ML20066A085
| ML20066A085 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/22/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20066A086 | List: |
| References | |
| TAC 48916, TAC 68893, DPR-57-A-091 NUDOCS 8211050050 | |
| Download: ML20066A085 (8) | |
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UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION g
ij WASMNGTON. D. C. 20555
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dEORGIA POWER COMPANY i
OGLDHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
_ CITY OF DALTON, GEORGIA I
DOCKET NO. 50-321 i
EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No. 91 License No. DPR-57 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The. application for amendment by Georgia Power Company, et al., (the licensee) dated October 6,1982, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common
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defense and security or to the health and safety,of the public; and t
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and 'all applicable requirements '
have been satisfied.
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Accordingly, the license is amended by changes to the Technical Spec-oh ifications as indicated in the attachment to this license amendment i
no and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows-(2) Technical Specifications 10 0 0*
The Technical Specifications contained in Appendices A and l
B, as revised through Amendment No. 91, are hereby incorporated i
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in the ifcense. The licensee shall operate the facility in accordance with.the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chief /
erating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 22, 1982
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ATTACHMENT TO LICENSE AMENDMENT NO. d FACILITY OPERATING LICENSE NO. DPR-57 i
DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Techn'ical 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 3.7-12 3.7-12 3.7-12a i
3.7-13 3.7-13 5.0-1 5.0-1 5.0-la f
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LIMITIh6 C0hDITIOh5 FOR OPERATION 5URVEILLANCE REQdlKtrtMih C.
- l C.
Secondary Containment Intearity 1.
Surveillance While Integrity Maintainec a.
Integrity of the secondary con-tainment shall be maintained Secondary containment surveillance during all modes of Unit 1 plant shall be performed as indicated operation except when all of the below:
following conditions are met:
(1) The reactor is suberitical and Specification 3.3.A is met.
a.
A preoperational secondary contain-ment capability test shall be (2) The reactor water temperature is conducted after isolating the below 2120F and the reattor secondary containment and placing i
coolant system is vented.
the standby gas treatment system filter trains in operation. Such (3) No activity is being performed tests shall demonstrate the capa-which can reduce the shutdown bility to maintain a minimum margin below that stated in 1/4-inch of water vacuum under
. Specification 3.3.A.
calm wind (<5 mph) conditions with each filter train flow rate not (4) The fuel cask or irradiated fuel more than 4000 cfm.
I is not being moved in the re-actor building.
b.
Secondary containment capability to maintain a minimum 1/4-inch (5) All hatches between Unit I of water vacuum under calm wind secondary containment and
$t5 mph) conditions with each Unit 2 secondary containment filter train flow rate not more are closed and sealed.
than 4000 cfm shall be demonstrated at each refueling outage, prior to (6) At least one door in each refueling.
access path between Unit i secondary containment and Unit 2 secondary containment is closed.
b.
Integrity of the Unit I secondary containment shall be maintained during all modes of Unit 2 plant operations except Operational Condition 4 as defined in the Unit 2 Technical Specifications.
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(For secondary containment during 1982 refueling outage, see page 3.7-12a.
Amendment No. Ef,$Qf,91 3.7-12
LIMITING C0hDITION5 FOR OPERATION SURVilLL ANCE REQUIREENT5 2
Secondary Containment Integrity 2.
Surveillance While Integrity Maintaired During 1982 Refuelin; Outage Only a.
Unit I secondary containment Secondary containment surveillance shall below the refueling floor is be performed as indicated below:
not required provided all of the following conditions are met:
a.
A preoperational secondary contain-ment capability test shall be per-(1) The reactor is subtritical and formed af ter isolating the Unit 1 Specification 3.3.A is met, secondary conte.inment above the re-fueling floor and placing the (2) The reactor water temperature is standby gas treatment system filter below 212of and the reactor trains in operation. Such tests shall demonstrate the capability coolant system is vented.
to maintain a minimum 1/4-inch of (3) All hatches between Unit i second-water vacuum under calm wind dary containment and Unit 2 secon-(<5 mph) conditions with each fil-dary containment are closed and ter train flow rate not more than 4000 cfm.
sealed.
(4) At least one door in each access b.
If secondary containment integrity path between Unit I secondary should be required as stated in containment and Unit 2 secondary Specification 3.7.C.1, perform sur-containment is closed.
veillance as stated in Specifica-tion 4.7.C.l.a.
