ML20151D127
| ML20151D127 | |
| Person / Time | |
|---|---|
| Site: | 07003054 |
| Issue date: | 03/22/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20150E341 | List: |
| References | |
| A-44, NUDOCS 8807220372 | |
| Download: ML20151D127 (14) | |
Text
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LIMERICK GENERATING STATION 3 l4 To A-44 PROCEDURE FOR SCEC*AL NUCLEAR MATERIAL ACCOUNT ~NG 1.0 PURPOSE This procedure describes the administrative controls, responsibilities, methods and documentation required for proper acccunting of special nuclear material (SNM).
It is imperative that the plant staff have a complete record ef.SNM locations.
This information is required by the Philadelphia Electric Company, the code of Federal Regulatiens and the venders of SNM.
Philadelphia Electric Ccmpany requires the location and quantities of SNM to aid in core performance optimi::ation, scheduling of refueling outages and the purchase or reprocessing of SNM.
10 CFR, Part 70.51 states that the licensee sha'll keep recc:ds of the receipt, inventory, disposal, acquisition and f.S
- ansfer of all SNM.
10 CTR, Parts 70.53 and 70.54 require G'
the submittal of Material Status Reports and Nuclear Material'Transf er Reports, respectively (Ref. 1).
Fuel and SNM venders require reperts concerning their p:cduct.
The cen:ents of these reports are outlined in the warranty con::ac and are usually required as par: cf -he war:anny centrac:.
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2.1 The Purchasing Division of the Purchasing and Gener'i a
Services Department shall be respcasible te:
2.1.1 Aid the Reactor Engineer in packaging and shipping a::angements fc inc
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SNM and o-her incere compone 2.2 The Nuclear Ingineering Section of t.
I.
O hlecga.id%Imman%,
Research Department shall be responsible to:
Provideadministrativeguidanceof.${T;Q*fj/'ryd N f >. n 2.2.1 JU1 2.2.2 Provide technical advice arda
- irm materia-shipments and receipts.
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..g, EXF.I3I; 2 8807220372 080506 i
REG 1 LIC70 PNV SNM-1977
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A-44,.Rev. 3
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m k 9 2.2.3 Aid the Reactor Engineer in maintenance of inventories, storage, internal transfers, measurements,. records, reports and procedure changes concerning SNM.
2.3 The Superintendent - Nuclear Generation Division, shall be responsible to:
2.3.1 Manage SNM for Philadelphia Electric Company.
2.4 The Fuel Management Section of the Electric Production Department shall be responsible to:
2.4.1 Aid the Reactor Engineer in administration, accounting, shipping and receiving, inventory 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 Inventcry Listing DOE /NRC Form - 742C.
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2.5 The Station Superintendent or his designated respresentative shall be responsible to:
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2.5.1 Provide station management of SNM.
2.5.2 Receive SNM.
2.5.3 Review and app:ove SNM,ac. counting procedures.
2.5.4 Acknowledge the outgoing shipment of SNM.
2.6-The Techn'ical. Engineer s.y.all'be responsible to:
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.
i 2.7 The Reactor Engineer shall be responsible to:
2.7.1 Control the on site administration of SSM.
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'KWE:rgs b..:7 2.7.2 Develop implementation procedures to receive, handle, store, account and ship SNM.
2.7.3 Maintain and submit the reports, records and
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logs necessary to ensure accountability of all on site SNM.
2.7.4 Coordinate site personnel activities such as receiving, shipping, storage,- internal transfer and accounting of SNM.
2.7.5 Provide direction for the receipt, unloading, loading and shipment of SNM.
l 2.7.6 Ensure that station accountability records, l'
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, loading and shipment of SNM.
2.8.2 Ensure that the appropriate Eealth Physics documents concerning the SNM are appropriately CN maintained.
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2.9 Tne Operations Shift Superintendent shall be l'
resconsible to-1 1
2.9.1 Ensure that personnel responsible for core alterarions are Senior Reactor Operators who have no other concurrent responsibilities during this activity.
f 2.10 The Fuel Handling director shall be responsible to:
2.10.1 Direct, from the refuelinc' platform, fuel movement and any core alteration.
2.11 Administration Engineer shall ce responsible to:
2.11.1 Develop and implement station procedures to ensure that all SNM is properly guarded and patrolled.
3.0 PREREQUISITES s
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A-44, Rev. 3 Page 4 of 14 KWE:rgs h
4.0 DEFINITIONS 4.1 Special Nuclear Material (SNM) is plutonium, uranium j
233, uranium enriched,in the isotopes 233 or 235, er any material artificially enriched in'the' preceeding, but does not include source material.
