ML20235G631
| ML20235G631 | |
| Person / Time | |
|---|---|
| Site: | 07003013 |
| Issue date: | 03/18/1986 |
| From: | Leverenz K COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20235F489 | List: |
| References | |
| 1-1, NUDOCS 8707140325 | |
| Download: ML20235G631 (35) | |
Text
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Commonwealth Edison Company NUCLEAR PROCEDURE NO.1 7
Effective: March 18,1986 Organization, Responsibilities, I
and Facilities for Controlling 1
Supersedes Nuclear Procedure No.1, and Safeguarding Nuclear Material dated 1-20-84
(
The organization, responsibilities, and facilities comprising'the Company?s Nuclear Material Control System, providing a system for detecting any loss or -
unauthorized diversion of, nuclear material, in compliance with regulations ~
issued by the Nuclear Regulatory Comission (NRC) and the American National Standards' Institute Standard (ANSI-N15.8-1974) Nuclear Material Control' Systems for Nuclear Power Plants, is outlined in Nuclear Procedure-Nos.1 through 8.
It should be noted that any incident in which an attempt has been made, or is believed to have been made, to commit a theft or unlawful diversion of nuclear material, shall be reported immediately by telephone as provided in General Company ~ 0rder No.19. The Nuclear Materials Safeguards Manager will be responsible for the reporting of such incidents to the NRC as required by NRC regulations.
A.
Organization and Responsibilities
(
Nuclear Materials Safeguards Manager (NMS Manacer)
A NMS Manager shall be designated in writing by the President of the Company, or his designated alternate, as an " Authorized Individual'
.having the overall responsibility for surveillance and control of nuclear material in the possession of the Company. The NMS Manager shall report to the Comptroller of the Compan/ ar.d be responsible for:
1.
Implementation of the Company's nuclear material control system as prescribed in Nuclear Procedure Nos.1 through 4.
2.
Preparing and filing Nuclear Material Transaction Reports and Nuclear Material Balance Reports and Physical Inventory Listings as may be required by the NRC or other regulatory authority.
3.
Maintaining a complete record of ' Authorized Individuals' and other persons having the responsibility for surveillance and control of nuclear material.
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Organization'and ResD0nsibilities Assistant Nuclear Materials Safeauards Manaaer'( Assistant NMS Manaaer)
(
An Assistant Nds Manager shall be designated in writing by the President of the Company,' or his designated alternate, as an
' Authorized Individual" having the responsibility of assisting the NMS:
Manager,in the implementation of the Company's Nuclear Material. Control System..The Ass.istant NMS Manager shall: report to the NMS Manager and shall serve as his alternate when required.
- Station Manaaer and Services Superintendent The Station Manager and.the Services Superintendent at' each nuclear.
generating station shall be designated in writing by the President'of-the Company, or his designated alternate, as." Authorized Individuals"-
having the responsibility for the overall physical control of nuclear material and for the implementation, administration and compliance with th.e requirements of the Company's Nuclear Procedures, Security Plan, NRC licenses and other applicable regulations with respect to their respective nuclear generating stations.
They shall also be responsible for taking prompt action to correct any deficiencies disclosed.as a result of Quality Assurance audits performed at their respective stations and for reporting the corrective action taken (or justification if no action is taken) to the; Manager of.
(
Quality Assurance and, if Security Plan activities or procedures are involved, to the Nuclear Security Director.
- Nuclear Materials Custodian (NM Custodian)
A NM Custodian for each nuclear generating station shall be designated in writing by the Services Superintendent. The Services Superintendent may also designate in writing an alternate for a Nuclear Materials Custodian.
The NM Custodian or his alternate shall'be responsible for performing the functions that relate to the control of nuclear materials at each plant site. He shall also be responsible.for: - (l) inventorying and maintaining records of the movements and locations of all special nuclear material within the Item Control Areas (ICAs) assigned to him, (2) ensuring that all fuel vaults are properly secured after each inventory or other use, and (3) preparing all necessary reports to verify all receipts of nuclear fuel delivered to the station, all shipments from the station and all transfers within the station site.
