ML20151D131
| ML20151D131 | |
| Person / Time | |
|---|---|
| Site: | 07003054 |
| Issue date: | 03/22/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20150E368 | List: |
| References | |
| A-44, NUDOCS 8807220372 | |
| Download: ML20151D131 (14) | |
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Provide administrative cuidance of (dN.M9 elbh E/
2.2.1 2: ovide te=hnical aevice ater.7
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2.2.2 shipments and receipts.
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..id'the Reac::: Engineer in maintenance of inventories, s: Ora.ge, internal transfers, measurements, records, reports-and procedure changes concerning SNM.
2.3 The Superintenden: - Nuclea: Generation Division, shall be responsible to:
2.3.1 Manage SNM for Philadelphia Electric C0=pany.
2.4 The Fuel Manacement Section of the Electric P:Oduction Department shall be respcnsible to:
Engineer in administration, 2.4.1 Aid the Reac:0:
accounting, shipping and receiving, inven:0:y maintenance, storage, internal transfers, measurements, records, reports and procedure changes 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 Inven: cry Listing DOE /NRC Form - 742C.
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2.5 The Station Superintendent or his designated
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respresentative shall be responsible to:
2.5.1 P: Ovide station managemen; of SNM.
2.5.2 Receive SNM.
2.5.3 Review and aco:Ove SNM accountinc c:Ocedures.
i 2.5.4 Acknowledge the outgeing shipment of SNM.
2. 5-The Technical. Engineer shall be responsible to:
2.6.1 Supervise.the administration of SNM.
2.6.2 Supervise the maintenance of records necessarv to determine depletion of SNM.
4 2.6.3 Supervise the preparation of reports ccacerning changes, additions or deletions to SNM.or SNM related components.
2.7 The Reactor Engineer shall be responsible to:
2.7.1 Control the on site administration of SNM.
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A-44, Rev. 3 Pace 3 cf 14 2,
KWE:rgs rm Deve2cp implementation' procedures to receive,
.;f t.<.2 handle, s:cre, account and ship SNM.
2.7.3 Maintain and submit the' reports, records and logs necessary to ensure accountability of all en sita SNM.
2.7.4 Coordinate site personnel activities such as receiving,. shipping, stcrage, internal transfer and acccunting of SNM.
2.7.5 P:cvide direction fc: the receipt, unloading, loading and shipment of SNM.
I 2.7.6 Insure that station accountability records, reco::s and locs concerning SNM are app cpriately maintained.
2.8 The Eealth Physics Supervision shall be responsible to:
2.S.1 P cvide Health Physics direction of the. receipt, leading and shipment of SNM.
2.S.2 Ensure that the appropriate Eealth Physics documents concerning the SNM are appropriately T.'.
maintained.
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2.9 The Operations Shift Superir.tenden shall be reso0nsible to:
2.9.1 Ensure that personnel responsible for core altera:icns are Senic: Reac:cr Opera:0:s who have no c her concurrent responsibilities during this activity.
2.10 The Puel Handling director shall be responsible :::
2.10.1 Direct, '-+-
k e refuelinc~ platform, fuel movement and any core alteration.'
2.11 Administration Engineer shall be responsible to:
2.11.1 Develop and implement station p ccedures to ensure that all SNM is properly guarded and oat:clied.
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l 3.0 PREREQUISITES None C..
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,. 0 D _: :.. s. ! ~.. O,.., S 4.1 Special Nuclear Material (SNM) is plutonium, uranium 233, uranium enriched in the iso:cpes 233 or 235, c:
any materia'. at:ificially enriched in the preceeding, but does no: include source material.
SNM includes Scurce Range Monitors (SRMs), Intermediate Range M0ni:0:s (IRMs), Traversing.Incore Probes (TIPS), Lccal
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Power Range Monitors (LPRMs) and fuel (10CTR 70.4).
4.2 Material Balance Areas (MBAs) are specific areas on 1
site wnere SNM is s:0:ed c: p ccessed.
Inventories cf each MEA as well as records and legs of all additions ll and re=0vals are maintained by the Reactor Engineer (10CFR 70.51).
The following locatiens are defined as MEAS for fuel:
1.
New Fuel Storage 2.
Te=.0crary Storac.e 3.
Unit 1 Fuel Floor i
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Unit 1 Reacto 6.
Unit 2 Reac 0:
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se' The foll: wing locaticns are defined as MEAS f0: SRMs, IRMs, LPRMs, T:Ps and other SNM:
1.
