge ~ piping.
'E'W T'b7q?.'i'f
=
E Securely, bolt the sampler.to the floor in accordance with seismic' 4;
2.4.3
- 21. qui re'm(e ntsi?F '.W. e el 1
.. '.3
' 7 "'
~
- re
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.S.
7 i
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3
- [.%%Miiig'cle' sed:portini[samle line from the SJAE disch'arge pipe 2
the three-way solenoid valve.
.E
- 6k $ 5.% 0:G.'.4:?
'~'V PMM6.3,4;2.4.56 Tee-off.a ' branch sample line from the SJAE discharge sample line 9.e5g~Q-Ma'ppropriate' shutoff' valve-to the SAMPLE INLET connection on the,
yf fednhection' joint'; described in Step 3.4.2.4.4 above and connect 1 vial sampler.
v $ ! & @.boC yl, @?& W@h % & C
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43.4.2.4.69.Connectathe sampler box SAMPLE OUTLET connection via appropriate
%phrvi ' dto'[the': of fg'a s' pi pe' ' ( SJ AE : s e c ti o n ).
The sample air discharge pipi f.' */
y c8.@Wsample 'cHa'mbir.Itied into' it, see Reference 3.9.
n D -' k?
leading:toithe2SJAE.section pipe is'to have the discharge'from thejff gas-TW-
%q
~ ~ ~
N.
- J D'
- d5,YM$N "%W:$MW'ap$ ' 'propriate sampler purge bypass tubing, check valve.
- M 314:2.4.7M Connect the i
6'W.j.QWEd sh'dtoff%1Eb'eheen thu samplier box CONDENSER VACWM discharge' con-M.D5:#FnecticWand;the7SJAI. suction line..
U...Yt.QWVn. b*.% y:.,'........n.. c.m.
.y t
g.f e w sc.u 3q,2.4.89. Connect. alf. field wiring to the sampler a:, insicated in Reference 3.
3iWs?:0&N.2.2.18ecausei.the samoler controls are self-containe,', connecting ther-w *'
sampleripoweF Wdr 'sually is all' the wiring that is required.
~
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CAUTION
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- $6.L7 <;'. mation;co,ncerning preparing this pump for service. Consult thelp,0mp m NGI ff
- .L D.d:..
a
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Wyn,.7ttW MY.' sam'ler pump.'is not pre-installed on a panel, proceed as GW' F#!fithe' vial-p T,W.@ ' ' ~ -
KM ~.13. 4. 2 ~ 4. 9 2 : Re ove%hi.lample pump shipping and storage protection and examiye i,f$?.%#2Jthe 'p'umi for.;N@f ' m..
dainage and irregularities.
.dgl+.Wa /.M79 7.", W.<4 r
M n g.? Tv.i2.4.10. Obse'r e#
M*.;p 3". 4erify that'the~m the ptimp motor identification and name plate data and otor electrical requirements fit the application.
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LIM ERICK INTERN ALS INSTAL.LATION E I.'.bh PROJECT NO.
L M I.3 2
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SUBCONTR ACT NO. 8031.FSC.202
-l'
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- W 5 accessible 16-inch by 19-inch area on thed.W..
12! 11 i
'f1T>orY,a.2 Install.a.the. pump. n andja'c'ehtitojth'e', viali samplerepanel'.. T
- 2. I M-
' Mr'en'ces'.MirstMos.1, tion and install the four pump. frame shock mounts'(thesa f'.
6CKtf art. shibedfse'p'a'rately. from the' pumps); then," securely atta'ch the' W $
- ~ -
~ Tp'u'rWmotor. frame't' ?q.he' mounts.
dt
- r,.
- n..,.m. e. '. p.. y.g.
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s.w o.-.
m....
!4.2.4i12'T Connect,: the.provided pump' inlet hose to. the appropriate valve on
.P pr k
S
~
'tNe~linel / iee Reference 3.1.
r.,<.4.c m. w.+giq;pe.r. -
r 3'.4,/23.'134 Connect the' provided pum'p. outlet hose to a check valve.'and a
.M i;E 5..... g,.
~
- 7. '.Y - Y.;.G.... #.' 1 C'/:> ;
5 6ff.%al'v'eF6 MW';aNW w
9.".
M.-
s Qy%.4 2.4;14'E$.k.,$.7 ' ff valve to the off gas' pipe (SJAE suction).' :
fR$~E'@ 6nne,.ctt the. shuto
. <.< +..
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C
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93 w.n.s:.r ~, v. ; v.,.
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w.
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r w.
l 3 *.
4.156Af ter.linstiilling and connecting all saniple lines, samp er compo.
c No leakace is permissible._,
?..
,',QM@pf. Ken'ts'andftn,epsnW1eakitest the entire sys
<"...?..
6ii
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t
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...:b:w.4.s.<,.'l * * *,o 4 P. v. ~m.m,re.:
n
> * ~ j :-.
5 kt 3f4:2;5'.Sa e'.Charnr.JIon Charters '
&n p & n.g: mw...;
a RTtseioff gis?sai.. inspecting'and testing the. ten charbers to b w
' c" 1
,3j4. 2.5.15,Af tednp1Mhanter.. connect and waterproof each chader as'de-
- t c:
W W ' F rib ~ediin'Stepl3f2':4.
- J...
1 W W...
.;k Q m..< y:
,9' : W.y p....,.s ~ n.
v :- -
.s ~,t. d3.4 2.5.2r Using..i'nsulation tape or a 5 racket, attach the ion chartier to the r
1:v =-(
Orient tr.e ion chacer ver m';q Yoit' side iu'rface'ofd.he off gas' sample chamber.
M#&T.kti*ca11y'with',th~ effable' connectors pointed dcwn.
1 M Q~i..A m mig, dg#4'3.'4.2.5.3GIfijdre.than one ion chader is installed, positien the chamcers. -
~
.:6f. M/ radially a"round th'e75anple chanter'so that each ion chader views a;;rexi-c..Sg j; niately an' ' equal.7 s'asple chader srea with the mininum of viewing aiea overlap.
. ' 1;.-y. ~' ' '
lQSq '.did.*L s.. :.
?. W%Q.3:4.31 Pest-Trent. ment Off Gas Radiatien Monitorine Subsystem wi
- ..7:;.z.
i lipos t
t Mf gas rac'iation monitoring subsystem con-
.'; g iu y. ~,...@d.q,.(3:4';3.1. A typ ca. f.;>.-m. 2 ? sis ng majer. idaces cf e'culpment:
- ?.
1,,%;- n s..,.,
- f. W.."f. f,'.W. 5a@ e, a, n.e.li c.entsi ning : Pressure' and' flow indicators, sh
^'
p 3,%.14.i1 tion: eneck"s'ources, scintillation or GM detectors, pulse pre-W *,'
amplifiers, vacuum pumps, alarms and switches; piping and
- 3 valving
~
r;,.
Vial Sampler. Panel containing:,
%. Ed.
'-l.' } -DM.[.'3..k;'i.. pressure.l.i.n.dicator, vacuum pump, switches,
'^
& c -;
and sample vials '
.&;;-th., % *r
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LIMERICK INTERN ALS INSTALLATION T.* Q.
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- .m PROJECT NO. L M I.0 2 K((s5M.$hiY.,
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a F ;...~..,.,. c %o-v...
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Pro.ces.s*te w.y.on Honitors. log count rate meters and alarm...
s W
Radiati g..
e
.c. v
..n
,.y..5::
uLg.fW Tr.i.p" Auxiliary? Units m,s.%.f.;'.p c....w.g hart; Recorder.
1
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Stri C '.
- p~t TheTaboit...s.w!.w.m,f similar to but not identical with the pre-treatment ' '
equ.ipnie,ntTi However, many requirements: and'.
"yfgjas7 mop,itorfn'g'",'s'u6 system equipment.. methods!c'dnc7irni'ng insta1
..n.., n..y.
r...-
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g;kh,.3.4.3.
( Post-Treatment Off Gas Sample Panel 3
ej
.Mb NM*,'M,fid '..