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Organization and Responsibilities Fuel Handlina Foreman
(
The Fuel Handling Foreman shall be' responsible'for reporting all fuel movements under his supervision, as required by the Nuclear. Procedures, to the NM Custodian, ensuring that all fuel vaults are secured properly after each use, and for maintaining up-to-date Tag Boards showing the current location of all fuel assemblies.
j j
Director of Auditina j
The Director of Auditing shall be responsible for observing and performing audit tests of physical inventories of nuclear fuel assemblies in a Reactor upon completion of and insnediately prior to installing the reactor head.after initial fueling, refuel _ing, or rearrangement of fuel, and of reportable quantities of.Special Nuclear.
Material in Fuel Pools. Fuel Vaults, and other storage locations when such audited inventories are required.
He shall also be responsible for performing annual audits to ensure compliance with the Company's Nuclear Procedures and such other audits as requested by the NMS Manager.
- Nuclear Fuel Services Manacer j
The Nuclear Fuel Services Manager shall be responsible for the operation of the Nuclear Component Accountability System (NCAS) which shall include.the recordkeeping for all nuclear fuel-assemblies, the computation of all nuclear fuel burnup, and the total element an.d isotopic composition of all nuclear material in nuclear fuel assemblies in the possession of the Company. He shall document and retain for NRC audit purposes the methods used in the computation and compilation of nuclear fuel data for inclusion in the NCAS.
The Nur. lear Fuel Services Manager in conjunction with General Procedures Department shall be responsible for coordinating proposed changes to the Company's Nuclear Procedures with responsible departments and area's. The Nuclear Fuel Services. Manager is responsible for obtaining and defining Company policy with respect thereto and submitting to the Director of General Procedures, after j
consultation with the affected departments, and with the concurrence of i
the Nuclear Materials Safeguards Manager, recommendations.and j
instructions for changes to the Company's Nuclear Procedures.
- All suggested additions, deletions, or revisions to the Company's Nuclear Procedures shall be submitted by the initiating department or area to the Nuclear Fuel Services Manager with copies to the NMS Manager and the Director of General Procedures.
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Organization and' Responsibilities Manaaer of Fuel
[.
The Manager of Fuel shall be responsible for purchasing. nuclear fuel and. requiring that vendors supply certification withl respect to. the-enrichment and quantities of nuclear fuel detemined in a manner satisfactory to the Company. He shall arrange for transportation of '.
nuclear fuel and shall qualify carriers to ensure that NRC requirements will be met by carriers.
He shall be responsible for purchasing fuel cycle-services and i
arranging fur the disposition of spent fuel and residual materials.
-)
Director of Nuclear Licensine
'The Director of Nuclear Licensing shall.be responsible for submitting applications to the NRC'and the States of Illinois and Indiana, as applicable, for licenses and certificates of registration and such revisions thereto as may be necessary. He shall maintain the master file of all licenses and certificates, including applications, application support material..NRC approval letters, and all revisions' to the licenses or-certificates.
He shall issue updated copies of the licenses and certificates, control f'
the distribution of copies for use within the Company and arrange for
(-
periodic physical inventories, as prescribed in the governing regulations referenced in N.P. No. 6, of all. radioactive materials (except for Nuclear Fuel) covered by each license or certificate.
Manacer of Ouality Agurance The Manager of Quality Assurance, as set forth in Section b uf this' procedure and as provided in the Capany Nuclear Quality Assurance'
.j Program Nanual, shall be responsible for performing audits of:
l compliance with the Security Plan and the relevant procedures in effeet i
at each nuclear generating station and for assuring timely corrective action of deficiencies identified during audits.
Similarly, he shall be responsible, as prescribed in Nuclear Procedure No. 6. for periodic auditing to assess compliance with the NRC licenses and other applicable regulations.
Written reports covering such audits shall be distributed to:
Vice President - Nuclear Operations Station Manager / Services Superintendent Nuclear Security Director 100929a 3/86
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N.P. N3. 1 Page 5
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A.
Organization and Responsibilities
- Nuclear Security Director
. n
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The Nuclear Security Director shall be responsible for the development of a Security Plan for each " protected area" as prescribed in 10 CFR 50.34 and 10 CFR 73.55 and for providing assistance to the Service's Superintendents in the preparation of procedures (ANSI Standard, N18.17) to implement the Security Plan. He shall assist the Services Superintendents, as required, in the implementation of the procedures to ensure that security requirements of the protected areas are satisfied.