Temporary Storage
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Uni: 2 Fuel Pool 8.
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4.3 Fuel Handline director - Durine an cutace with the reac:0: ' head removed and irradiated fuel in the vessel the Fuel Eandling director shall be a SRO licensed individual.
During an outage with the reactor head not removed c during a non-ou: age period the Fuel Handling director shall be a cognizan; individual desic.nated bv the Station Superintendent.
5.0 PROCEDURE 5.1 RECEIPT OF SNM
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.5.1.1 SNM shall be received at the station by the
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.:7-5.1.2 Shipping records accompanying the SNM shall be delivered to the Storeroom for disposition (Except for fuel).
A copy of the shipping p
records containing item serial numbers for all I
SNM (except f0: fuel) will'be transmitted by the s: Ore keeper c: OC Receip Inspection, to the Reactor Engineer.
A copy of the fuel shipping records containing item serial numbers will be transmitted'by the Reactor Engineer to the Fuel Management Section of the Electric Production Department.
5.1.3 Health Physics personnel shall measure external radiatica levels of the shipment and examine the shipment fc: surface contamination.
5.1.4 The shipping containers shall be checked f0:
signs of damage and any damage found shall be disp 0sitioned as per FH-101. In the event of major container damage, the-SNM manufac ure mus: be notified-and remedial actions implemented.
The Reactor Engineer will file a repc : concerning the. steps taken after the discovery.of majer container damage.
5.1.5 For fuel shiements, the serial number cf the two 60 seals on the'woeden shipping box and the enree seals en the metal centaine shall be verified to be as. listed en the shipping records' containing the container serial nu=cers.
5.1.6 The fuel shipmen; shall be unl:aded and =cved according to app cved Fuel Handling P ccedures.
5.1.7 Fuel shipping centaine:s-shall be inspected for content according to the shipping records containing item serial numbe:s at.the earlies:
practicable time after m,ovement.:o the Fuel-j Floor.
SRM, IRM, LPRM and'TIP shi'pping-centainers shall be inspected for content according~ to the shipping records containing item serial numbers when the item is-receipt insoected.
5.1.8 Discrepancies in SNM cuantities 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 Enginee shall contact the shipper to resolve the discrepancy.
Any unresolved discrepancies shall P.S be reported immediately by telephone to the Nuclear Regulatory Commission (NRC) in accordance with 10 CFR Part-70.52 (Ref.1).
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'l A-44, Rev. 3 Page 6 of 14 KWE::cs
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5.1.9 A-44-la Fuel Receip:/ Tracking Data Sheet and A-44-lb Temporary Fuel Storage Data Sheet, if rec.uired, shall be initiated upon the recai -
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fuel.
A-44-6 Non-Fuel Receipt and Storage Data Sheet shall be initiated upon the receipt of any other SNM by the Reactor Engineerinc. G:cu.o or any cognizan: technical, staff member.
A-44-lb TO SE INITIATED ONLY IF NEW FUEL STORAGE AP.IA :S NOT TO SI USED.
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5.2.1 The preparation of SNM shipments is the responsibility of the Station Superintendent.
5.2.2 Packaging and shipment arrangements for SNM are suoervised bv the Reac:0: Enc.ineer with c.uidance from the EP G: cup, the Fuel Management Section 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.
C 5.2.3 Changes to the site SNM inventory are recorded b#
at the departure of each shipment by the Reac:Or i
Engineer or his designated respresentative.
5.2.4 Shipping records for each shipment of SNM are kep: en file in the station files. Ccpies of tha fuel shipping records containing 1:e. serial j
numbers are forwarded by the Reac:0: Engineer :0 i
the Fuel Management Section of the Electric Production Department and, if recuired, to the Nuclear Engineering Sec.:icn of the Engineering and Research Department.
5.2.5 The compl~etion and distribution'of D'OE/NRC-741
is the responsibility of the Fuel Managemen:
Section of the Electric Production Departmen:.
Ele,cin5 discrepancies cetween Philadelphia Shio.
5.2.6 ctric Company and the receiver of SNM are to be resolved promptly.' Unaccountable discrepancies are reported immediately by 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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5.2.7 Shipping discrepancies are reported to the Fuel Management Section of the Electric Production Department due.:
the possible impact on DCE/NRC - 741 by the Reactor Engineering G cup cr any cognizan: technical staff member.
5.2.8 Shipman
of irradiated fuel.shall comply with 10 CFR 20, 10 CFR 70, 10 CFR 71, and applicable Department of Transportation regulations.
