ML20101K472
| ML20101K472 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/07/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20101K479 | List: |
| References | |
| TAC 55813, DPR-57-A-102 NUDOCS 8412310363 | |
| Download: ML20101K472 (7) | |
Text
- ._
m __
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
$ '%,., /n,I o
k%9 wAsHlNGTON, D. C. 20556
\\,.%,/
1 GEORGIAPOWERCOMPhNY l
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-3E1 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.102 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power. Company, et al.,
(thelicensee)datedSeptember 17, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended
'(the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:(i) 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 conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and t
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, t
l' and paragraph ?..C.(2) of Facility Operating License No. DPR-57 is hereby amended to. read as follows:
$"$NO P
. Technical Specifications The Technical Specifications contained in Appendices A and B,.as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef.fective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
John F. Stolz, hief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 7,1984 t
)
.i i
-r
-~
e
~-
n
,--.m,
- - - - ~
ATTACHMENT TO LICENSE AMENDMENT NO. ins FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 4
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 1.0-2 1.0-2 3.10-2 3.10-2 3.10-7 3.10-7 5.0-1 5.0-1 e
i 1
C.
Core Alteration -. Core alteration shall be the addition, renoval, relocation, or movenent of ~ fuel, sources, incere instr, ments,- or reactivity controls within the reactor pressure vessel with the vessel head renoved and fuel in the vessel.
Suspension of core alterations shall not preclude canpletion of the movement of a ccaponent to a safe conservative position.
D.
Desian Power - Design power refers to the power level at which the reactor is producing 105 percent of reactor vessel rated stem flow.
Design power, does not necessarily correspond to 105 percent of rated reactor power.
The stated design power in megawatts thermal JMt) is the result of a heat balance for a particular plant design.
For Hatch Nuclear Plant Unit 1 the design power is 2537 MWt. Design power is used as an initial condition in transient and accident analyses.
Engineered safety features are those E.
Encineered Safety Features teatures proviced ter mitigating the consequences of postulated accidents, including for exmple contairment, energency core cooling, and stancty gas treatment systen.
F.
Hot Shutdown Condition - Hot shutdown condition means reactor operation with the Mode Switch in the SHUTDOWN position, coolant tenperature greater than 2120, and no ccre alterations are permitted.
F G.
Hot Standby Condition - Hot standby condition means reactor operation witn the Moce Switch in the START & HC7T STANCBY position, coolant tenperature greater than 2120F, reactor pressure less than 1045 psig, critical.
H.
Dunediate - 2 nediate means that the requirec action shall be initiated as soon as practicablef considering the safe operation of the Unit and the importance of the required action.
I.
Instrunent Calibration - An instrunent calibration means the adjust:nent of an instrunent output signal so that it corresponds, within acceptable range and accuracy, to a known value(s) of the paraneter which the instrunent monitors.
J.
Instrunent Channel - An instrunent channel means an arrangenent of a sensor and auxiliary equipnent required to generate and transmit to a trip systen a single trip signal related to the plant paraneter i
monitored by that instrunent channel.
l r
Amendment No. I8, 1 02 1.0-2 j
i i
I
I
[
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIRE!'ENTS 3.10.C Core Monitoring During Core 4.10.C Core Monitoring During Core
~ Alterations Alterations
- 1. During normal core alterations, two Prior to making normal alterations
~
-S m's shall be operable; one in the to the core the Sm's shall be i
i core quadrant where fuel or control functionally tested and checked for rocs are Doing moved ano one in an neutron response. Thereafter, adjacent quadrant, except as specified while required to be operable, the in 2 ano 3 below.
SPM's will be checked daily for response.
For an S m to be considered operable, it shall be inserted to the normal-Use of special movable, dunking operating level and sh41 have a type detectors during initial. fuel minim a of 3 cps with all rods capable loading and major core alterations of normal insertion fully inserted.
in place of normal detectors is.
permissible as long as the detector
- 2. Prior to spiral unloacing the S m 's is connected to the normal SPM shall be proven operable as. stated circuit.
above, however, during spiral-unloading the count rate may drop Prior to spiral unloading or below 3 cps.
reloading the Sm 's shall be functionally testec. Prior to
- 3. Prior to spiral reload, up to four- (4) spiral unloading the Sm's should fuel assa blies will be loaced into also be checkeo for neutron
-their previous core positions next to response.
each of the 4 S M 's to obtain the j
required 3 cps. Until these assemblies have been loadeo, the 3 cps requirement is not necessary.
D.
Spent Ebel Pool Water I4 vel D.
Spent Fuel Pool Water Level Whenever irradiated fuel is stored in Whenever irradiated fuel is stored the spent fuel pool, the pool water in the spent fuel pool, the water l
level shall be maintained at or above level shall be checked and recorded
)
8.5 feet above the top of the active daily.
I fuel.
E.
Control Rod Drive Maintenance.
E.