He shall also be responsible for following-up to ensure the receipt of reports from department heads involved indicating actions taken to correct any security deficiencies disclosed as a result of Quality Assurance audits and for initiating appropriate revisions to the Security Plan and relevant procedures that may be required as a consequence of the audit findings'.
l I
8.
Nuclear Generatinq Station as a " Protected Area" j
j' A nuclear generating station shall be a " protected area" as
(
prescribed in 10 CFR 73.55. As such, the Station must be accompassed by a physical barrier and access to the Station must be coi; trolled.
2.
The Services Superintendent shall prepare and implement procedures (ANSI Standard, N18.17) for controlling access to the protected area. A copy of the station's Security Plan and procedures which implement the Security Plan, and all revisions thereto, shall be sent to the Manager of Quality Assurance and the Nuclear Security Director.
3.
At least once each year, the Manager of Quality Assurance shall audit compliance with the Security Plan and relevant procedures in ef fect at each nuclear generating station. Written reports shall be prepared and distributed and follow-up will be made for corrective actions required as provided in Section A of this procedure.
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g, Safecuardine Fuel Vaults The safeguards protection required 'for_ Fuel Vaults when nuclear fuel is present will vary depending upon their construction and location.
1.
Dresden 1 Fuel Vault 1
a.
Dresden'1 Fuel Vault,' Item' Control Area VDl, shall be locked-I with a three-position, manipulation _ resistant, dial-type, combination padlock at all times except when authorized work is in progress..The Fuel Handling Foreman will ensure that the vault is secured properly and the NM Custodian will verify that the' vault is locked when authorized work.is halted at _the end of each shift if no work is planned for the.following shift.
b.
Two copies of the combination shall be retained. One shall be-in the Services Superintendent's per'sonal custody, and the other shall be kept in a locked container in the office of the. station administration building.
c.
Access to the combination shall be restricted to the Station Man 4ger, the Services Superintendent, the Assistant Superintendent Technical Services, the NM Custodian, the Shif t Engineers, and the Fuel Handling Foreman.
d.
The NM Custodian will immediately notify the Station Security
(
)
Administrator whenever the vault is found in an unsecure s
condition and no authorized work is in-progress. The Security Administrator will arrange for surveillance'e of the vault until such time as it is properly secured.
e.
An investigation of the circumstances leading to the unsecured' condition will be conducted in accordance with normal station i
procedures for handling deviations.
-)
2.
All Other Fuel vaults a.
The Fuel Vaults shall be secured by concrete block covers nr locked metal grates at all times when fuel is present, except-J when authorized work is in progress.
b.
The covers need not be put back in place if work-is temporarily i
halted.
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Safeauardino Fuel Vaults-2.
(Continued) c.
The covers shall be put back in place at the end of~each
[
shift if no authorized work is planned for the following j
shift. The Fuel Handling Foreman will ensure that.the covers are secured properly and the NM Custodian will verify that the covers or locked metal grates' are~1n place when new fuel is in.the vault.
1 d.
The NM. Custodian will immediately notify the Station.
Security Administrator whenever.the vault is found in an unsecure condition and no authorized werk is in progress.
I The Security Administrator will arrange for surveillance of the vault until such time as it'is properly secured.
e.
An investigation of the circumstances leading to the unsecured condition will be conducted in accordance with normal station procedures for handling deviations.
9 i
3.
The following is applicable to all Fuel Vaults when' fuel containing plutonium is present:
{
a.
The Vault may be protected by an intrusion alarm (as j
(
defined in Title 10 CFR 73.2) capable of detecting
)
(
intrusion by an individual into the Vault by means of a visible or audible signal sufficient to summon guards or watchmen immediately so they arrive at the. vault within J
five minutes.
b.
When in use, the intrusion alarm shall be inspected and tested for operability and required functional performance at intervals not exceeding seven days. Records of such tests-and inspections shall be kept by th,e NM Custodian, c.