2 %.43.4.3.2.1J. Remove the panel shipping and storage protection and examine the ' '
Q
(.? y;W.Jpahel componentsifo'r damage.or. irregularities.
.T:
v..h y:.
r.: g.ll.
- #M.^.3.4.3.2.3 c Insta11' the panel. adjacent 'to the carbon bed filter discharge downstream.'of tne carbon bed isolation valve. The p'anel must
.&<'v:Epiping,lo.c._a.t.e.d'.in..an.; inaccessible are.a or a potential high radiation N'Nm.-.be.
d %.S.'/r rf.ot.!
. d i.
- s.. 'T,W,..
JcyN.;}rWY.Lk'h'~,F'j,'. g a r e a.'/.,M ' y.
, &l.~' -
Bolt the. panel to the floor 'and supply any additional panel sup '
fk'y'.
e
.i p.i.3. 2.3 sorts.necessary to s.atisfy seismic requiremnts.
3.4
. m; p:f..e n,9:~.-
%7
.c y.
.r Connect an'd'. leak test the panel sample lines and valves including
.y
..$W.*I3'M3.'2.4 i
2 @.r. % d min and' purge. tines.
e
,c.d. ; *' :"' '3.6.3.2.5, Insta11' and connect all field wiring to the panel as indicated inAlso, the wiring
- W
- Ql References 3.2.and 3.5.
The wiring must be identified.
%@1 V.
.}',$Tecntinuity and insulation resistances must be checked.
f
. # $. W s '.>r.c,:. ;.. J., 1 l ff
..... ?.O 4'.3.3 The Post-Traktment Off Gr.s Vial Sampler 7.fM l
M5
<h.c..m..'f., ; :.; ~
' f.
Con'sult the pumo manufacturer's instruction m.anual for informa-s
- t ';.(!4 J.:
l for service.
.';,%.L tion concerning preparing the samp er pump
-A.-
f.
? :: 3.4.3.3.1 The post-treatment off gas vial samole* is installed similar to.
I
- e. o e :
3.4.2.4..
I
}@&. c',,,;the, pre-treatment off gas vial sampler described in Step 1 ;
4.'3.4.3.3.2!.l.Insts11.the sampler panel adjacent to the post-treatment off gas a...
..}
'.'.d.c (a,W. sample rack. A.,:9 s
.. ~; a.y i.g.
Q,ConnectJnd. leak test the sampler panel sample lines.
.a. W Q,. v.. 2,
%[f%.,}.3.d333 ?.-
?T 3.4.3.3.4 4 Insta11/and connect the field wiring to the panel per References dNg..w. e c P Q '.lWS 3 2 J and 3. 5.'. '. ~.. '
d n:w'
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LIMERICK INTCRN ALS INSTILLATION A-iME.%iv
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hfi,${.%.. (W.-.?..
PROJECT No. Lyi,8 2.,..'
- Qfq, 3.4; sUBCONTR ACT, NO. 80st.FSC 202 e =*&.3
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M3 48 Radiation Monitor panel 1QW4:&9:.,.
m. ;. s.c.~. :.'
y wi 3' 7 EThist.instri; ment panel contains the pre-and post-treatment radiation tr.h.44'.1inini'tirs? alarm'. trip ~JUnits and the strip chart recorders.
The panel is.
7 fp~.Ruhlly.installedsinithe ein plant control room, similar. to other control.
Tro'om'paneli# Adeqiiate. seismic rated panel floor supports must be' provided,
^
~
9 :@4;%r.A 'f.oi. the'.'. pan'e1MM:%. '$3.4i4'.21 Insta1
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- ' 1. '..S t.wr.w.- n..,.n.m' VENT PIPE (STACK) RADIATION MONITORING SYSTEM D.F0FF.GASf.
~
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.W' v A.;h.%w.n:V.v.rC.,w.. w~.s s.s& W W Mr s A...
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NOTE w Va.Mii. fr$p::v.s...
m r
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w V:p..y
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3 rious' plant ventilat. ion system gases, such as gases from the
- d. O.
Uliiptiinal Ra$ast'"Building Vent System Purification Building e
~
k b.VenP Sist'enr,%T0rbine Building. Vent System, turbine generator:
-ce -
9 k.. W '
~
~ '. '....
ya. iaipment jentWa'nd the gland seal and condenser vacuum pum 7, f, e.C/ 4<
eq t-esp,he,rie. discharge, gases may be. monitored by independent.
4tp 9thise!sy[sie^ttedng systemsr Except for the isokinetic probe.
H.
m.-
goff.:gastren T*,j.,
ns'#us'e. equipment' identical, to the'off gas;"vent pipe
. +.
"i.;
3 w d.iation%iinitoring'equ.ipment'.and shouM be installed similarly...
- ri
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' t*p(.f.. by.c.&.h..o,c.)wv, ~ w.
":o M~S t 1*.* Ecui eme nti.M.e,.1...%:c 1.su.,%.SdObh.$
.. d..
3.
,l d';
I v 3.5d.t:A' M8,f.OI'it 1s':;.typicalf off. gas ' vent pipe oF. ' tack gas s
calle'd'at'p~lants with laree ventilation stacks, consists of the -
w D.e[.
4 b
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M f o.1.1.i.w.i.n.'g %.i j o'.r7...p'i e c. e s o f e qu i pme n hf e
c; e GM'%g? *.fc/G, e '.
~.
p.
v',
. yiC,. ' m ;.. Isokinetic;Sarole Probe w ~ me..c - ~ -.
r
% W. Blank Assently. fo,r Calibratien Filter Installation 4 g,791;;.,e?.c
+.2 &:.w OffAas< Vent Pips (Stack) Sample Panel centaining:
- 1..:~.e.n..
s
%h-< e, v? M :., 2 Z:';.tJ W"< WC,.
]andpanel r
i 6.xc,7..r wyy, epi. d..<. c.
Particulate.and. Halogen Filters (vent pipe [ stack w~
f ;i ttis i r. c 4 <,
gp m c,'y k.f?;g c. d. y.p....
TA Jyhe.igr'.CShieldet Sar.ple Charters
. SiiintillaIion' or*GM Tube Detectors f.%. 7.L'hhMF '.Ra'diition~ Check Source Vacuum PUEos~J 94/jtyW.9%.0,.. Pres'shreX Flow Indicators and Switches NMr7 l.
~
W 9'%?ha.
M.M
.; Timers (Relays and Switches
- 4. l. d '
S Flo# Control; Station U g.t E ' * %cp.. -W Pi pi n'g7aiid'.L.aVal vi ng"-
m..
Ndj.gj m.u... pa.-2
- s..
}p.gMn..D...e Log. Radiation Monito.r and Alarms W catcic 'NTERN ALS INSTALL.
i
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~n v,..s,:.-e..z.-
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gy'p:<'. :.;2 d.W.:gg$.*.:y'r6. -4 g ha.rt Recirder. '
'7... Strip C i'
t PRCi.IECT NO.
L M I. 8 2. '.
k.M Q.).., '1
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);
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SUBCONTR ACT Nb.' 8031*FSC 202 l
NMf
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%.yg;.4,%*eY,51.'Wlk.ME, * '.'
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sic
.8
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u 13.'5'.?:!_s_okinetic Sample probe and Blank Asserbly Y'
L.. ^
pmC&%.T?LW:D ^~3 specifications References.-
3.'1'. and.,.: C '.
- g' Fo11cWing
- Reference. 3.
- '.dii'g' rims:aM/Epp.11 cable plant equipinent layout drawings,, inst
.3 '. 5
../
t e is.okfnetiFp7 rob'e'M.~nithe'off gasNent. pipe' (suck).
3?
s
.w
.s wa.
,. - :. u.,..
diameters above'Theprob 76
$ sit on[h[wp$b'e Yt' least Sen v'ent pipe
- 4 stack 3;5 2>.2$[fiaF'disch'aige point'inside the ve'nt pipe
.S.E P
stack.-
Rf Wl'?
sM.pTe%el1T'mised;)ases.represe7.tative of the gases being released from :', '
1
~~
k
) y tt W ? M W('21 % Q ]am.a.ith'e'.Yant'* pipe' stack)>into th 2.N -
pling no::le tips so the mixed vent pipe (stack) -
.;s probe.s ir.^f:w.3.5* 2.3: Orient the:fe? probe: directly from below the prebe and at 'approxi-b
- Wgas es,' wille enterjt
' *^
~
' P,.