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5.3.1 SNM shall be stored only in the MSAs specified in Step 4.2.
5.3.2 SNM shall no: 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 en Forms A-44-la and A-44-lb.
5.3.5 S:crage of non-fuel SNM in temporary storage MSA shall be documented on Form A-44-6 and A-44-9
.(7 (as required).
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5.4.1 Fuel transferred between storage MSAs c: between a s:orage MSA and a fuel fico: or between a fuel f '_ : : a..d a fuel pc01 shall be documented en FO:
A-44-la and, if receired, on Form A-44-lb.
5.4.2 Fuel transfer between MEAS requires updating the fellowing fuel accounting. documents:.
1.
A-44-2, Fuel Invento:V. Summary Sh.ee:
i 2.
A-44-3, Fuel Inventory Log-fuel c.ool i
(fuel pool only) 3.
A-44-4, Fuel Inventerv. Loc - Core (core only) 4.
Sterac.e Location Tac. Board (fuel pool and reactor only) j 5.
A-44-5, Fuel Location Eistor.v Sheet 1
(fuel Pool and reactor only)
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5.4.3 Transfer of fission chambers between MBAs shall be authorized by A-44-8, Fission Chamber Transfe: Authorization Sheet (FCTAS).
Movement of fission chambers may occur only. after the s. ',
Reactor Engineer or his designated "d
representative has signed A-44-8.
(Exception:
See Step 5.4.4.)
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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 between MSAs 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 Sheet
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5.5.1 Movement of fuel frem the fuel floor to the fuel poci is recorded on A-44-la and as required by the applicable FE Procedure.
ALL FUEL MOVEMENTS FOLLOWING PLACEMENT IN THE
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s 5.5.2 Movement of fuel within the fuel pool is authori:ed by a CCTAS.
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5.5.3 Manipulation of fuel withir. the fuel poci should be acccmplished in accordarce with 597.0.E (General Handling cf Core ':=ponent and Irradiated Items in the Fuel Fool / Cask Pec1).
5.5.4 Within three months of a fuel handling cperation in the fuel 7:01, the applicable fuel accounting records shall be assemoled and the following logs and records updated:
1.
A-44-3 the Fuel Inventory Log - Fuel Pool shall be u dated.usin the CCTAS and the Fuel.Poci Tag Board.
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A-44-5 Individual fuel Location History Sheets shall be updated using the CCTAS.
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5.6.1 Movement of fuel into or cut of the reacter is authori:ed with a CCTAS.
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j A-44, Rev. 3 Page 9 cf 14 KWE:rgs f.:.s 5.6.2 T:ansfer of fuel into c: out of c: within the reaq: : shculd be accomplished in accc dance with S97.0.C (Transfer of Fuel f cm the Fuel
? 01 to the Reac:0:), S97.0.C (Transfer of Fuel f: = the Reacter to the Fuel P0ol) and S97.0.I (Transfer of Fuel Within the Reactor).
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5.6.3 Visual cor.firmation of fuel assembly serial numbers in the reactor shall be done following refueling operations.
5.6.4 Within three months of a refueling cutage the applicable fuel acccunting records shall be 1
acsembled and the folicwing 1 cgs and records updated:
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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 Lccation Tag Scards.
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A-44-5 the Fuel Location His:O r v. Sheets are
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updated using the CCTAS.
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5.7.1 The plant p:ccess computer p cvides reactor
- hermal power and fuel burnup info:riation tha:
the Tecnnical Engineer should forward to the Fuel Management Sectic Of the -Ilec::ic P::duc:ica Depar ment.
5.7.2 The Fuel Manage..en: Section of the Electric j
P: duction Depar: ment shall calculate the i
is0:c.cic c.uantities cf fuel cresen on site.
4 5.7.3 The Reae:c: Engineer shall conduct an inventory cf all on site SNM annually c 'when a descrec.ancv in any of the MEAS is discovered.
The SNM in the reacto: is exempt f cm the inven:0 y when the reactor head is in place and verification of reactor inventory has been performed.
Outstanding discrepancies shall be b:cught 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 (Ref. 1).
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5.7.4 The Reac :: Engineer shculd forward the results of inventeries to the Fuel Management Section of l
the Electric Production Department.
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l 5.7.5 The Fuel Mar.agement Sectic.. of the Electric P:Oduction Department shall prepare NRC/ DOE-742 f0: transmit:2>.