Where an intrusion alarm has not been-installed or is not operable, the Vault shall be protected by"a guard or a
~
watchman who shall patrol at intervals not exceeding four hours. The guard or watchman shall record in an appropriate log (Form 86-2605) the time and results of his inspection of the Fuel Vault.
d.
The patrol log and the record of intrusion alarm tests shall be made ava116ble, as required, for examination by representatives of the Director of Auditing, the Manager of Quality Assurance, and the Nuclear Security Director.
s 100929a
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Page 8 D.
ReDortinQ Identification Symbols (RIS) 1 The NRC has established specific reporting identification symbols which' i
f the Company is. required to use in submitting Material Balance Reports and
]
Physical Inventory Listings and Nuclear Material Transaction Reports to the NRC.
The presently authorized RIS's are:
l Symbol Nuclear Reactors ZED Dresden 1
YVE Oresden 2
YYF Dresden 3
YUA Quad-Cities 1
XEL Quad-Cities 2
XEX Zion 1
YZM Zion 1
2 2S8 LaSalle Cty ISS LaSalle Cty 2
XYS Byron Unit 1
i XYT Byron Unit 2
XWX Braidwood Unit 1
/
XYU Braidwood Unit 2
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E.
Item Control Areas (ICA's)
The following Item Control Areas (ICA's) are designated for the Company's nuclear. generating stations:-
VD1 Dresden 1 Fuel Vault P01 Dresden 1 Fuel Pool RD1 Dresden 1 Reactor.
S01 Dresden 1, Other Protected. Location (c).
V02 Oresden 2 & 3 Fuel Vault-(a).
P02 Dresden 2 Fuel Pool P03 Oresden 3 Fuel Pool 1
R02 Oresden 2-Reactor i
R03 Dresden 3 Reactor S02 Dresden 2 Other Protected Location (c)
S03 Dresden 3 Other Protected Location (c).
VQ1 Quad-Cities.1 & 2 Fuel-Vault (a)
PQ1 Quad-Cities.1 Fuel Pool (b)
PQ2 Quad-Cities 2 Fuel Pool (b)
RQ1 Quad-Cities')
Reactor RQ2 Quad-Cities 2 Reactor SQ1
. Quad-Cities 1 Other Protected Location (c)
SQ2 Quad-Cities 2 Other Protected Location (c)
(
VZ1 Zion 1 & 2' Fuel Vault (a)
PZ1 Zion 1 & 2 Fuel. Pool (a)
RZ1 Zion 1 Reactor RZ2 Zion 2 Reactor 511 Zion 1 Other Protected Location (c) 522 Zion 2 Other Protected Location (c)
VL1 LaSalle County 1 & 2 Fuel Vault (a)
PL1 LaSalle County 1 Fuel Pool- (b)
PL2 LaSalle County 2 Fuel Pool (b)
J' RL1 LaSalle County 1 Reactor-RL2 LaSalle County 2 Reactor SL1 LaSalle County 1 Other Protected Location (c)
SL2 LaSalle County 2 Other Protected Location (c)
VY1 Byron 1 & 2 Fuel Vault (a)-
PY1 8yron 1 & 2 Fuel Pool (a) j RY1 Byron 1 Reactor l
RY2 Byron 2 Reactor SY1 Byron 1 Other Protected Location (c)
SY2 Byron 2 Other Protected Location (c)
]
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I E.
Item Control Areas (ICA's)
ICA No.
Unit location f:
VW1 Braidwood 1 & 2 Fuel Vault (a)
PW1 Braidwood 1 & 2 Fuel Pool (a)
RW1 Braidwood 1 Reactor RW2 Braidwood 2 Reactor SW1 Braidwood 1 other Protected Location (c)
SW2 8raidwood 2 Other Protected Location (c)
(a) Single facility used by two units l
(b) Two pools connected by a water channel J
(c) For temporary storage,9JLly.
Includes the following-specific locations:
1.
On the. receiving / shipping vehicle ' located in the reactor building or within the protected area of the yard.
2.
In shipping containers within the reactor building or fuel but1iing.
3.
In fuel handling fixtures.
4.
Other locations - cannot be utilized without the prior approval of the Nuclear Materials Safeguard Manager. When
(
utilized, around-the-clock surveillance must be.provided.
i F.