~ ?-M,M nisly the's'a'me:v'16ci.ty,'as i.he gas [ flow'ir. the vent 7:.'
4
,. 5 e
@hP M*;MM88$'C -
').53.5f@2.4~. The(probe 'and'the sheple line blank asse21y p f'~
/
G, l
[. t g[ffl.?the ye'n'Iy,ipe((sth'ck)V3. < 6 '.
i 7,
I
.y, grit of 8 % Q +5".' h ' M I S
.ri -
M'UbWN(5.2.5.Insta11i'the+1ank-tube assembly or filter (see Reference.3.7)' in Hd.Mthifs' amp.16111Ee itfor' b'eleV the probe elevation but as c yM3.
l'(@%i/N4.TsTpossibli:
- M$hd.tting'i1Q.FeF eji,W.removali use flexible connecting sample lines at eacn
d
' ;p wmrend of.th'e blank assedly.
- r' 2
M'.
Q}%e M39.2.6$M*.ic.' *1.,dF': robe Egilter er blank assembly accessibility 2
For?
.Qi.g;.,k.,rfic' cess decirp'can bednstalled in the vent pipe (stack) wall.
If this is
~
d h
't ipe V.N;E(' stack)2.fthen.icute the sample line out to the assembly.M/E
^
. ~ '
dh..f 7,4.p., rk.3(5.,jk.samole1.in[sk;7
, ^
am:nt.:*.%r; ;
.. r: a....n, J
~
- ~
l To minimize' moisture condensation, radioactive particulate build-uc-
., y, w
i sample lines, install the lines ver-.. ' *
.- W:
3 '. 5'. 3.1
.fi:W vfa'nd' plate' out iiiside the vent p pe gasU.;%C.tically. and if' pei'sible, ccmp
..d:.
i to the base of the vent pipe er. stack.
W;.t
' l<
.p-.ch)r.:blankassembly,connecton drain trap at the sample line low peint gf: ~ ?,.:Q ~. q'f; ~ '
.~
.Ad2,;~;+'p3L5.3 2 S, ns tal,1;a moistu. ek side th,e bas.e efl,,the vent pipe (stac r
r
.. - q: g, ri c
a,:
y.
c,...
,V cyr,3 5.3.3.. After. the sample lines leave the icw point meisture trap, the lines ~
- w..--
e t-should slope continually upward to the vent pipe (stack) sample panel.
My,'/u 3
.ek
' r Y, ". n f:
.r;, h5.3 4... A11 sample lines subject to excessive cecling, especially where execsed to the weather, must be wrapped with electrical heat tracing
..?p
. o,',
.%e.W:.M, e,.therral, ins,ulation and a waterprcof f acket.
W' W:'i m LnsgmggK,H%NALc N Q.v.33.. f -
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p g O.;E C T N O hTP'
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. ELECTRIC. :4 22A4211
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..~
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.c.
bing with F.
a.*
y6
....c DW1eas't!.1[0'058D'ne'h'wallethickness'. '. smooth ID stainless
, "5r3:54A11i samp1 Qines.must be 1 inch.
r
'3.
h0'ns7wh'erever'p'ossib1*'hIfc the tubing' is. bent, all bend surfaces mst be -
e
- i..
~
4 smioOFtdu'ghohuftfe' besd 'and bend-radii. must exceed 20 inches.
~
' +, 1 <. i.
hn'RV4WT's)'.(Vent Pioe Samole Panel
.C itM
- n 'P,2;.-;,D.jt' '
?375/4j:30ffaGa
%Q3w:2 5p " p.u. o +
&:514[14'o,,Tolmaxiln:izejpartic:ulate and halogen gas trapping at 6
f.,. '...
panelt..
,3 0
wqc sr.w.a. :u. O,. v e n t,.p,.,
.. s..t a c k ) b a s e k#.p s_ee.pa_'ne1%..l.o.i '*' tisivent pip
%':~andjt
....:...*.9
.h.
.2 s area... n..e.a r., the a.t_e; t.ipe. (. -
t c.
~
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s
.. - - s
' e ",
L'
~-
. e.
.m y.
- -3.5.4';2
- L.ocateithe!, sample panel in a heated ard well ventilated buildir.g..
- N.. '.
~
Pf; Position'.it'where.there'is adequate clearance to ope
~
-E eu fy
..n
,41.. s.f.... i..., sg; t-
.l.p7 g. +.
. 3.i.: q.
~y.....;..
- z. s r3~.'5'.4.3u. Connect and, pressure test all sample lines, fittings, and panel N
.?p..a-d See E-7.,duipmint to' 1!1/2 tires operating pressures or at least to 5 p P
i@:Th'e< panel':equipme~nt? and 'a11 sample line piping must be leak tight.
p 4.v
.:.2,y.. c..s.v
.;g.
4 C M ION y..
i ~ Y'1U9' $p;.:.
%@ Co:not press'Urize glass indicaror filters above 5 psig.
,,.7
+9 L
W.' * -
W.W,
J 63.5'.4^.41 While alllecuipment and piping must be adecuately supported per J.;. seismic, requirements, the piping supports must allow f6r ther.a1 expan-2 sion. v....: af'..
. +.....
b-Install,'-test and connect the electrical wiring to the sample panel C3 :.:.-
63.5.'4.5 bWuipment'.in' accordance with the appropriate wiring specifications and k'idrawings;.T See' References 3.2, 3.5, 3.22 end 3.25.
- .wg;,
..- c :...,.g. e NOTg
, p-a - : ^ (
., j ?.pp
,..:. w.-..
f..
. :7.,.nThe panel installed vacuum pump may recuire preoperatier.a1
... s -
".' ;f.1 A servicingD Consult ~ the pump manuf acturer's ins *t uction glA - manual' f.or t..hi.s information.
- .1... 1... 1
- 3..,. ;;
u..
?< 3.5.5, Radiation Fbnitor O':M."..
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"3.5.5.1.' Verify.thatsthe radiation menitor and the associated vent. pipe k
in the control reem are ins,talled in the i.
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E.g'*3J.JREACTOR'. BUILDING VEHTILATION EXHAUST PLENUM AND CARBON BED: VAULT.RADIA4, W.[ MONITORING
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wphannils, eacEofdhich'is'similar to an area radiation monitor. (ARM)
't 4i - ati on.co.ntent3 of, various reactor building ventilation inlet and exhaust..
Eac.h instrument channel measures 'the1
,- 4' pMy.radi.n'el.'.*.d. e._r.4.1 b e..'d.Fi.'n. 5. ec ti o n 4 fyyi..h.'.E 5
a.;gduhss'a'ndithe'iirbiin bed vault at ciphere gases prior to their disCnarge '
- .Wbntoithe7e~iictYr7 building vent pipe. Because the rnitoring channels pro-
$'.7 -?fif.v'ide re' actor.~v'ent'ilation system and standby gas treatment system opyttien 1 d;'dtlips', 'th'e.Tequfpme.p.must satisfy all ventilaticn sysdem operating and - -
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. c..m w;;%. pc..-;9g.$..
4, Indicator;and Trip Unit w-y,.u. q a..= '. owc.' Supp %y,w.
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- c. 7c:.t;...:gm Auxil.iary[, Unit (Carbon Bed Vault Monitor only)
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!.Sc.h@M; adja' cent to the"isel'ected to monitor any two individual channel Q
channel indicator trip units in the ecntrol room.' The
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ious. sensor, converter units and auxiliary, units are WTA M..
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t67ednect the sensor: converter units to the f ndicator. tripM-rou
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ly markedr The.iouting and separation. of the.. a
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revide sturdy mounting supports for each sensor converter atd on t
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- v i.,.p,W. 3;7.5.1. Verify that7the identification' and location of each indicator trip
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'the,', pr,.d.,.vi.'ded control room panel are correct.