SNM includes
-)
Source Range Monitors (SRMs), Intermediate Range Monitors (IRMs), Traversing.Incore Probes (TIPS), L'o ca l Power Range Monitors (LPRMs) and fuel'(10CFR 70.4).
4.2 Material Balance Areas (MBAs)_are specific' areas on site where SNM is stored or processed.
Inventories of each MBA as well as records a'nd legs of all additions f
and removals are maintained by the Reactor Engineer f
I (10CFR 70.51).
The following locations are defined as MBAs for fuel:
1.
New Fuel Storage 2.
Temporary Storage 3.
Unit 1 Fuel Floor 4.
Unit 2 Fuel Floor 3.
Unit 1 Reactor 6.
Unit 2 Reactor 7.
Unit 1 Fuel Pool pQ.
8.
Unit 2 Fuel Pool Ca*
The following locations are defined as M3As for SRMs, IRMs, LPRMs, TIPS and other SNM:
l.
Temporary Storage 2.
Unit i Fuel Floor 3.
Unit 2 Fuel Flocr.
4.
Unit 1 Reacto:
5.
Unit 2 Reactor 6.
Unit 1 Fuel Pool 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 the Fuel Handling director shall be a SRO licensed individual.
During an outage with the reactor head not removed or during a non-outage period the Fuel Handling director shall be a cogni: ant individual designated by 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 j
Station Superintendent or his designated representative.
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d 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 QC Receipt 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 radiation levels of the shipment and examine the shipment for surface contamination.
j 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.
.CQ, 5.1.5 For fuel shioments, the serial number cf the two 69 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 unicaded and mcved according to approved Fuel Eandling Procedures.-
5.1.7 Fuel shipping cc:. tainers shall be inspected for content according r.o the shipping records containing item serial numbers at.the earliest cracticable time af ter movement.to the - Fuel-
' Floor.
SRM, IRM, LPRM-a'nd~ TIP shi'pping-contaiders shall be inspected for' content according to the shipping records containing item serial numbers when the item is receipt inspected.
5.1.8 Dis ~crepancies in SNM quantities discovered during the inspection shall be reported to,the Reactor Engineer, Station Superintendent and the Fuel Management Secti on of the Electric Production Department.
The Reactor Engineer shall contact the shipper to resolve the discrepancy.
Any unresolved discrepancies shall gA 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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.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 i
Sheet shall be initiated upon the receipt of any 4
other SNM by the Reactor Engineering Group or any cognizant technical staff member.-
A-44-lb TO BE INITIATED ONLY IF NEW FUEL STORAGE AREA IS NOT TO BE USED.
,l 5.2 SHIPMENT OF SNM 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.
supervised by the' Reactor Engineer with guidance f cm the EP Group, 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 1
Departmen' 1
G) 5.2.3 Changes to the site SNM inventory are recorded I
at the departure of each shipment by the Reactor Y 2' Engineer or his de'signated respresentative.
5.2.4 Shipping records for each shipment of SNM are kept on file in the station files. Ccpies of the fuel shipping records containing item sarial nu=bers 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 DOE /NRC-741
l is the responsibility of the Fuel Management Section of the Electric Production Department.
5.2.6 Shipping discrepancies between Philadelphia Electric Ccmpany 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 arefreported to the Fuel Management Section'of the Electric. Production Department due,to the possible impact on DOE /NRC - 741 by'theLReactor Engineering Group or any cogni= ant 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 r.
5.3.1 SNM shall be stored only in the MSAs specified in Step 4.2.
5.3.2 SNM 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 shallibe 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 gy, (as required).
5.4 INTERNAL TRANSFER DOCUMENTATION' UPDATE.FOR SNM l.
5. 4.1, Fuel transferred between storage MBAs or between i;
a storage MBA and a fuel floor or between a fuel flocr and a fuel pool shall be documented es.
Form A-44-la and, if required, on Form A-44-lb.
5.4.2 Fuel transfer between MSAs requires updating the following fuel accounting, documents:.
l 1.
A-44-2, Fuel Inventory Summary Sheet l
2.
A-44-3, Fuel Inventory Log-fuel pool (f,uel 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 Eistory Sheet (fuel Pool and reactor only)
N Transfer o' fission chambers between MBAs shall f
5.4.3 be authorized by A-44-8, Fission Chamber Transfer Authorization Sheet (FCTAS).
Movement j
of fission chambers may occur only after the 4-[,3 Reactor Engineer or his designated f.
representative has signed A-44-8. (Exception:
See Step 5.4.4.)