Nuclear Fuel Assembiv Records The NM Custodian of each nuclear generating station shall maintain records of all fuel inventories, receipts, shipments, transfers, and all other records as may be deemed necessary by the HMS Manager pertaining to nuclear fuel safeguards required by the NRC and/or th,e International Atomic Energy Agency (IAEA).
Nuclear Fuel Services Department through its NCAS shall maintain records for all nuclear fpel assemblies in the possession of the Company. Such records shall include: dates of receipts, transfers and shipments; quantities of nuclear materials received, fissioned,- produced, decayed, transferred and shipped; exposure; inspection results; audit dates; and countries of origin. The methods used in the compilation of nuclear fuel data contained in the NCA5 shall be documented and maintained by the Nuclear Fuel Services Manager for NRC audit purposes.
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Forns and Records t
See attached Appandix.
Instructions covering the use of the forms and I.
records described and/or depicted in the attached Appendix are incluced in Nuclear Procedures Nos. 2 through 8.
/
Director of General Procedures
]
APPROVED:
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Vice President
./
i Vice President and Comptroller 1
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N.P. N3. 1 App;ndix Page 1
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NUCLEAR FUEL FORMS AND RECORDS (Samples of typical forms are attached. They may vary from Station to Station).
I Form Nos.
Descr1Dtion oP Title 86-1584 Nuclear Fuel Receiving Report (Form A) 86-2593 BWR Nuclear Component Transfer List (Form C) 86-2616 PWR Nuclear Component Transfer List (Form C) 86-2592 Nuclear Fuel Location and Exposure Record (Form E) 86-2606 Report of Nuclear Fuel Audit for the Nuclear Fuel Services Department 86-2610 Inventory of Non-Fuel items Containing SNM 86-2602 Rail Cask - PWR - 7 Cell (Form K) 86-2603 Rail Cask - BWR - 18 Cell (Form K) 86-2601 Truck Cask - PWR - 1 Cell (Form M) 86-2600 Truck Cask - BWR - 2 Cell (Form M) 86-2604 Truck Cask - BWR - 7 Cell (Form M) 86-2611 Truck Cask - PWR - 3 Cell (Form M) 86-2605 Watch Patrol Report - Fuel Vaults (Form P) 86-2524 Radioactive Materials Shipment Record Form F Fuel Vault Inventory
(
Form 6 Fuel Pool Inventory Form H Reactor Core Map Form J Nuclear Fuel and Channel Inspection Data Sheet Record Descriptions Fuel Assembly Tag Board - Indicating up-to-date location of fuel assemblies for each ICA Reports of receipts, inventories, transfers or shipments of nuclear u.aterial Reports of inspections nf the Protected Area Reports of inspections of Fuel Vaults Other reports as required by appropriate NRC and IAEA regulations and as deemed necessary by the NMS M.anager Note: Supplies of the above numbered forms can be obtained by forwarding an approved Form Request (86-9001-5) to General Procedures Depa rtment. The aloha-coded forms will be designed and copies reproduced by the individual stations as needed.
ID0929a 3/86 I
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. RAIL' CASK-GENERAL ELECTRIC CO.
IF-300 n., _
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7 PWR 7 CELL FUEL BASKET C.E.Co.
86-2602 8-80 N.P. 1 3/86 O
- 1 i
C.E.co..
RAIL CASK N.P. No. 1 GENERAL ELECTRIC CO.
Appandix
'Page 8
.j IF-300, 1
b 4
1 2
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1 5
6 7
8 9
i
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'14 15 16 17 18 BWR 18 CELL FUEL.BASKrF C.E.Co.
86-2603 8-80 N.P. 1 3/86
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N.P. No. 1 Appendix
, 3, Page 9
~
TRUCK CASKS
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PWR 1 CELL FUEL BASKET C.E.Co. 86-2601 8-80 N.P. 1 3/86
- .: r.
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N.P. No. 1 Appendix Page 10
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1 TRUCK CASKS-
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N.P. Ib. 1 -
Apperx11x Page 12.