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KMe.LGer.ify:that.the?sens'er: converter unit is compatible with. th
@bD@k'Oc@y~l1< cabling"and% iring between units
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See Reference 3.1.
4.. e n g.: n'eTrlysi WAM.Wr..: cal dentic'a1.P..a.d.i..st.i.e'n. nonitorin. g channe channels." are :-
Typj : M ':N:.h4 if ":
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3.3;2hThe. liquid w,ar...fo.w.W, llf assedly weighs appr3xim.itely 1100 pounds 4.'When?!
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If cessible, the detector
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It may'.be. desirable to install the lead shot in the liquid well M.. J.
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Joseph W.
Moon EDUCATION 1970 Graduated Bordentown Military Istitute, Bordentown, N. J.
1975 Graduated Ursinus College, Collegeville, Pa.*
- B. S. Degree in Biological Sci 6nce 1977 Brookhaven National Laboratory, Upton, Long Island, N. Y.
Health Physics Tellowship. (E.R.D.A.)
1980 Graduated Rutgers University, New Brunswick, N. J.
M. S. Degree an Radiation Science WORK EXPERIENCE 1986 to Philade.phia Electric Company Present Special Projects Physicist.
Developed Field Isotopic Analysis system for E-Plan using intrinsic Dermaninium Detector and Multichannel Analyzer.
Developed Operation Procedures and incorporated system into E-Plan.
Succecsful demonstration of fully operational system during practice drill.
Conducted training of HP technicians on system.
Managed Contamination Control Program and upgrade system of area tracsing to include waste generation figures for 4
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.
Rewr'te procedure controlling Instrument o
Calibration requirements.
Implemented changes to program.
Assessment of new instrument types.
Obtained recertification of instrument Calibration Source. Wrote Operation Procedures for Alarming Desimeters, Continuous Air Monitors and Underwater Radiation Monitoring Program.
Implemented Engineering Controls for Drywell while Purge System inoperab1v.
Layout of Outage Exposure control Points.
Implemented Station Radiological Deficiency Tracking Program.
Tiaure 2.1.3-1 f(d g, en j
f.
1984-1986 Radi.ogical Engincoring Ccnsul' at et Polo Vorde Nuclear Generating Station 1982-1986 Corporate Health Physicist at Humanco Inc., Rhode Island 1984 Radiological Engineering Consultant to Morrison-Knudsen at Point Beach Steam Generator Replacement Projcet Special Consultant to Duke Power Co., Mc Guire Sta'; ion 1983 Radiological Engineer on plant etaff 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 Tunctioned 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 2 ion Generating Station ALARA Coordinator at Millstone Point Unit 1 Decontamination Toreman at Surry Station, Steam Generator Replacement Project 1978 Sr. Heelth Physics Technician at Zion Generating Station 1977 Health Physicist at Millstone Point Professional Affiliations:
Health Physics Society; American Nuclear Society Tigure 2.1.3-2
Marth6
,astinsicnD t
lATION Rutger's University, New Brunswick, NJ MS Radiation Science /Bealth Physics Course Work Completed Thesis Working f
1 Georgian Court College, Lakewood, NJ l
t SS Physics, minor Chemistry Certified to teach Physical Sciences, Grades (K-12) l
!N!NG r
b i
7 Adv. Respiratory Protection (2 d): by Radiation Safety Associates, Inc.
J 36 Reta Dosimetry (2 d), by Sid Porter Consultants, Inc.
]
5 Air Sampling Techniques & Program Validation (2 d):
by Technical Management Services Inc.
l I
PBAPS Offsite Dose Assessment Ccmputer Model (1 d);
1 j
6 by Impell f
85 Dupont Safety Training (3 d): by PEco Nuclear Profes;ior.a1 Training (MUPRO) (3 wks); by j
5 aff j
PECo f5 RMMS Troubleshooting & Data Base (2 d); by Spectrum RMS I
5 RMN.S Circuit Boards & Calibration (2 d) by Spectrum RMS Fitness for Duty (1 d); by PEco/NTS I
5 RMMS Gen. Overview for MCR Operators (1/2 d): by r
i 5
t Spectrum RMS 5
RMMS Gen. Overview (2 d): by Spectrum RMS d
i
)
Radwaste Regulatory Awareness (4 d): by Chem
'84 Nuclear I
Medical and Legal Aspects of Radiation Induced 4B 4 Cancer (3 d) by University of Pennsylvania and l
RMC/ canberra.
14 PEA Nuclear Subcommittee Meeting (2 d): by PA Power G.eneration Committee.;
I Disposal of Low Level Radioactive Wastes (2 d): by 4
i
'83 l
Penn State University.
i rigure 2.1.3-3 I
l 4
4 i
9
Martha A. Christinalar i
Chemistry (Corp. rep): developed HP/QA audits and continuing education lesson plans for staff.
l 6/82 to Health Physicist-Brookhaven National Lab, Upton, NY 8/82 Internship provided training in HP/IN instrumentation, emergency response, dosimetry and respiratory protection.
c,*
\\
Directly responsible for determining neutron spractral distribution 4 National Synchrotron Light I
Source for PSAA submittal.
1/81 to Student teacher - Erick Twp. H.
S.,
Ericktown, N. J.
5/81 Physics (Seniors) & Chemistry (Juniors) j 6/80 tc Tutor / Counselor - Upward Bound Program 8/80 at Georgian Court College.
High school math and science.
Professional Affili<tions i
1.
Health Physic Society l
2.
American Nuclear Society I
3.
PA Department of Envir. Resources-BRP HP call-out list.
?
i l
l I
f I
Tigure 2.1.3-5 r
I
gh3E:
Stcph n L. Tayler
[
l 1,UCATION AND TRAINING D
1977 Red Lion Area Senior Nigh i
1983 Philadelphia Electric Company Nealth Physics and Chemistry Assistant Technician t
through A Technician l
Radwaste Quality Control Inspector ISI Ultrasonic Inspector
(
i ei General Physics - Mitigation of Core Damage i
Chem Nuclear - Regulatory Awareness Radioactive Waste
}
Packaging, Transportation and Disposal i
1985 Philadelphia r)actric Company Nuclear Professional'
, ming i
1986 Philadelphia El...ric Company Management Developr. int Program t
Time Management Training Writing Than Can Be Understood i
Kepner Tregoe-Resolving Concerns Through Rational Process 1987 Philadelphia Electric Compan continuing
- Training Advanced Respiratory Protect.on Porter Associates-Beta Dosimetry Training I
I WORK EXPERIENCE f
l t
l 12/84-Present Nealth Physics Technical Assistant - Plant ALARA, i
Limerick Generating Station Duties:
[
(
l.
General ALARA Responsibilities j
A.
Identifying areas where exposure can be reduced B.
Pre-planning and reviewing activities which have r
high potential exposures j
C.. Providing technical assistance and guidance for on-site gsoups to ensare ALARA effectiveness D.
Evaluating proced.res and methods for completing jobs with einimum interference while maintaining exposures ALARA Figure 2.1.3-6 I
I 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 work 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.
Develop!ng 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 i
3.
Specific First Refueling Outage A.
Refuel Floor Area Coordinator for first refuel I
activities B.
Assisted in development of an office enclosure utilized on the Refuel Floor j
C.
Review of Refuel Maintenance Procedures to ensure appropriate guidance is included to control the j
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 I
minimize worker exposures Figure 2.1.3-7 i
i-
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 1
3.
Operations HP - Duties on backshifts responsible for RP coverace in the plant.
Work directly for operating shift supervision (trained in emergency procedures) interim personnel safety team leader on backshifts 4.
Health Physics Crawleader of control points during following jobs:
A.
Refuel Floor 1.
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, chrink fit of new spargers and installation 7
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 I
1.
Breaching systems, removing mirror t
insulation, perform internal heat stress of welds, clad overlay on RHR-recirc P ping i
6/80-3/81 Peach Bottom Atomic Power Station Technician "C" Perform surveys, provide HP coverage, system l
breaches, unrestricted release of tools / equipment t
l Duties:
1 Specific Responsibilities include:
1.