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w 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 MBAs using
.either a FCTAS or CCTAS require _ updating.the following fission chamber accounting documents:
1.
A-44-7,-Fission Chamb'.;r' Inventory Summary Sheet-2.
A-44-9,,
Fission' Chamber _ Location History Sheet 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 THE FUEL PREP MACHINE MUST BE ACCOMPLISHED BY USING-TEE REFUELISG PLATFORM FCEL GRAPPLE.
5.5.2 Movement of fue1~within the fuel pool is authori:ed by a CCTAS.
(?l, 5.5.3 Manipulation of fuel within the fuel pool should be accomplished in accordance with S97.0.E (General Handling of Core Component and Irradiated Items in the Fuel Fool / Cask Pool).
5.5.4 Withinthreemon$hsofafuelhandlingcperation 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 I1ventory Log - Fuel Pool shall be uod.t ad.t sing the CCTAS and the
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Fuel. Pool ta, Boatd.
2.
A-4_4-5 Individual Fuel Location History i
Sheets shall be updated using the CCTAS.
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5.6 TRANSFER OF FUEL DURING REFJELING 5.6.1 Movement of fuel into or out of the reactor is authorized with a CCTAS.
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- c9 5.6.2 Transfer of fuel into or-out.of or within the reagtor should be accomplished,in accordance I
l with S97.0.C (Transfer of Fuel from the Fuel Pool to the Reactor), S97.0.D (Transfer of Fuel from the Reactor te the Fuel Pool) and S97.0.E (Transfer of Fuel Fithin 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 accounting records shall be assembled and the following logs and records updated:
1.
A-44-3, A-44-4 the Fuel Inventory Logs'for the Fuel Fool 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.
<. 3 C:V 5.7 SNM INVENTORY 5.7.1 Th'e plant process computer provides reactor thermal power and fuel burnup inforqation that the Technical Engineer should forward to the Fuel Managemen Section of the Ilectric Production Department.
5.7.2 The Fuel Managemen: Sectior. of the Electric P cdue: ion Department shall calculate the isotopic quantities of fuel present on site.
4 5.7.3 The Reactor Engineer shall conduct an inventory of all on site SNM annually or'when a 1
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 'nventory shall be repo:ted immediately by telephone to the NRC in accordance with 10 CFR 70 52 i
(Ref. 1).
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%d-5.7.4 The Reactor Engineer should forward tha results of inventories to the Fuel Management Section of the Electric Production Department.
5.7.5 The Fuel Management Section of-the Electric Production Department shall prepare NRC/ DOE-742 for transmittal, 5.8 CEANGES TO SNM AND SNM ACCOUNTING 5.8.1 If SNM other than fuele Sh:4s, 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, j
the Reactor Ingineer shall determine if existing procedures are sufficient to prot'ide adequate accounting.
2.
A permanent change to SNM may require changes to this procedure.
The Reactor Engineer shall determine the accounting needs of the new SNM.
f'!!l3 3.
New accounting procedures and changes to this procedure shall be performed in accordance with LGS Procedure A-1 ('leference i
7.2).
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5.9 SNM ACCOUNTING DOCUMENTS 5.9.1 A-44-la, Fuel Receipt / Tracking Data Sheet (Form M-21974) - This cheet indicates the location of fuel from receip: on site to storage in the Fuel Pool after the receipt inspection.
When fuel is stored in Temporary Storage rather than the New
. Fuel Storage' Area, A-44-lb must also be used and the "lb" column on A-44-la check'ed.
As a minimum this sheet shall contain:
arrival ~date and time, Container. Serial Numbers containinc
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seal numbers, Fuel Assembly Serial Number, transfer dates, location on the Fuel Floor
("pile" as r>pecified 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 Fuel intpected on Ruel Floor.
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5.9.2 A-44-lb,JTemporary Fuel Storade 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-is1 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 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, Fttel Inventory -Summary Sheet (Form M-21976) - This shee.t is a listing of the site MSAs.
The areas are as defined.in Step 4.2.
All fuel assemblies shall be accounted'for in-these MBAs.
Whenever fuel is received, shipped or transferred, the Fuel Inventory Summary Sheet
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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, n7; Temporary Storage,' Fuel Flo,or, Reactor and Fuel j
't-floor.
5.9.4 A-44-3, Fuel Inventory Log - Fuel Fool (Form M.
21977) A-44-4. Fuel Inventory Log-Core-(Form M-l 21978) - These logs are a location record of fuel assemblies in the Fuel Poci or-Core..The Fuel :nventory Logs are updated and verified "crrect at the completion of a fuel handling op. cation.