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N.P. No. 1 RADIOACTIVE MATERIAL ZICPMI2fT RICCRD App 3ndix c.t.co. ns.as sgs:
..te ro, rrem:
Pega 14
/
(
Attn.:
Phone at Consignee License *:
Shipper:
- hie-ent ;. s e ri e tion cactive Mat'l Descriptions
- . deipal Nuclides:
Total Activity:
S rt es Physical Torm O Solid O Liquid O cas Chemical Term:
Fe r.n Transpert Creup tuantit*
O Normal OI O II O III
- 7 SA O Type A i
O Opecial O 77e 5
O rissile O7 0 7.
O 7I:
O small 0 arse
)
Fissile fissile Wei6nt F.nrienment IFissile Vatertal Cnbj Fissile class Isotece (Grams)
( P e ra e n t
O Exempt O Class I:
T:/Pxo j
Approved:
O Class Class !!!*
l NM Custodian
- Warning - Fissile Class III thipment. Persennel Handling and : towing this Ihipment Must be Advised to not Lead More Than i'ackages per.*ehicle.
In any *cading er itewage f
Area, this Shipment Must be 3egregated oy at feasc 20 Feet."rcm Cther *ackages tearing Padtemetive tabels.
Peckage
Description:
Orocs Weight of Shipment:
Its Orcss Volume of shiemset:
- *e Package: O Exempt Type A Type 9 O arce cuantity D.c.T. : pee. ~ or n tC pecial Permit.:
f "2diatinn Fretaetien 01reet Padistien ?urv*Y Type Labels and " yam n
- Package:
mrem /hr :. Contact O Radioactive '4hite :
O 'radicac*tve" Package:
mrea/hr ; 3 ft. (Transport 'ndex)
Radioactive 'ellcw :*
O rpt7
'/shicle s mrem /hr a Contact (Jole Use Only s radioactive ellcw !!!
'ther:
7ehicle:
trem/hr.r o ft.
(Cole "se Only, O " Radioactive :A :e ise.1
- t ar-Cab:
mrem /hr maximum
.(3 ole Use Only)
" Radioactive "aterial - No Label Kequired" knt aminatien Iurvaar pecisi ?cauira ents 2
2 Pacnage: O Avg 3 g i 22 dpm/cm and Max A*I i 220 opm/cm O Vehicle Placarded Package O Avger 12.2 dpm/cm2 and Maxer 122 dpm/cm2 O ;ecurity Seal Affixed to Package (s)
'ishitle (Common Carrier): O so significant Pamovable Centam.
O Packace maintenance / Opening Instructions Max. 0.E. g 0 5 mrem /hr "i Centact (See Feverse Side)
'lehicle (Sole Use): O Max 110 mrem /hr i Contact Max. $ 2 mrem /hr 3 3 ft.
Signature of Surveyor:
Comments:
Ce rti ficatien O ':his is to certify that the above named articles are preperly classified, descrited, pacr. aged, marked, and lateled sad are in preper condition fer transportation accordind to the applicable regulations cf the Department of Transportation.
O This is to certify that the contents of th.a.: consigreent are preperly described by name and are packed, marked and lateled and are in prepar conditien for carriage by air according to all applicable carrier
(
and governmental regulations. This consignment ir within the limitations prescribed fer:
O Passenger Aircraft only 3/86 O Cargo Aircraft only Approve 4 By:
Cates
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1 C.E.Co.
FORM F
'N.P. No. 1 Appendix j
NUCLEAR GENERATING STATION RIS Pcga 15 FUEL VAULT lavtausRY ICA f
/
6 t
Date:
i
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ROW l
1 A
B C
D E
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I Aav.IuORIED BY NM Custodian CBSERVERS l.
APPROVED FORM F N.P. 1 stRvicts suMRINTENetwr 3/86
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51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 INVENTORIED BY DATE 3/BG oeSERVERS
.q APPROVED n oseu e m aiarcauwr
'N.P. 1 rom. n s
+9 858+aW e est e9ED
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C.E.Co.
FORM J N.P. No. 1 1
Appendix Page 18 NUCLEAR FUEL AND CHANNEL INSPECTION DATA SHEET Assembly No.
,-s Channel No.
(if applicable)
FUEL ASSEM81.Y INSPECTION Initial 1.
All shipping spacers removed.
2.
Fuel assembly cleaned and checked 3.