Providing HP coverage for first feedwater sparger replacement,1.1.3-6 "per f orming invessel n,,,..
surveys, monitoring worker doses, surveying tools and equipment
~
2.
Providing HP coverage for Torus Proper Modification, draining decon of Torus Proper, open sand-blasting of Torus, welding new supports 3.
Performing non outage coverage of piping support modifications in the Torus Room, Residual Heat Removal Rooms and Core Spray Rooms 3/79-6/80 Peach Bottom Atomic Power Station Assistant Technician - Duties:
Routine surveys, in-plant training, provide HP coverage Specific respor.sibilities 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 l
t l
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l 1
l Figure 2.1.3-9 '
NAME:
Rob 3rt E. L.dy.
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 Series "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 4/84 - Present Philadelphia Electric Company Responsibilities:
developing the ALARA program, procedures and guidelines; developing techniques to evaluate the effectiveness of the ALARA program; reviewing engineering or design changes to epsure 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.
4 Tigure 2.1.3-10
6/82 - 7/83 As
- ican ElGctric Powar S3rvi, Corp.
Responsibilities:
providing corporate technical support for a two-unit PRR, 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 Responsibilities:
&ssisting 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.
t t
i Figure 2.1.3-11 l
NAME:
Clark D. I th EDUCATION AND TRAINING 1975 Kennard-Dale.High School-College Prep 1975 Millersville State College-Six semert'ers 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 techniquec, radivactive waste, and chemistry theory and J aboratores.
8/79 - 12/83 Periodic ir, depth classroom training by PECo in both health physics and chemistry totaling 726 hours0.0084 days <br />0.202 hours <br />0.0012 weeks <br />2.76243e-4 months <br />.
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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3/85 Radon Survey Techniques - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 9/86 Problem Solving and Decision Making (Kepner Tregoe) - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
Figure 2.1.3-12 4
1/87 B
1 Dosicatry Workchop - 15 urs 6/87 Advanced Respiratory Protection - 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 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.
Develop and supervise the program controlling use and accountability of temporary shielding, providing calculations and other shielding technical 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.
r
/
Figure 2.1.3- )
WORK EXPERIENCE 12/83-6/84 Health Physics Technician "A"-Limerick Generating Station Duties:
Filled job of Technical Assistant.
Worked towards set-up of training program.
Wrote and reviewed procedores.
Approved various procedures as a PORC member.
Worked toward acquisition of contracts for personnel, services, and equipment.
Approved purchases of equipment and supplies as needed to set up the health physics program.
Helped set up Emergency Preparedness Plan and served as the Evacuee control and Vehicle Decontamination Group Leader du-ing 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:
1 Initi,al, Breach, and RWP update surveys.
Job coverage and suTveys as assigned including all areas of the plant.
7/79-6/80 Health Physics Assistant Technician-PBAPfi i
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, Meist Separators Area, etc.
Tigure 2.1.3-14 l
l
J SENIOR HEALTH PHYSICIST DATE APPOINTED:
Jant try 1984 i
NAME:
Richard W. Dubiel 1
EDUCATION AND TRAINING
)
1971 Georgia Institute of Technology, Atlanta, Georgia
[
Master of Science Nuclear Engineering i
1970 Fairfield University, Fairfield, Connecticut 4
i Bachelor of Science i
Physics
[
l t
WORK EXPERIENCE 1/84 to Senior Health Physicist / RPM /RSO-Limerick i
Present Generating Station
^
i 1.
Responsibile for the implementation of the Radiation Protection Program at Limerick Generating Station.
2.
Provides administrative and technical I
f direction to the health physics staff in J
E the areas of Dosimetry and Bioassay, Respiratory Protection, ALARA Program implementation, Radioactive Waste t
l packaging, classi*fication and shipping, Radioactive Effluent monitoring, and
[
Radiation Monitoring Instrument i
Calibration and use.
l l
3.
Serves as a member of the Plant i
Operations Review Committee.
]
l 4.
Oversees the development and i.
implementation of training for Health l
Physics professionals and Technicians.
[
12/82 to 1/84 Professional Services Division Nuclear Support Fervices. Inc., Hershey, PA i
I
[
l l
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Figure t
2.1.3-15 1
i
Involved in the marketing, sales, and project management aspects of the division.
1.
Specific services include the areas of professional health physics services, emergency planning services, chemistry services and training services, primarily to the commercial nuclear industry.
10/81 to 12/82 Senior Planner, Emergency Consultant, Inc.,
Harrisburg, PA On-site Emergency Planning GroJp 1
1.
Supervised the activities of the Emergency Planning Specialists in support of the full spectrum of emergency planning services to fixed nuclear facilities.
2.
Developed emergency plans implementing procedures and training programs to meet the current regulatory requirements.
3.
Developed scenarios and conducted drills and exercises to ensure workable emergency plans.
4.
Evaluated the performance of the on-site emergency planning staff in their support of programs being provided to f
nuclear facilities, 5.
' Assigned emergency planning specialists fo specific tasks as necessary to support client requirements.
6.
Provided technical assistance in the areas of health physics and nuclear engin~eering to another group within the company.
7.
Personally developed and presented training programs for dose assessment personnel, on-site health physics personnel, emergency directors, and emergency coordinators during accident situations.
Tigure 2.1.3-16
9/74 to 10/81 Radiological Engineering Manager - Assigned following the Post-Accident Reorganization 1.
Responsible for the ALARA program, effluent monitoring, i n-plah't radiation monitoring, respiratory protection program, technician training program, GET program and rad' nuclear training Course Content.
2.
Responsible for rewriting all health physics related procedures to make them applicable to a single unit and close out of all audit findings resulting from the accident investigation and subsecuent inspections.
Supervisor - Radiation Protection and Chemistry for the Two Unit Nuclear Stations (Station RPM) at TMI Responsible for all aspects of the health physics, chemistry, radwaste, and industrial waste programs, including:
ALARA,' internal and external dosimetry, respiratory protection, effluent ronitoring, h2alth physics field operations, radwaste packaging and shipping, radiochemistry, lab chemistry, plant chemistry, chemistry control, industrial waste plant operations, and monitoring in accordance with the station NPDES.
1.
Managed a staff of 40 full-time professional technical and clerical personnel'.
2.
Full health physics responsibilities during four refueling outages (TMI-I).
3.
Startup and test responsibilities for health physics and chemistry (TMI-II).
4.
Startup and test responsibilities for the station industrial waste treatment system to accommodate both units.
5.
Upgrading of the TMI-I emergency plan and procedures to incorporate the second unit.
Figure 2.1.3-17
?
6.
Implementation of these plans as senior individual responsibile for all on-and off-site radiation protection activities during March 28, 1979 incid,ent at TMI-II.
Radiological Engineer, Three Mile Island Nuclear Generating Station, Middletown, PA Assigned to Health Physics Department 1.
Responsible for the development and presentation of the general employee training, rad worker training, and technical training programs.
2.
Developed the station dosimetry and effluent monitoring programs.
9/73 to 9/74 Radia-lon Physicist, US Navy, Naval Regional Medied Center, Charleston, South Carolina Assigned to Radiology Department 1.
Responsible for health physics program for the department, including x-ray, fluroscopy and nuclear medicine lab facilities.
2.
Responsible for maintenance of the hospital radiation emergency plan for support of the Charleston Naval Shipyard.
t 1/72 to 9/73 Radiation Health Officer, U.S. Navy, U.S.S. Orion (AS-18) 1.
Responsible for dosimetry program for the submarine tender supporting ten nuclear powered submarines.
2.
