ML20235G691
| ML20235G691 | |
| Person / Time | |
|---|---|
| Site: | 07003013 |
| Issue date: | 03/18/1986 |
| From: | Leverenz K COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20235F489 | List: |
| References | |
| 3-1, NUDOCS 8707140346 | |
| Download: ML20235G691 (11) | |
Text
.
Commonwealth Edison Company NUCLEAR PROCEDURE NO. 3 Effective:
March 18,1986 Safeguarding and Controlling Movements of Nuclear Fuel Supersedes Nuclear Procedure No. 3 Within a Station dated 1-20-84 The procedures for safeguarding movements (transfers) of nuclear fuel assemblies and nuclear fuel rods within a Station are outlined below. A
' Transfer' includes a ' reassignment
- of fuel assemblies (or rods) from one RIS to another even though no physical movement takes place.
The procedure consists of two sections:
A.
Transfers of Nuclear Fuel Assemblies or Fuel Rods Between or Within Fuel Vaults and Pools i
B.
Transfers of Nuclear Fuel Assemblies To and From Reactors A.
Transfers of Nuclear Fuel Assemblies or Fuel Rods Between or Within Fuel Vaults and Pools Area Responsible Action NM Custodian or 1.
Prepare BWR Nuclear Component Transfer His Alternate List (Form 86-2593) or PWR Nuclear Component Transfer List (Form 86-2616) as appropriate, numbered consecutively by year, showing the following for each fuel assembly or fuel rod movement required in accordance with Station Operating Procedures:
~
Step No. (Sequence to be followed in moving fuel)
Fuel Assembl,y or Fuel Rod Serial Number From ICA (Present Vault, Pool, or Other Authorized Storage Location)
To ICA (Proposed Vault, Pool, or Other Authorized Storage Location) a.
If transfer involves a change from one reactor (RIS) to another, promptly notify NMS Manager of proposed transfer.
h b
c ID0771a 3/86
C.E.Co.
N.P. No. 3 Page 2 I
A.
Transfers of Nuclear Fuel Assemblies or Fuel Rods Between or Within Fuel Vaults and Pools Area Responsible Action NM Custodian or 2.
Forward Nuclear Component Transfer List.
His Alternate together with any other required instructions, to the Fuel Handling Foreman.
a.
Retain copy as follow-up to. report completion of transfers.
b.
For on-shift changes to the step-by-step Nuclear Component Transfer Lists that do not change the intent of the procedure, obtain the approval of the Fuel-Handling Foreman and a senior licensed operator or two senior licensed operators.
Fuel Handling Foreman 3.
Supervise the execution of the steps listed in the. Nuclear Component Transfer i
List.
a.
Verify and initial each step.
b.
Update Tag Board.
c.
Sign and forward executed j
Nuclear Component Transfer List to the NM Custodian.
d.
If errors are discovered in the Nuclear Component Transfer Lists, or if fuel handling errors occur, the Fuel' Handling Foreman shall notify the NM Custodian, or the NM Custodian's alternate, and obtain concurrence with the proposed corrective' action.
NM Custodian 4.
A physical inventory of each vault and/or pool may be taken periodically while fuel movements are in progress by filling in a blank copy of the appropriate inventory map (s).
100771a 3/86
9 C.E.Co.
N.P. No. 3 Page 3 A.
Transfers of Nuclear Fuel Assemblies or Fuel Rods Between or Within Fuel Vaults and Poo11 Area Responsible Action NM Custodian 5.
From the executed Nuclear Component Transfer List, enter the changes in location of fuel assemblies or fuel rods, by serial number, on a working copy of the Fuel Vault map and/or Fuel Pool map as appropriate.
a.
Verify coincidence of such maps with Step 4 inventory maps.
6.
Review and, if in order, sign Nuclear Component Transfer List showing actual transfers; obtain completion reviewed signatures as required by form and promptly distribute copies as follows:
All completed sheets together:
NMS Manager Each sheet when all moves on such sheet are completed:
Nuclear Fuel Services Manager Retain a fully executed copy of the a.
Nuclear Component Transfer List.
Destroy file copy acquired in Step 2-a.
7.
Updste Nuclear Fuel Location and Exposure Record (Form 86-2592), as required, for each fuel assembly or fuel rod moved within three months of completion of Step A.6 (above).