5.6 CEANGES TO SNM AND SNM ACCOUNTING 5.8.1 If SNM other than fuel, SRMs, IRMs, LPRMs c:
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 Reae::: Engineer shall determine if existing p ccedures are sufficient to provide adequate accounting.
2.
A permanent change to SNM may require chances tc this crocedure.
The Reacto:
Engineer shall d'termine the accounting e
needs cf the new SNM.
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New accounting p ccedures and changes te this procedure shall be performed in accc: dance with LGS ?:ocedure A-1 -(Reference
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5.9 SNM ACCOUNT:NG DOCUMENTS J
5.5.1 A-44-la, Fuel Receio. / Tracking Data Sheet ( F O :..
M-21974) - This shee indicates the location of fuel f:cm receipt en site to storage in the Fuel Peel after the :eceipt inspection.
When fuel is s:cred in Temporary Storage rather than the New Fuel Storac.e' Area, A-44-lb must also be used and the "1b" column en A-44-la checked.
As a minimum this sheet shall contain:
arrival date
^
and time, Container Serial Numbers containing seal nu.T.bers, Fuel Assembly Serial ~ Number, transfer dates, location on the Fuel Floor
("pile" as specified in TH-102 (COL),."Row" with and "Tier" as the level position wi,d west walls number 1 starting f cm the north an th the lowest position being 1) and Date Fuel inspected on Fuel Floor.
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t. i.f 5.9.2 A-44-lb, Temporary Fuel Storage Data Shee (Form M-21975) - This shee:.is used when fuel received is not s:0:ed 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 Temporary Storage Area (e.g. row, tier, column).
As a mini =um this sheet shall contain:
Containe-Serial-Number, Fuel-Assembly Se:ial Number, Temporary Storage Area, loca:icn in Temporary Storage Area, Date/ Time in and.out of s : O r a c. e.
5.9.3 A-44-2,_ Fuel Inventory Summary Sheet (Form M-21976) - This sheet is a listing of the site MEAS, !!he areas are as defined in Step 4.2.
All fuel assemblies shall be accounted f0: in these MBAs.
h'henever fuel is received, shipped c: ::ansferred, the Fuel Inventory Summary Sheet shall be updated.-
The total fuel on site shall ecual the sum of the fuel in the MBAs.
As a minimum this sheet shall contain:
date received, number of items received or shipped, total en si:e, number in Ne,w Fuel Storage, s';
Temporary S:Orage, Fuel F100:, Reac: : and Fuel-
"C-ficer.
5.9.4 A-44-3, Fuel Inventory Log - Fuel Pool (Fc:= M-21977) A-44-4 Fuel Inventory Log-Core (Tc:= M-21978) - These irgs are a location record cf fuel assemblies in the Fuel P0cl c: C0re.
The Fuel Inven:Ory Legs are updated and verified cc: rec: at the c0mpletion of a fuel handling operation.
Sc:mally, tabulations of Fuel Fool I
and Core pcsitions are used,'hewever, other, mea *s are acceptable.
The fuel asse=bly serial l
nu.-ber is entered in the space p cvided en the log cc :esponding to the'lecatien in the Fuel P001 c: Core.
The Fuel Pool dnd Core Invin:ory Logs and the Storage Location Tag Board should agree.
After the fuel handling operation, the Fuel Pool and Cora Inventory Logs tre thc official fuel assembly location records.
As a minimum A-44-3 shall contain the Unit Number, Fuel Fool Location, Fuel Bundle Serial Number, and Name and Date of person revising the form.
A-44-4 shall contain the Unit Number, Core J
Location, Fuel Bundle Serial Number, and Name and Date of persen revising the form.
Both A-44-3 and A-44-4 should be approved by the Ch Reactor Enginee..
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5.9.5 S crage Locatien Tag _Ecards - These boards are plan views cf the reactor and the fuel pool.
Erch fuel assembly snall have a tag iden:ifying ne serial number.
The tags will be moved as i
its cc :esponding fuel assembly is moved.
While the Tag 30ards should be kept as accura:e as possible, they are used for information only and do no: consti:ute an official fuel accoun: ability record.
5.9.6 A-44-5, Fuel Location History Sheet (Form
.u.-
21979) - Eacn fuel assembly on site shall have a Fuel Loca:icn History Shee: after placement in
- he fuel peel.
The shee: heading has spaces for the following information:
1 1.
Serial Number 2.
Date Received 3.
Date Inspected 4.
Channel Serial Number - Date Channeled 5.