Presented radiation nuclear training program for to:, der personnel assigned to radiologically controlled repair work.
s 4
Figure 2.1.3-18
LICENSES AND CERTIFICATES Qualified Radiation Protection Manager in Accordance with Regulatory Guide 1.8 Certified Power Reactor Health Physicist by the American Board of Health Physics Member of Health Physics Society and the Delaware Valley Society for Radiation Safety 1980 Present paper "Health Physics Problems at TMI" at American NJclear Society Annual Meeting 1980 Presented paper "Lessons Learned at TMI - An Industry Perspective" at American Nuclear Society Midyear Symposium L
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Tigure 2.1.3-19 L
NAMEt Jchn F. Si no EDUCATION AND TRAINING 1972 State University of New York at Albany - 2 week seminar in X-ray Spectrometry 1975 Widener University - B.S.
in Business Administration 1977 Delaware Technical and Community College -
besic course in Electricity 1983 Philadelphia Electric Company - Health Physics Assistant Technician Through A Technician Training 1985 Panasonic TLD System Operation Training Accuscan Whole Booy Counter Operation Training 1987 Tastscan Whole Body Counter Operation Training Kepner-Tregoe Management Decision Training Seminar WORK EXPERIENCE 12/84-Health Physic's Technical Assistant-Dosimetry Limerick Generating Station 1.
Participate in development / review of Desimetry procedures 2.
Develop and implement methods fqr maximizing
~
efficiency and productivity in the Dosimetry
. Dept.
i 3.
Co-ordinate process to ensure Eberline TLD's are properly exchanged each month and returned for Read
- eview operable status of Desimetry equipment and 4.
A report to Dosimetry Physicist 5.
Calibrate and r'equalification of Direct Reading Desimeters 6.
Perform monthly Eberline Cycle and related activities to ensure integri*y of external Fipre 2.1.3-20
Dos stry tonitoring progrca (N ERS), and to resolve discrepancies vs estimates 7.
Interface with PECo Services Division 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 (QA, NRD, etc.)
13.
Supervise the use oc 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 t
14.
Cn-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 Physics Technician A I
e Figure 2.1.3-21
j Dutioss Implement Radiation Work Permits, perform Radiation j
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 work *ed five refuel outages as well as numerous mini-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 Proper - Dewatering of Torus including monitoring 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 snutdown.
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 no::le t
replacement.
E.
Inboard and Outboard MSIV repairs and breaches.
F.
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.
Recire Motor removal and Replacements including Decon & Transport between units.
I b
Tigure 2.1.3-22
J.
lRD rcmoval Gnd rcplcccman (cs wall cs 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 transport from Drywell to Rebuild Area, CRD disassembly, Decon & Rebuild.
6.
?NCU 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.
D.
New fuel receipt and inspections.
E.
Spent fuel bundle disassembly by GE with pin f
puncture coverage.
F.
Initial entries to Vessel pre & Post Decon inclusive of disassembly and assembly of i
Reactor Vessel Components.
L 9.
Turbine Floors - Disassembly, Repair and modifications to HP & LP turbines, RTP Turbines, CIV's, Stop Valves and Control Valves.
Sandblast i
L l
t Figure 2.1.3-23
covo 33 of LP Turbino and RFPT 71ndloc and buckwcs.
10.
Meisturo Separator 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 & QC coverage for receipt and shipments of Radioactive materials - sources, condensate and RWJU 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 Emeraency Response Team Member - Participate in rejuired 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 for the area.
l$.
Spec!al projects & surveillance Test - As assigned.
16.
Contiel Rod Blad Stellite Roller Removal - CRB decon ar.c prep for snipment, and shipment coverage 9/78-3/79 Artesian Water Company, William De - Corporate work order in progress accounts, audit Property Account - maintain and investment 1/77-9/78 Piquet Securi.ty 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.
Engineering Technician (R&D) tested electrical stability and integrity of high voltage transmission cables.
Constructed EV test circuits utilizing test transformers, e
Figure 2.1.3-24 w -, - - -. - -
--,-m---.
...-r-
- n
tork.etiono cnd cplicing tochn.ucs.
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 ResGarch Technician - performed physical and chemical analysis of polypropelene films and polyr ers.
Supervised experimental film manuf acaring process.
5 4
l 4
e
{
i I
i i
Figure 2.1.3-25
NAMES Robert K.
B.. clay i
EDUCATION AND TRAINING i
1977 University of Pittsburgh i
B.S.
in Biology 1979 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) 1982 University of Tennessee, Oak Ridge Associated Universities Additional post-graduate credits (12) in Health Physics and Microdosimetry 1.
Panasonic Operations Course University of Micnigan, Ann 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 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 t
WORK EXPERIENCE.
7/84 to Philadelphia Electric Co.
Present Responsibilities:
Dosimetry Program; including external and internal dosimetry (Eberline, Panasonic, Landauer dosimeters and Canberra W.
B. C. equipment), procedures, data review.
Nuclear Employee Dr'a System (NEDS) site contact.
Supervision of contractor dosimetry employees.
Special Projects:
Drywell penetration neutron monitoring with Landauer dosimetry, Panasonic badga magasines, irradiation jig, irradiator field mapping.
e e
Figure 2.1.3-26
8/82 to Un_an Corbido Corp. Nucl00r D. A0 ion 7/84 Responsibilities:
maintenance and ongoing development of sodium iodide /hyperpure germanium in vivo analysis program, b,ody count result investigation, prediction equ'acidn analysis, preparation of purchase specifications, TLD system quality assurance, duties with medical staging area of plant emergency ressanse 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 applicatior.a and renewals.
10/77 - 8/79 Allegheny General Hospital Responsibilities:
Laboratory Technician with hospital blood team l
I f
i o
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[
Tigure 2.1.3-27
l TEs AICAL SUPPORT HEALTH PHYSI ST NAME:
Gary W. Murphy i
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. Radiation Protection with f
concentration in industrial hygiene 1976-1979 Harvard University, School of Public Health Graduate level courses in:
Radiation Biology Radiation Protection occupational Health Environmental Health Management
[
Short courses int Nuclear Emergency Planning I
Radiation Safety
[
i 1969-1973 Merrimack College, North Andover, Mass.
B.A.
Biology WORK EXPERIENCE 11/83 to' Support Health Physicist, j
Fresent Lin.arick Generating Station l
i l
Supervise the Technical Support Health Physics Group which ir.cludes the Desimetry, Respiratory Protection, and Protective Clothing, Special i
Projects, Enviremental Monitoring, and Radwaste and Radioactive Material Shipping Programs.
[
Responsibilities include Establish objectives L
for program area managers consistent with i
excellence in plant operation.
Provide l
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
Emergency offsite Dose Assesment Team Leader.
Serve as Plant operations Review Committee
[
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l 4
Tigure 1.3-28
A16ernate.
Serve as Health Pr.. sics 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 Eagineer, Limerick Emergency Offsite Dose Assessment System and Effluent Monitoring Syatem 9/76 - 7/79 Senior Research Assistant, Laboratory of Radiation Biology, Harvard University, Sc! Sol i
of Public Health I
3/74 - 7/76 Tufts University Medical School, Senior Research Assistant, Sidney Farber Cancer l
Research Center t
+
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J Tigure 2.1.3-29
/
NAME:
LorCnzo W21.s EDUCATION AND TRAINING 1982 Purdue University B.S. in Industrial Hygiene / Health Physics 1983 Peach Bottom Atomic Power Station-13 week training in Health Physics Staff Development and Operations 1983 Dosimeter Corporation of America, course in Dosimeter Calibration (1 day) 1983 Kepner-Tregoe two day course in Management Problem Solving Techniques, (2 Days) 1983 PECo, Engineering Orientation Training Prograt-BWR Systems and Reactor Theory (4 weeks) 1983 Training lectures on Dosimetry & 10CTR20 given by PECo personnel-training in the reading of P&ID's (1 day course) 1984 Chem-Nuclear Systems, Inc. Radioactive Material Shipping Regulatory Awareness Course WORK EXPERIENCE 10/84 to Radioactive Material and Radwaste Present Shipping Physicist-Phila. Elec. Co.
Limerick Generating Station j
Duties:
1.
Develop procedures relative to the handling, processing, and shipping criteria of radioactive material and radioactive waste.
i
~
2.
Developed program for the maintenance of records on the procurement, use and disposal of radioactive material in the form of source material.
I t
t 8
Tigure 2.1.3-30
3.