If secondary con-(5) All hatches separating Unit I tainment is subsequently requitec seconoary containment sove the as stated in Specification 3.7.C.2, refueling floor from Liit 1 perform surveillance as stated in secondary containment b.!lon the Specification 4.7.C.2.a.
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refueling floor are closed and sealed.
(6) At least one door in each access path separating Unit I secondary containment above the refueling floor from Unit 1 secondary con-tainment below the refueling floor is closed.
b.
Integri.ty of the Unit I secondary containment above the refueling floor shall be maintained during all modes of Unit 2 plant opera-tions exce;:t Operational Con:ition 4 as defined in the Unit 2 Tech-nical Specifications.
c.
Refueling operations may continue in Unit i secondary containment (above the refueling floor) orovided all conditions in Specification 3.7.C.2.a are met.
Amendment No. 91 3.7-12e
l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 5 3.7.C.3 Violation of Secondary 4.7.C.3 Surveillance After Integrity Violated Containment Integrity After a secondary containment vio-If Specification 3.7.C.1 cannot lation is determined the standby be met, procedures shall be gas treatment system will be operated initiated to establish conditions immediately after the affected zones listed in Specification 3.7.C.1.a are isolated from the remainder of through 3.7.C.1.d.
the secondary containment. The ability to maintain the remainder of the secondary containment at 1/4-inch of water vacuum pressure under calm $:5 mph) wind conditions shall be confirmed.
D. Primary Containment Isolation Valves D.
Primary Containment Isolation Valves
- 1. Valves Required to be Operable 1.
Surveillance of Operable Valves During reactor power operation, Surveillance of the primary con-all primary containment isolation tainment isolation valves shall be valves listed in Table 3.7-1. and performed as follows:
all reactor coolant system instru-ment line excess flow cneck valves a.
At least once per operating shall be operable except as stated cycle the operable isolation in Specification 3.7.D.2.
valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and the closure times specified in Table 3.7-1.
r' Amendment No. Jer J4r, 91 3.7-13 j
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5.0 MAJOR DESIGN FEATURES A.
Site Edwin I. Hatch Nuclear Plant Unit No.1 is located on a site of_ about 2244 acres, which is owned by Georgia Power Company, on the south side of the Altamaha River in Appling County near Baxley, Georgia. The Universal Transverse Mercator Coordinates of the center of the reactor building are:
Zone 17R LF 372,935.2m E and 3,533,765.2m N.
B.
Reactor Core 1.
Fuel Assemblies The core shall consist of not more than 560 fuel assemblies of the licensed combination of 7x7 bundles which contain 49 fuel rods and 8x8-fuel bundles which contain 62 or 63 fuel rods each.
2.
Control Rods The reactor shall contain 137 cruciform-shaped control rods. The control material shall be boron carbide powder (B C) compacted to approximately 4
70% of its theoretical density.
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 FSAR.
D.
Containment 1.
Primary Containment The principal design parameters and characteristics of the primary con-tainment shall be as given in Table 5.2-1 of the FSAR.
2.
Secondary'Contairinent* (See Page 5.0-1a)
The secondary cont'ainment shall be as described in Section 5.3.3.1 of the FSAR and the applicable codes shall be as given in Section 12.4.4 of the FSAR.
3.
Primary Containment Penetrations
' Penetrations to the primary containment and piping passing 'through such.
penetrations shall be designed in accordance with standards set forth in i
Section 5.2.3.4 of the FSAR.
T' E.
Fue1 Storage 1
~1.
- Spent Fuel All arrangements of fuel in the spent fuel storage racks shall be main-tained in a suberitical configuration having a k,ff not greater than 0.95~.
2.
New Fuel The new fuel storage vault shall be such that the k,ff dry shall not be greater. than 0.90 and the k,ff flooded shall not be greater than 0.95.
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Amendment No.. R l 91 5.01
2.
Secondary Containment During the refueling outage beginning October 9,1982 the IJnit 1 secondary containment shall consist of the main stack, the Standby Gas Treatment System., and the portion of the reactor building above the common Unit 1 and 2 refueling floor provided.the conditions of Section 3.7.C.2 are met.
e, Amendment No.' 91 5,0-la
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