3 Nuclear Fuel Services 8.
Promptly enter all transfers of nuclear fuel assemblies or fuel rods reported on the Nuclear Component Transfer List in the Nuclear Component Accountability System.
I 100771a 3/86 i
1 1
N.P. N3. 3 C.E.CD.
j Page 4 5
A.
Transfers of Nuclear Fuel Assemblies or Fuel Rods Between or Within Fuel Vaults and Pools q
Area Responsible Action i
NMS Manager and 9.
If the material is transferred from one Comptro11er's Staff RIS to another RIS, promptly prepare NRC/00E Form 741.
Obtain ' signature of j
Authorized Of ficial" and distribute
)
copies as follows:
l Mail one copy to:
Martin Marietta Energy System, Inc.
CS/0RGDP Site Nuclear Material Control Mail Stop 19 P.O. Box P Oak Ridge, Tennessee 37831 i
Forward one copy to:
NM Custodian Nuclear Fuel Services Manager Others, as required Retain one copy.
10.
Review Nuclear Component Transfer List for resolution of any questionable items.
i
- 11. Verify that all transfers reported on i
the Nuclear Component Transfer List and DOE /NRC Fonn 741 have been properly entered in the Nuclear Component Accountability System.
j B.
Transfers of Nuclear Fuel Assemblies To or From Reactors NM Custodian 1.
In advance of (a) the initial loading of 1
a reactor or (b) the removal of a reactor vessel head for refueling or core alteration, obtain the tentative loading or refueling data from the core management organization.
1 ID0771a 3/86
)
i C.E.Co.
N.P. No. 3 1
Page 5 j
(
B.
Transfers of Nuclear Fuel Assemblies To or From Reactors Area Responsible Action 4
Station Outage Coordinator 2.
Prior to the start of a refueling j
or NM Custodian outage, prepare a description of the nuclear fuel related events which will i
take place during the outage (see Exhibit A for an example).
1 a.
The description should include, but not necessarily be limited to, incore sipping, core unloading, out of core sipping, and core loading.
3.
Provide required copies of the refueling outage description to the On-Site Review.
1 On-S u a - >
4.
Review the refueling outage description
)
and, if in order, approve copies for distribution as follows:
NMS Manager k
NM Custodian 1
Fuel Handling Foreman j
Operating Engineer
{
On-Site.. Review File
_ l Nuclear Fuel Services Manager NM Custodian or 5.
Using the approved refueling outage His Alternate description as a guide:
a.
Prepare BWR Nuclear Component Transfer List (Forn 86-2593) or PWR Nuclear Component Transfer List (Form 86-2616) as appropriate.
show1.ng the step-by-step fuel movements for those events in the refueling outage description which 1
require such lists.
Note:
If movement involves a-change from one RIS to another, promptly notify NMS Manager of proposed transfer.
b.
Modify the Transfer Lists to include final sipping results, damaged fuel assemblies or other changes in the core loading plan.
ID0771a 3/86
C.E.C9.
N.P. No. 3 Page 6 B.
Transf ers of Nuclear Fuel Assemblies To or From Reactors Area Responsible Action NM Custodian or 5.
(Continued)
His Alternate c.
Obtain approval of Services Superintendent or Assistant Superintendent Technical Services and Technical Staff Supervisor for the step-by-step Nuclear Component Transfer Lists, i
d.
For on-shift changes to the step-by-step Nuclear Component Transfer Lists that do not change the intent of the procedure, obtain the approval of the Fuel Handling Foreman and a senior. licensed-operator or two senior licensed operators.
6.
Distribute the step by-step Transfer Lists,(from Step B.5) as follows:
1 - Fuel Handling Foreman 1 - Shif t Engineer 1 - Retained by NM Custodian Fuel Handling Foreman 7.
Obtain approval of the NM Custodian or his alternate before initiating any transfer of nuclear fuel to or f rom the reactor.
8.
Supervise execution of the steps of the Nuclear Component Transfer Lists in accordance with Station Operating Procedures.
a.
Initial the step-by-step list as the step is completed.
b.
Update Tag Boards as often as practicable.
ID0771a 3/86
C.E.Co.
N.P. No. 3 Page 7 4
B.
Transfers of Nuclear Fuel Assemblies To or From Reactors Area Responsible Action Fuel Handling Foreman 8.
(Continued) c.
Date and deliver the completed i
sheets of the list (Form 86-2593 or 86-2616) to the NM Custodian at the
.end of each shift.