Station licsion with antractors performing radioactive material and radioactive waste transport, processing and waste disposal functions for conformance to federal regulations and burial site. criteria.
4.
Schedule radioactive waste shipments, and provide technical direction in the preparation of shipments.
5.
Prepare all necessary shipping documentation for each shipment of radioactive material and radioactive waste from the site.
6.
Remaining aware of the changing regulatory requirements, which impacts shipping radioactive material and l
waste, including attending workshops, seminars, and review of the Federal Registet.
7.
Perform the duties of the Program System Manager for the computer i
i program used in generating the radwaste container tracking documents for each container processed, and the shipping manifest for radioactive waste designated for burial.
8.
Development of a scaling factor tracking program for the different waste streams and corresponding surveillance test that relate to this Program.
I 9.
Serve on the Emergency Dose Assessment Tean. during Emergency Drills.
4/83 to Special Project Physicist 10/84 Philadelph'a Electric Company Limerick Generating Station Duties 1.
Development of Health Physics procedures.
2.
Assisted in the procurement of survey instruments and area monitors.
1 Tigure 2.1.3-31 i
3.
Training iceturcs on 4 diction protection and unique methods for radwaste disposal.
4.
Aided in the development of the external dosimetry program by determining decision to be Wade and equipment to be ordered.
5.
Participated in PBAPS Emergency Drill and practice exercises.
Acting as a controller / evaluator of in-plant health physics.
1/83 - 4/83 Health Physics Training at Peach Bottom Duties:
1.
Performed surveillance tests, area surveys and air samples throughout the plang.
2.
Performed ALARA calculations, estimates and record keeping.
3.
Routine operations of counting lab.
4.
Worked in the areas of radiochemistry lab operations, waste water treatment, internal and external dosimetry &
operations and handling of radioactive waste shipments.
I 5.
Contributions at Peach Bottom include:
Procedure development in the use of persor.
air sampling pump, performing air s6 ples during operation of electropolishing decontamination tank and assisted in *.he development of post accident sampling station procedures.
6.
Observed outage operations including aspects associated with health physics, removal of reactor head, main turbine, control rod drives, and entry into the drywell.
Figure 2.1.3-32
9/81 - 5/82 H.lth Physics Internrhip at arduo University Duties:
1.
Surveillance of laboratories containing radioactive material. This included discs smears and fadi& tion readings.
2.
Handling, and processing of low level radioactive waste.
3.
Calibration of survey instruments, GELI, and NaI (Ge) counters.
4.
Surveying of radioactive shipments packages prior to issuance.
5.
Inspecting radiation sources for leakage.
l 6.
Survey of small research reactor.
7.
Personal exposure monitoring using TLD.
8.
Microwave oven surveys for leakage.
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Tigure 2.1.3-33 i
L
NAME:
Stanlcy F.
0kor EDUCATION AND TRAINING 1976 East Senior High School (West Chester, Pa.)
3/79 - 11/83 Academic and "On the Job" training ih*He*alth 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, Nuclesr Physics, Radiation Biology, Radiation i
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.
i 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.
l Nine day course) 1/81 Quality Control Inspection of Rad-Waste Packaging and Shipment (Trained by PECo.
Quality Assurance Departruent) 1/84 Mitigation of Core Damage for Technicians (General Physics Corporation)t 4
11/85 Managing Safety Training PEco/Dupont 11/85 CPR Instructor Qualification 6/86 Nuclear Professional Training PECo a
6/86 Identifying Abberant Behavior PECo 9/86 Kepner Tregoe Decision Analysis / Problem Solving 1/87 Beta Desimetry/ Skin Dese Assessment-Perter Consulting 7/87 Advanced Respiratory Protection Training-Paul f
Steinmeyer i
I i
i 1
Tigure 2.1.3-34 l
l
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-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 v
6.
Established Surveillance Program and
]
developed U-1/U-2 Isolation Program 7.
Ordering of consumable supplies t
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" I
12/84 Limerick Generating Station t
l.
Pre-PORC review of Maintenance Procedures -
for Health Phy' tiles concerns.
2.
Assist in development of rough drafts of survey maps and review of same.
1 i
3.
Develop Health Physics Procedures.
l 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.
t Figure 2.1.3-35
6.
Day-to-day instructicn of
,o tcchnicions 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 Rad-Waste and Radioactive Material shipments, including solidified liquids, resins, laundry, filters, TW & R heaters and motors.
3.
Wrote changes to various procedures.
4.
Prepared, issued, revised radiation work permits.
S.
Performed all types of surveillance 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).
7.
Evaluated ALARA information for ALARA i
categorization.
[
8.
Off-site emergency coordineter for Emergency procedure exercises along with various other roles in response t'o emergencies and drills.
9.
Performed duties of Rover HP with interface with all job groups at PBAPS Units 2,3, and i
i 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-lating, freon, acid and sandblasting decon effort l
l t
Tigure 2.1.3-36 i
i 1
. ~..
F
... Cavorego of uso of mini
- colorator 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 MRTs 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 Teedwater 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 1.
As'sist at major controlPpoints.
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 Appointed Limerick Generating Station Red Cross Blood Drive Chairman 10/86 Tipre 2.1.3-37
.sPPLIED HEALTH PHYSICXST DATE APPOINTED:
March 1983 NAME:
Richard J. Titolo EDUCATION AND TRAINING 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 CTR, Chem Nuclear Systems, Inc.
1982 Georgia Power Company-Supervisor Safety Training Observation Program
- May, 1983 PECo, Kepner Tregoe (K-T) - 2 days, Problem Solving and Decision Making
- July, 1983 PECo, Engineer Orientation Training Program-4 weeks, covering BWR Systems and Reactor Theory i
- June, 1984 Theory & Operation of Eberline Survey Instrumentation
?
- November, 1984 Radioactive Material Shipping Regulatgry Awareness Course - Chem Nuclear Systems
- June, 1985 INPO Radiation Protection Manager's Workshop-3 days i
- December, 4
1985 Nuclear Professional Training-3 weeks, Nuclear Plant Systems, Regulatory Awareness September, 1986 Edision Electric Institute Meeting-4 days 2
- February, 1987 Beta Desimetry Training-2 days Porter Consultants
- June, 1987 Advanced Respiratory Protect.on-2 days: Radiation Safety Associates e
d Figure 2.1.3-38
- - =.
- July, 1987 Health Physics Audits-2 days WORK EXPERIENCE 3/83 to Applied Health Physicist, Limerick Generating Present Station Dutiest 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 routine and special radioingical surveillance program.
2.
Responsible for the development and implementation of the station Radiation Work Permit system.
i 3.
Direct the Instrument and Control group i
responsible for maintenance and calibration of Health Physics instrumentation.
t 4.
tvaluate Health Physics instrumentation requirement.< and assist in procurement.
- 5. Supervise the Health Physics Supervisor, Health Physics Technical l
Assistants, and Technicians.
r j
6.
Supervise the ALARA Physicist and Technical Assistants, and direct the 4
development and implementation of the station ALARA p'ogram.
7.
Supervise procedure development and
(
review technical procedures for adequacy and accuracy.
8.
Serve as Personnel Safety Team Leader j
(alternate) during emergencies.
i t
I Tigure 2.1.3-39
10/81 - 3/83 GGorgio Pcwor Ccmpany-Hocith Physicist E.I.
Hatch Nuclear Plant 1.
Responsibility for the development of the site ALARA program in collaboration with INPO personnel.
1 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.
1 4.
Instructed decontamination personnel in the use of strippable coating, approved and supervised initial applications.
i S.
Collaborated with maintenance personnel in the development of a pre-job checklist and supervised the initial phases of implementation.
t 6.
Performed job reviews for ALARA concerns and coordinated preparatory activities.
7.
Devised protective clothing and 1
respiratory protection guidelines and j
action levels.
8.
Developed and provided ALARA training to plant personnel.
l 9.
Performed plant. inspections of health physics related activities, e.g.
posting, procedural compliance, and directed HP staff in the resolution of problems identified.
l 10.
