ML20032B746
| ML20032B746 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 10/27/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20032B747 | List: |
| References | |
| TAC-57316, TAC-57317, NUDOCS 8111060252 | |
| Download: ML20032B746 (6) | |
Text
-
DUKE POWER C0!!PANY DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMEND!!ENT TO FACILITY OPERATIliG LICENSE Amendrient No. 8 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Special Nuclear 11aterials License SNil-1773 filed by the Duke Power Company (licensee) on Ilarch 9,1978, couplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conduc%d in compliance with the Comission's re<;ulations; D.
The issuance of this amendment will not be inimical to the comaon defense l
and security or to the health and safety of the public; and The issuance of this anend..ent is in accordance with 10 CFR Part 51 of the l
E.
T l
Cocrtission's regulations and all applicable requirenents have been satis-fled.
l l
2.
Accordingly. Facility Operating License NPF-9 is anended by the following changes:
A.
Add paragraph 2.K. to read:
K.
The licensee is authorized to receive from the Oconee Huclear Station, Units 1,2 and 3, possess, and store irradiated Oconee fuel assemblies contsiaing special nuclear material, enriched to not more than 3.24%
by weight U-235 subject to the following conditions:
j a.
Oconee fuel assemblies nay not be placed in the licGuire Huclear Station, Unit 1 and 2, reactors.
a "-
"a OFHCE)
.-- lbh %R"abbg OFFICIAL RECORD COPY u m e -s w o pe ronn aia nomi mcu am 4
., b.
Irradiated fuel shipped to McGuire Unit 1 from Oconee shall have been removed from the Oconee reactor no less than 270 days prior to shipment.
c.
Iio more than 300 Oconee irradiated fuel assert > lies shall be received for storage at the I:cGuire Unit 1 spent fuel pool.
d.
Burnup of Oconee fuel shipped shall he no greater than 36,000 tN d.=ys per rc.etric ton.
e.
Receipt of irradiated Ocor.ee fuel shall be lin.ited by the use of the NFS-4 (NAC-1) or NLI-1/2 spent fuel casks.
f.
The spent fuel pool crane travel shall be restricted by ao...f nis-trative controls to the paths required by Technical Specification 3/4 9.7 whenever a spent fuel cask is being handled.
B.
Change the designation of paragraph 2.J. on page 19 to 2.L.
C.
The Technical Specifications are changed as indicated in the attachment t9 this license auendnent, and paragraph 2.C.(2) of Facility Operating License 11o. IIPF-9 is aereby amended to read as follows:
(2) Technical Specifications The Technical Specificptions contained in Appendix A as revised through Anendment No. o, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license anendment is effective es of its date of issuance.
FOR THE t!UCLEAR REGULATORY COIt!ISSION d
'l Darrell G. Eisenhut. Director Division of Licensing Office of Nuclear Reactor Regulation Attacheent:
Appendix A Technical Specification Changes Date of Issuance: October 27, 1981
- NOTE: SEE PREV 10US WHITE FOR CONCURRENCE omer y. L A.: D L:.La..#.4....DL:LB..f 4.... !. 0 ELD..
.b:.LB..#4..
9.
DL..
...DIR
/
SURNAMEh
........h..
.k.k.k..
S{.hSI.....
.9/
/81...
.9
/81-outj 8/27/81...
.8/2781....
.8/27/81..
, unc ronu ais oo-son emeu oxa OFFICIAL RECORD COPY uwu un-mm
. b.
Irradiated fuel shipped to ficGuire Unit 1 fron Oconee shall have been renoved from the Oconee reactor no less than 270 days prior to shipment.
c.
No nere than 300 Oconec irradiated fuel assenblies shall be received for storagc at the McCuire Unit 1 spent fuel pool.
d.
Burnup of Oconee fuel shipped I, hall be no greater that. 36,000
!N days per netric ton.
e.
Receipt of irradiated Oconee fuel shall be limited by the use of the HFS-4 (NAC-1) or NLI-1/2 spent fuel casks. The spent fuel pool crane travel shall be restricted by administrative controls to the paths required by Technical Specification 3/4 9.7 when-ever a spent fuel cask is being handled.
f.
Prior to spent fuel cask novement at ticGuire, ficGuire spent fuel stored in the first 17 rows of the ficGuire Unit 1 spent fuel pcol, closest to the spent fuel cask handling area, shall be decayed a ninimun of 45 days.