Fuel Pin Changes 6.
Loca:icn 7.
Date In 8.
Date Out
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Fuel assembly locations are to be 10c.c.ed Oniv
'c.
fc: movements of significan: duration 4 - FO:
example, fuel shuffling _between two core locations may require temporary placement in the fuel peel.
The fuel pool location need not be sh0Vn en the Fuel L0 cation History Sheet.
Cnly
- he final 1cca:icn in the core mus: be shown.
The "Date Ou:" and "Da:e In" entries should be the date the bundle is verified to be in i:s p Ope: 10 cati:n for moves made during a fuel handling cpera:icn.
Non-cutage fuel =0ves snould be dated as performed.
Te=ocrarv, storage 10:ations and time of =0vement are recorded on
. s. e
..c.S.
5.9.7 Core Component Transfer Authori:ation Sheets (CCTAS) - The CCTAS p 0Vides a sequential listing of the fuel and core component movements to be performed and shall be used by the Fuel Eandling director in performing the fuel handling operation.
The CCTAS is a Form (M-21965, 21966, 21967) that is referenced from the applicable TE Procedure. A CCTAS is required for all fuel movements following initial inspection and storage in the fuel pool.
A CCTAS should include the following information:
"1....<4 1.
Signature of person authori:ing the work.
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Date authorized.
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Column f0: Step Number 4.
Column for Serial Number 5.
Column f0: From Location 6.
Column for Orientation in "From" column 7.
Column for To Location 8.
Column f0: Orientation in "To" column 9.
Columns as required for initials of personnel required to document the transfe:
- 10. Column f0: Time of Transfer
- 11. Colu=n f0: Date cf Transfer 5.9.8 A-44-6, Non-Fuel Receipt and Storage Data Shee (Form M-21980) - This. sheet is required when.
non-fuel SNM is received on site.
This shee:
indicates the location of SNM storage upon receipt. As a minimum this sheet shall contain:
Tvo.e of SNM, Serial Number, Storage Location, and date received.
5.9.9. A-44-7, Fission Chamber :nventory Summary Shee:(Form M-21981)- This sheet is a listing of the :Otal number of fission chambers in each Cs MEA.
Whenever a fissica chamber is received, shipped or transferred, A-44-7 should be uoda:ed.
The :ctal firsion chambers on site i
- s. hall equal the sum of the MBAs. As a minimum I,
I this shee shall contain the Unit Number, l,
Chamber Type, Date, number received, number t-shipped, :::al en site, number in Temporary S:Orage, Fuel F10ct, Reac:ct, Pocl or I :adiated S:0 : a c. e.
5.9.10 A-44-8, Fission Chamber Transfer Authori:ation Sheet (FCTAS),(Torm M-21982) - The Reactor Engineer or his designated representa:ive shall fill in the form before signing the authori:ation.
The person performing the move shall initial and date the form and :eturn it to the Reactor Engineer.
This sheet is required prior to any movement of fission chambers after initial receip (Exception:
See Step 5.4.4). As a minimum this sheet shall contain:
the Unit j
Number, Authorized By, Date Detector Type, r
Serial Number, MBA presently located and future MSA location, Initials and Date.
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5.9.11 A-44-9, Fission Chamber Location History Sheet (Form M-21983) Each fission chamber recuires an A-44-9 afrer 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 shee shall contain:
the Unit Number, Detector Type, Serial Number, Date received, Loca:icn and Date In and Date Out.
5.9.12 Retention cf documents shall be as follows:
1.
Appropriate data sheets, logs, and summary shee:s 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 recention.
2.
The Reactor Engineer shall provide the Nuclear Records Management (NRM) System 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 a4 wi:n apprcpriate Health Physics documents relative to the SNM as per Health Physics
~'
Precedures, l
5.10 Materials Control Managemen 5.10.1 Periodi: audits of the Fuel Handling redords are l
initiated by the NRS (Nuclear Review Board)
I using independent auditing agents.
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- e. _r r _re..r r.. _r S 6.1 10 CFR, Part 70 - Demestic Licensi.ng of SNM 6.2 A Procedure.fer Preparation and Control'of Administrative Procedures 6.3 S97.0.E General Eandling of Co,re Component and Irradiated Items in the Fuel Pool / Cask Pool.
6.4 597.0.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 p,s tgjy 6.6 S97.0.E Transfer'of Fuel Within'the Reactor 6.7 A-46 Procedure for Maintenance of Plant Quality.
Assurance Records.
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