Investigated Radiation Occurrence Reports written by HP technicians and 3
i provided direction for corrective action.
11.
Wrote Laboratory Standing Orders (LSO) at the request of the HP Supervisor which provided instruccion in the resolution of problams encountered by the HP operating organization supervised initial phases of LSO impicmentation.
Figure 2.1. 3-i.0
12.
Provided guidance and townnical support to the technicians responsible for radwaste shipments.
13.
Prepared project documentation for equipment and services required in the annual budget.
This included vendor l
interface for functional specifications and cost-benefit analysis.
Emergency Preparedness Duties:
1.
Developed and 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 i
exercise.
5.
Developed and p'rovided training to Operations personnel on control roem l
procedures for emergency classification, offsite dose assessment and recommendetion of protective action.
6.
Supervised and dispatch 3 offsite d
monitoring teams during emergency drills and exercises.
L i
1/80 - 9/81 Georgia Institute of Technology Research Assistant l
Project: Correlation of absorbed dose to the hand with dosimetry measuring devices attached i
to the extremei' ties
(
This project was designed to study the
}
reliability and accuracy of extremity dosimeters l
through a comparison of point readings with a continuous dose distribution.
Directly responsible for the formulation of a model of f
the hand and wrist composed of ti, ue equivalen.
material and TLD powder.
Also, responsible for the calibration of the Car TLD, i.e. formulation t
of glow curves.
I t
107994 Figure 3 i LAt
G0er io Institute of Technology..csocrch 9/80 - 12/80 v
Assistant This project involved the experimental verification of the MIRD computer based calculations in the area of internal (psimetry.
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.
6/80 - 9/80 Applied Physical Technology Project Director Involved primarily with emergency assessment and response systems.
Directly responsible for project scheduling, customer communications, and procuring the necessary equipment.
Assisted in r
system configuration and testing, as well as preparation of associated equipment manuals.
6/79 - 6/80 Georgia Institute of Technology Research
[
Assistant Research done on the field of environmental l
impact from radioactive waste disposal.
Responsibilities included the design, performance and interpretation of experiments 1
utilizing columns packed 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 program to analyze results.
PRCFESSIONAL APTILIATIONS l
Health Physics Society American Nuclear Society l
l 1
1
\\
l i
i I
l I
l 2.I.3-42
~
j
_ NAM _E_: Thtmas J. F. cisz EDUCATION AND TRAINING 1968 Montgomery County Community College A.A.S.
in Electro-Mechanical Engineering Techno, log,y 1970 U.S. Navy Nuclear Power School-Nuclear Technology Fundamentals and U.S. Navy Nuclear Propulsion 1971 U.S. Navy Nuclear Propu2 sion Prototype and Engineering Laboratory Technician Training-Classroom instruction and hands-on experience at the prototype facility.
1984 Mitigation of Core Damage Training (January-2 days) 1984 Chemical Nuclear Regulatory Awareness Training (December-4 days) 1985 First Aid Instructor Training (June-2 days) 1986 K T Decision Making / Problem Analysis Training (August-3 days) 1987 Beta Dosimetry Training (February-2 days) 1987 Advanced Respiratory Protection Training (July-2 days)
WORK EXPERIENCE I
8/83 to Health Physics Supervisor Present Limerick Generating Station Duties:
Assigned the responsibility for supervising PECO and Vendor HP Technicians.
Responsibilities include:
1.
Responsible for supervising the RWP Program through periodic reviews of RWP's for compliance with procedures, completeness, accuracy, and necessity for additional action.
e Figure 2.1.3-43
2.
Establish work scheduaes and manpower loading based on plant operating and maintenance requirements in accordance with regulatory and administrative guidelines and good health physics practices.
3.
Performs various administrative duties associated with subordinates and maintains records doncerning payroll, input, vacation / leave requests, training and qualification, etc.
4.
Responsible for implementatior,of the Department overtime Policy in accordance with regulatory and adminstrative restrictions.
i 5.
Conduct weekly informational meetings to keep subordinates updated on HP procedure revisions and plant conditions.
t 6.
Review procedures and make
[
recommendations for changes.
i 7.
Develop maintain, and implement the
[
Routine Surveillance Program r
continually monitoring the adequacy I
based upon current plant conditions.
l 8.
Conduct routine plant inspections to
(
evaluate procedure compliance, safety and housekeeping conderns, etc., and arranga for, corrective actions where necessary.
9.
Maintain awareness of plant i
conditions through routine document
[
review, plant inspections, discussions with technicians on the job, attendance of routine meetings I
with interfacing groups and updates j
the Applied Health Physicist on plant 7
radiological conditions and status, t
i 10.
Oversees and ensures accomplishment f
of Surveillance Tests and Routine L
Tests.
Figure 2.1.3-44
l..
Generates and issues toutine reports to Management concerning personnel contamination summaries, accidents, overtime staffing.
12.
Provides direct supervision.of.
Technical Assistants and Sr.
Technicians responsible for implementation of the Applied Health Physics Program.
6/82 - 8/83 Health Physics Technical Assistant, Desimetry/ Bioassay at Peach Bottom Atomic Power Station Duties:
Was assigned the responsibility for the routine operation of the Peach Bottom Desimetry and Bioassay Program.
Responsibilities included:
1.
Making manpower schedulea 2.
Fr.suring operability of all related equipment and availability of spare parts and supplies.
3.
Reviewing, revising, writing dosimetry related procedures.
4.
Interfacing with other groups reguarding specific dosimetry requirements.
5.
Maintaining dosimetry, training, and security records in dhe Nuclear Personnel Systems data base.
10/77 - 6/82 Health Physics Technical Assistant Peach Bottom Atomic Power Station Duties:
Was assigned the responsibility to coordinate Health Physics efforts in Unit 2 and Radwaste during routine operation and cutage conditions.
Specific responsibilities included:
1.
Acted as Alternate Personnel Safety Team Leader in PBAPS E.mergency Plan.
i Figure i
2.1.3-45
2 Mako manpowar lecding tccomm3ndations and schedules.
3.
Conduct investigations reguarding personnel 'intamination, exposures in excess of guides, violations of Station Operating Procedures.
3/79 Volunteered as a Health Physics Technician at Three Mile Island 3 days after the Accident.
Duties:
Tracked the raciation plumes in the Middletown area and acted as a Health Physics escort fer an operator to enter the basement of the affected Unit 2 Reactor Auxiliary Building.
9/77 Health Physics Senior Technician for Rad Services, Inc. at Oconee Nuclear Station (2 weeks)
Duties:
He worked as a technician providing health physics coverage of workers on a steam gr.nerator lower tube sheet.
10/74 - 9/7" Health Physics Technician at Temple University Radiation Safety Office, Philadelphia, PA.
Duties:
Worked as a health physics technician for one year performing routine health physics monitoring of various rooms and laboratories in the University, Medical Research Labs, and Nuclear Medicine, Department of Temple Hospital.
1.
Receip*t of radioactive packages 2.
Handling and shipping of redioactive waste.
3.
Pe.sonal exposure monitoring 4.
Routine contamination surveys.
i Tigure 2.1.3-46 i
i
4 Ths next 2 years were spent in..pecting radiation producing machines throughout the University.
These inspections were to ensure compliance with State and Federal Regulations pertaining to use, total output and filtration.
The machines inspected. included x-ray units, flouroscopes, x-ray diffraction spectormeters, electron microscopes, teletherapy units, and a neutron generator.
I was directly involved with shielding calculations and installation of the newly-renovated Dental School X-Ray Department.
10/68 - 10/74 U.S. Navy Duties:
The first 2 years were spent in classroom instruction and prototype training.
After initial training he was assigned to the U.S.S. Benjamin Tranklin as a Nuclear Machinist Mate.
During this time, 14 months were spent in the shipyard for refueling and overhaul of the submarine's nuclear propu2* ion system.
Prior te Honorable Di.scharge I was assigned for 4 mentas as a maintenance mechsnic aboard the NR-1, and experimental nuclear miniature submarine.
e 1
t f
[
Figure 2.1.3-0
.