Visible fuel rod free of scratches, nicks, or dents in excess of 0.003 inches deep.
4.
Visible fuel rods s'eated against lower tie
]
plate, except tie rods which may be backed off seat to a maximum of 0.005 inches axial gap.
5.
Top nuts on tie rods are in place and locking i
tabs on lock tab washers are properly bent.
f'3 6.
Tie rod nut clearance between mating surface j
less than 0.01 inches on one nut per side of i
fuel assembly.
7.
All spacers visually examined for shipping damage (broken welds, bent bands, bent bars or dividers) and lobes are smooth and free of burns or galled metal.
8.
Rod to rod spacing of 0.109 inches checked in each section (from spacer to spacer to tie plate) between spacers.
9.
Rod to water rod spacing checked in each 1
section, each direction (0.055 inch minimum spacing).
10.
Rod to simulated channel spacing (0.121 in'ches) checked for each face.
ID0929a
_ j 3/86 A
-e p
C.E.Co.
N.P. No. 1 Appendix Page 19 r
i I
11.
All-accessible rods are tight in each spacer with a maximum of 0.015 inches clearance between fuel rod and spacer contacts.
12.
Spring length of each of the 4 corners not less than 1.28 inches and not greater than 1.42 inches.
13.
All springs undamaged and not missing.
14.
Corner rod to spacer corner radius clearance checked and greater than or equal to 0.036 inches.
15.
Finger spring to lower tie plate slot minimum dimension checked in 8 places (greated than 0.005 inches) (if applicable).
~
16.
Condition of all four finger 3prings checked for gross deformation (indentation, ripples, etc.)
17.
Upper tie plato checked for correct location of different enrichment, poison, pins, etc., and that fuel pins are in their correct location.
Correct orientation of engraved serial number f
(_!
on bale verified.
FUEL CHANNEL INSPECTION (If Applicable) 1.
All surfaces of' fuel channel clean and f ree of finger marks, oil smears, dirt, dust, or other contamination.
2.
All channel surfaces f ree of cracks, gouges, dents, and any other questionable defects (dents up to 0.006 inches acceptable).
3.
Channel tabs and welds free of cracks or any visible distortion.
4.
Channel free of visible distortion (bow, sides not square, sides convex or concave).
Inspection Completed (or witnessed) by Ceco Fuel Inspector y,.-
Date Completed ID0929a 3/86
- i. j
-.. ~
C N. P. ~ Nos. 1 -8 i
Appendix R t ')
Page 1 of 4
/
Record Retention Relatino to This Procedure PART I 1
- 0ffice of Record /
Item Form No.
Description of Form / Record Responsible Deot.
1.
86-2584 Nuclear Fuel Receiving NMS Manager Report (Form A)
NM Custodiar
)
2.
86-2593 Orig 8WR Nuclear Component NM Custodian Dup Transfer List (Form C)
Nuclear Fuel Services 3.
86-2616 Orig PWR Nuclear Component NM Custodian Dup Transfer List (Form C)
Nuclear Fuel Services 4.
86-2592 Nuhlear Fuel Location NM Custodian 1
and Exposure Record (Form E)
/' ' ' s 5.
86-2606 Report of Nuclear Fuel Audit Nuclear Fuel Services
(- '!
for the nuclear Fuel Services Department 6.
86-2610 Orig Inventory of Non-Fuel Items NMS Manager Dup containing SNM Tech Staff 7.
86-2602 Rail Cask-PWR-7 Cell (Form K)
Tech Staff 8.
86-2603 Rail Cask-BWR-18 Cell (Form K) Tech Staff 9.
86-2601 Truck Cask-PWR-1 Cell (Form M) Tech Staff 10.
86-2600 Truck Cask-BWR-2 Cell (Form M) Tech Staff 11, 86-2604 Truck Cask-BWR-7 Cell (Form M) Tech Staff 12.
86-2611 Truck Cask-BWR-4 Cell (Form' M) Tech Staff ID0929a
- 3/86 J
i 1
N. P. Nos. 1 -8 n
(
I Appendix R Page 2 of 4 m
Record Retention Relatinc'to This Procedure PART I i
- 0ffice of Record /
11 3 Fom No.