9.
Review and, if in order, sign each sheet NM Custodian of the completed Form 86-2593 or 86-2616; obtain completion reviewed signatures required by form and immediately disi.ibute copies as follows:
All completed sheets together:
NHS Manager Each sheet when all moves on such sheet are completed:
Nuclear Fuel Services Manager Retain a copy e
Note:
See Nuclear Procedure No. 4 for the reactor physical inventory required to be made before head 1
.I is replaced on a reactor.
- 10. Update Nuclear Fuel Location and i
Exposure Record (Form 86-2592),as i'
required, for each fuel assembly or fuel rod moved within three months of completion of Step 8.9 above.
1 100771a 3/86
C.E.CL N.P. No. 3 Page 8 8.
Transfers of Nuclear Fuel Assemblies To or From Reactors Action Area Responsible i
Nuclear Fuel Services 11.
Promptly enter in the Nuclear Component i
Accountability System all transfers of nuclear fuel assemblies reported on the Nuclear Component Transfer Lists.
NMS Manager and
- 12. Verify that all transfers reported on Comptroller's staff the Nuclear Component Transfer List have been properly entered in the Nuclear Component Accountability System.
l f[
Director of General Procedures 1
1 APPROVED:
i L
Vice President Vice President and Ccaptroller ID0771a 3/86
l
- 8' N P. No.')
Exhildt A Page 1 l
W 1
August 5, 1981 L
TO:
On Site Review
SUBJECT:
QC 2 EOC 5 Master Refueling Nuclear Description i
Attached is the Quad Cities Unit 2 End of cycle 5 Master Refueling Nuclear Description, provided for your review and approval in accordance with CICo. Nuclear Procedure No. 3.
3
-1
.A Y
w Isad Nuclear Engineer f
%e
~
On Site Review and Approval-Tech Staf f Supervisor b
__ Operating Eng1heer,
/
h ps7>44#g BRS/PDK/sjw cc:
E. T. Wein P. D. Knoespel (2)
G. P. Wagner H. E. Bliss Shift Engineer (2)
Fuel Handling Forenan (2)
L 3/86 9
e
I N P. Nb 3 i
Exhibit A Sage 2 i
MASTER REFUELING NUCLEAR DESCRIPTION
)
QUAD CITIES UNIT 2 - END OF CYCLE 5 r'
Purpose I
)
The purpose of this description is to give a short summary of all anticipated refueling events requiring the movement of fuel In addi-tion, major core alterations and other related events are listed.
l Description Work to be performed prior to and during the Quad Cities 2 End of Cycle 5 Refueling Outage includes (in approximate chronological order):
A.
Receipt and inspection of 224 reload fuel assemblies (General Electric pre-pressurized 8 I 8R type, 144 fuel assemblies are the barrier fuel type).
B.
Pre-outage channelling of 60 new fuel assemblies with used
- channels, C.
Full core unloading to facilitate potential in-vessel outage work. Fuel surrounding LPRM's to be replaced will be removed first.
D.
No sipping of fuel is planned during this out. age. The dis-charged fuel vill be sipped.when a pressure type sipping 1
apparatus is available4 E.
Approximately 10 control rod drives will be replaced with over-
)
hauled drives.
T.
Replacement cf up to 12 LPRM strings with NA-200 type General Electric LPAM's.
G.
Shuffling of 58 control rod blades to prevent blade exposure from exceeding the threshold of leaching the B C in the blades.
4 H.
Up to 500 fuel assembly channels will be measured for bow, bulge and tvist to determine the reusability of these channels.
It is esti=ated that approximately 100 channels may need to be re-placed during the outage.
I.
Core reloading incorporating 224 new fuel assemblies with re-arrange =ent of fuel in accordance with the General Electric core management plan for Cycle 6.
J.
Core loading verification, with independent company auditor.
Co::sne nts A.
As of this writing, item A above is in progress.
)b B.
All 7 I 7 fuel vill be discharged.
3/86
1
...w.,;
, C.E.Co..
' Dmibit A '
l Pcre 3 j
C.
Other fuel assembly replacement criteria vill be:
1.
Lowest reactivity (highest exposure), as determined by
e General Electric, and A
2.
Failure or obvious physical damage, as determined by CICo.
j D.
The final reload plan will be formulated by General Electric.
i s
1 W
D k
w 3/86
?a',
.