Control Rod Drive Maintenance
- 1. Rettuir m ents for Withdrawal-
- 1. Requirments for Withdrawal of 1 or 2 control Rocs of 1 or 2 Control Rods A maxims of two control rods separated by at least two control cells in all directions may be I
withdrawn or reoved fra the core for the purpose of performing control rod
{
drive maintenance provided that:
a.
% e Mode Switch is locked in the i
l REFUEL position. We refueling a.
Wis surveillance requirement is 2
j interlock which prevents more than the s ee as given in 4.10.A.
one cxantrol rod fra being withorawn
[
may be bypassed for one of the control rods on which maintenance is
-being Amendment No. Sy, 102 3.10-2
.~~
_... ~..,_--....-..-,_... -, _.. _....,..
.~
=,
3.10.A.2_ Fuel Grapple Hoist Load Setting Interlocks Etel handling is normally conducted kith the fuel scapple hoist.. The total load on this hoist when the interlock is required consists of the weight of the fuel.
grapple and the fuel assembly. mis total is approximately 1500 lbs. in camparison to the load setting of 485 1 30 lbs.
3
- 3. Auxiliary Hoists Ioad Setting Interlock Provisions have also been mace to allow fuel handling with either of the three auxiliary hoists and still maintain the refueling interlocks. The 485 1 30 lb load setting of these hoists is adequate to trip the interlock when a fuel bundle is being handled.
B.
Fuel Ioading 4
To minimize the possibility of loading fuel into a cell containing no control rod, it is required that all control rods are fully inserted when fuel is being loaded into the reactor core. @is reguirenent assures that during refueling the refueling interlocks, as designed, will prevent inadvertent criticality.
C.
Core Monitorina During Core Alterations ite SWs are provided to monitor the core during perioos of Unit shutdown and to 1
guide the operator during refueling operations and Unit startup. Requiring two operable SWs in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that quadrant during such alterations.
The requirements of 3 counts per second provices assurance that neutron flux is being monitorea.
During spiral unloacing, it is not necessary to maintain 3 cps because core alterations will involve only reactivity renoval and will not result in criticality.
We loading of up to four fuel bundles around the SWs before attaining the 3 cps is permissible because these bundles were in a subcritical configuration when they i
were renoved and therefore they will renain subcritical when placec back in their previous positions.
i D.
' Spent Fuel Pool Water Level f
The design of the spent fuel storage pool provides a storage location for 3181 fuel l
assenblies in the reactor building which ensures adequate shielding, cooling, and the reactivity control of irradiated fuel. An analysis has been performed which shows that a water level at or in excess of eight and one-half feet over the top of the active fuel will provide daalding such that the maximum calculated radiological doses do not exceed the limits of 10 CPR 20. %e normal water level i
provides 14-1/2 feet of additicnal water shielding. All penetrations of the fuel pool have been installed at such a height that their presence does not provide a possible drainage route that could lower the water level to less than 10 feet above the top of the active fuel. ' Lines extending below this level are equipped with two check valves in series to prevent inadvertent pool drainage.
E.
Control Rod Drive Maintenance
[>
During certain periods, it is desirable to perform maintenance on two control r:;d drives at the same time.
7e encanent No. H,102 3.10-7 i
-. ~..
, -.. _. _, _. ~.,
,. ~.
5.0 ' MAD DESIG FEA'IURES A. Site Ecwin I. Hatch Nuclear Plant Unit No.1 is located on a site of about 2244 acres, which is owned by Georgia Power Cmpany, on the south side of the Altmaha River in Appling County near Baxley, Georgia. The Universal Transverbe Mercator Coordinates of the center of the reactor building are: Zone 17R LF 372,935.3n E and 3,533,765.3n N.
B. Reactor Core 1.
Etel Assemblies The core shall consist of not more than 560 fuel assenblies of the licensed cmbination of 7x7 bundles which contain 49 fuel rods.and 8x8 fuel t.undles which contain 62 or 63 fuel rods each.
2.
Control Rods The reactor shall contain 137 cruciform-shaped control rods.
C. Reactor Vessel The reactor vessel is described in Table 4.2-2 of the FSAR. The applicable design specifications shall be as listed in Table 4.2-1 of the ESAR.
D. Contaiment 1.
Primary Contaiment The principal design paraneters anc charac..istics of the primary contalment shall be as given in Table 5.2-1 of the ESAR.
2.
Secondary Centaiment* (See Page 5.0-la)
The secondary contaiment shall be as described in Section 5.3.3.1 of the ESAR and the applicable codes shall be as given in Section 12.4.4 ot the ESAR.
3.
Primary contaiment Penetratien.:
Penetrations to the primary contalment and piping passing througt such penetrations shall be designed in accordance with standards set forth in Secticn 5.2.3.4 of the ESAR.
E. Fuel Storace 1.
Spent Etel All arrangement of fuel in the spent fuel storage racks shall be maintained in a subcritical configuration having a keff not greater than 0.95.
2.
New Fuel The new fuel storage vault shall be such that the kegg dry shall not be greater than 0.90 and the kefg flooded shall not be greater than 0.95.
Amendment No. /74, 91/,102 5.0-1
_ _