Description of Fom/ Record ResD0nsible Dept.'
13.
86-2605 Watch Patrol Report - Fuel Tech Staff Vaults (Form P).
14.
86-2524 Radioactive Materials NMS Manager Shipment Record 15.
Fom F Fuel Vault' Inventory Tech Staff 16.
Form 6 Fuel Pool Inventory Tech Staff-17.
Form H Reactor Core Map
, Tech Staff i
(
'4 18.
Fom.1 Nuclear Fuel'and Channel Tech Staff
( /
Inspection Data Sheet Nuclear Material Transaction NMS Manager 19.
Report (DOE /NRC Forn 741)
{
i 20.
Operating License Tech Staff 21.
Special Nuclear Materials Tech Staff License 22.
By-Product Material License Tech Staff 23.
Radioactive Materiai License Tech Staff i
l 1
100929a i, y 3/86 1
1 N. P. Nos. 1-8 Appendix R Page 3 of 4 Record Retention Relating to This Procedure PART II s
(
(
Retention Policy Office of Rec / Valuable Retention Type of Record item Respon. Dept.
Pacers Archives Requiation Record (A)
Code
- 1. (1)
LP Q.P. 17-51 Paper 007710
- 2. Orig.
LP Q.P. 17-51 Paper 007710 Dup LP Q. P. 17-51 Paper 011060
- 3. Orig.
LP Q.P. 17-51 Paper 007710 i
Dup.
LP Q.P. 17-51 Paper 011060 a
4.
LP Q.P. 17-51 Paper 007710
- 5. (2) 1LP Q.P. 17-51 Paper
- 6. Orig.
1 LP Q.P. 17-51 Paper Oup.
Q.P. 17-51 Paper 7.
5 Q.P. 17-51 Paper
(,, '
8.
5 0.P. 17-51 Paper i
s, 9.
5 Q.P. 17-51 Paper 10.
5
- 0. P. 17-51 Paper 11.
5 Q.P. 17-51 Paper 12.
5 Q.P. 17-51 Paper (1) Life of Plant Indicates Years for Retention (2) Indicates Years after Life of Plant to Retain Approved by Record Retention Committee Date Note (A):
Paper = Paper form or document; Printout (including System Code Name) = Computer Listing; Fiche (including System Code Name) a Microfiche; Film = Microfilm.
This Appendix R is used to maintain and add to the department Record Retention and Storage Manual. Records (generally copies) mentioned in this Procedure which are not included in Appendix R should be considered
" Destroy at Option'.
If there is a conflict between Appendix R and your
(
department Record Retention and Storage Manual, follow G.P.136 to set
' ~'
the retention policy.
100929a 3/86
j
'j N. P. Nos. 1-8 i
f Appendix R Page 4 of 4 1
l 1
Record Retention Relating to This Procedure 1
PART II I
Retention Policy Office of Rec / Valuable Retention Type of Record it,t!!!
Re5 Don. Dent.
Pacers Archives Regulation Record (A)
Code 13.
1 LP Q. P. 17-51 Paper 14.
5 Q P.17-51 Paper
- 15. (1)
LP Q.P. 17-51 Paper-j l
16.
LP Q. P. 17-51 Paper 17.
LP Q.P. 17-51 Paper 18.
LP Q.P. 17-51 Paper j
(s
.. -/ ' 19.
LP Q.P. 17-51 Paper l
20.
LP Q.P. 17-51 Paper 21.
LP Q. P. 17-51 Paper l
Q. P. 17-51 Paper
)
12.
LP 23.
LP Q. P. 17-51 Paper I
)
Approved by Record Retention Committee Date
]
Note (A):
Paper = Paper for1n or document; Printout (including System Code Name) = Computer Listing; Fiche (including System Code Name) = Microfiche; Film = Microfilm.
i This 4ppendix R is used to maintain and add to the department Record Retention and Storage Manual. Records (generally copies) mentioned in 4
this Procedure which are not included in Appendix R should be considered
" Destroy at Option".
If there is a conflict between Appendix R and your.
j department Record Retention and Storage Manual, follow G.P.13b to set the retention policy.
1
\\
^j ID0929a 3/86
.