Normally, tabulations of Fuel Pool and Lare positions are used, however', ot.ker,,
j means are acceptable.
The fuel assembly serial nu.-ber is entered in the' space provided on the
,l log corresponding to the~ location in the Fuel Pool er 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 q
minimum A-44-3 shall contain the Unit Number, l'
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 Location, Fuel Bundle Serial Number, and Name and Date of person revising the form.
Both A-
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44-3 and A-44-4 should be approved by the pg Reactor Engineer.
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Each fuel' assembly shall have a tag identifying the serial number.
The tags will be moved as-its corresponding fuel assembly is moved.
While
.i the Tag Boards should be kept as accurate as possible, they are used for information only and do not constitute an official fuel accountability record.
5.9.6 A-44-5, Fuel Location History Sheet (Form M-A 21979) - Fach fuel assembly on site shall have a Fuel Location History Sheet after placement in the fuel pool.
The sheet heading has spaces for 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 8.
Date Out g.',;
Fuel assembly locations are to be logged-only
'C.
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 mus be shown.
The "Date Out" and "Date In" entries should be the date the bundle is verified to be in its proper location for mcVes made during a fuel
[
handling operation.
Non-outage fuel moves should be dated as performed.
Temporary storage locations anc time of movement are recorded on the CCTA$.
5.9.7 Core Component Transfer Aushorization Sheets i
(CCTAS) - The CCTAS provides a sequential listing of the fuel and core component movements to be performed and shall be used by the Fu11 Handling director in performing the fuel handling operation.
The CCTAS is a Form (M-21965, 21966, 21967) that is referenced from the applicable FH Procedure. A CCTAS is required for all fuel movements following initial inspection i
and storage in the fuel pool.
A CCTAS should include the following information:
(D-1.
Signature of person authorizing the work.
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Date' authorized.
3.
Column for Step. Number
'4.
Column..for Serial Number 5.
Column-for From Location
-6.
Column for Orientation inL"From" column 7.
Column for To Location 8.
Column for Orientation in."To" column 9.-
Columns as required-for initicls of personnel-required'to document the transferi.
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- 10. Column for Time of Transfer
- 11. Column for Date of Transfer 5.9.8 A-44-6, Non-Fuel Receipt and Storage Data Sheet (Form M-21980).- This sheet is required when' i
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 eOg M3A.
Whenever a fission chamber is received, V's shipped or transferred, A-44-7 should be-updated.
The total fission chambers on site shall equal the sum of the MBAs.LAs 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.
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,i 5.9.10 A-44-8, Fission Chamber Transfer Authori:ation Sheet (FCTAS),(Form M-21982)-- The Reactor 1 Engineer or his designated representative'shall
'l fill in the form before signing the
,l authorization.
The pe.rson performing the move tl 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 5.4.4). As 1
a minimum this sheet shall contain:
the Unit Number, Authorized By, Date, Detector Type, i
Serial Number,'MBA presently located and future 8
MBA location, Init.'als and Date.
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~'*1 5.9.11.A-44-9, Fission. Chamber Location History Sheet -
-(Form M-21983) Each fission' chamber requires an
- j 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 1
this. sheet shall contain:.the Unit Number, 1
Detector Type, Serial Number,-Date received, Location-and Date In and Date out.
j 5.9.12 Retention of. documents shall:be'as-follows:
1 1.
Appropriate data sheets,~1ogs, and summary
' J i
sheets generated by this procedure,shall'be kept'in the Reactor Engineer's office or j
when the Data-Sheet,. Log or Summary Sheetyis.
' )
filled up it may be transmitted to Nuclear Records Management for retention.
2.
The Reactor Engineer shall-provide the-Nuclear Records Management (NRM) System with legible copies of the'A-44-3Truel Inventory Log, Fuel Pool (Form M-21977) and A-44-4 i
Fuel Inventory Log Core (Form M-21978).
-i 3.
Health Physics Supervis' ion shall' provide NRM' 4
- h[.4 with appropriate Health Physics documents relative to the SNM as per Health Physics
-l Procedures, y
l 5.10 Materials Control Management I
5.10.1 Periodi audits of the Fuel Handling redords are initiated by the NRS (Nuclear Review Board)
=
using independent auditing agents, j
6.0 REF RENCES
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6.1.
10 CFR,~Parh 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,re 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
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6.5 S97.0.D Tranrfer of Fuel from the Reactor to the Fuel Pool (hh 6.6 S97.0.E Transfer of Fuel Within'the Reactor i
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l 6.7 A-46 Procedure for Maintenance of Plant Quality, Assurance Records.
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