B.
Change the designation of paragraph 2.J. on page 19 to 2.L.
C.
The Technical Specifications are changed as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License ilo. IlPF-9 is hereby anended to read as follows:
(2) Technical Specifit ;tions The Technical Specifications contained in Appendix A, as revised through Acendrent 110.
, are hereby incorporated into this license.
The 11cen. ae shall operate the facility in accordance with the Technical Specifications and the Envircrental Protection Plan.
3.
This license anendment is effective as of its date of issuancc.
FOR THE NUCLEAR REGULATORY CONIISSION Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Attachment:
Appendix A Technical Specification Changes Date of issuance:
- NOTE: SEE PREVIOUS WHITE FOR CONCURRENCE omcc) LA:DL:LB..#4..
.. DL.: L B.. #4...
. 0Ebd..blL
.DL:LB..#.4..
.. AD.; L / DL..
..D.lR/QL
.. 9.9.h.O.9.!..h.b..
.,.(.
.....9
..b.i.senhut SURNAME
- 8../. 2 7../. 61 8/27../81 8/27/.81
......./81
..9/
/81 9/ /M 9/
oney I
P4RC FORM 318 (s0-0) t.RCM 0243 OFFIClAL RECORD COPY usam un-n,2
ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-9 i
DOCKET NO. 50-369 Replace the following pages of the Appendix "A" Technical Specifications 'with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding over-leaf pages are.also provided to maintain document completeness.
Overleaf Amended Page Page 3/4 9-7 3/4 9-8 3/4 9-8a i
I TC
j REFUELING OPERATIONS 3/4.9.6 MANIPULATOR CRANE I
LIMITING CONDITION FOR OPERATION
'j
'l 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of t
drive rods or fuel assemblies and shall be OPERABLE with:
a.
The manipulator crane used for movement of fuel assemblies having:
+
1.
A minimum capacity of 3250 pounds, and 2.
An overload cutoff limit less than or equal to 2900 pounds.
b.
The auxiliary hoist used for latching and unlatching drive rods having:
1.
A minimum capacity of 610 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
(
APPLICABILITY:
During movement of drive rods or fuel assemblies within l
,s ACTION:
With the requirements for crane and/cr hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations I
involving the movement of drive rods and fuel assemblies within the reactor j
pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS i
4.9.6.1 Each manipulator crane used for movement of fuel assemblies within 7
the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> l
prior to the start of such operations by performing a load test of at least t
3250 pounds and demor.strating an automatic load cutoff when the crane load exceeds 2900 pounds.
4.9.6.2 Each auxiliary hoist and associated load indicator usec for movement of drive rods within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 610 pounds.
l l!
K I
N McGUIRE-UNIT 1 3/4 9-7
REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loeds in excess of 3000 pounds
- shall be prohibited from travel over fuel assemblies in the storage pool.
Truck Casks shall be carried along the path outlined in Figure 3.9-1 it. the Fuel Pit and Fuel Pool area.
APPLICABILITY: With fuel assemblies in the storage pool.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly and control rod, shall be verified to be less than or equal to 3000 pounds prior to moving it over fuel assemblies.' ~ ~ ~ ~ ~ ~
- Weir gater of the spent fuel pool may be moved by crane over the stored fuel provided the spent fuel has decayed for at least 17.5 days since last being part of a core at power.
~"
McGUIRE-UNIT 1 3/4 08 Amendegnt No.
8
~
. ' r - ' '.;. ',
Extreme of Main Hook 1
l I
Os I
/
)
l i
I m
V l 6
[
9 E
o A
9
/
l 8
e i
l E
\\
u vl x -
Q o
o 4.
n 50 2
I o
o w.8
_m
.E Cask Pit o
Ei e
2'-6
. 3' Fuel Pool
$5
=
9*-0
[
=
a_ ~w e
8 4---
o o
E 5
l 3cr
- i5 9
[a~
.s 9
g o
z
/
N 8
s l
l I
q e
ni jr l
r,
/
l s
{_{---1'-1 %
~~
~
l l
l l
1r D l
l t
Figure 3.91 R_equired Path for Movement of Truck Casks McGUIRE UNIT 1 3/4 9-8a Amendment No. 8 75
.