ML20207G549
| ML20207G549 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/09/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207G554 | List: |
| References | |
| NUDOCS 9906110207 | |
| Download: ML20207G549 (10) | |
Text
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4, UNITED STATEE s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2068H001
'+9.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-57
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 1 (the facility)
Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (Southem Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated January 21,1999, which superseded your application dated July 22, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.
9906110207 990609 PDR ADOCK 05000321 P
f b 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.216,
are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Richard L. Emch, Jr., Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Offico of Nuclear Reactor Regulation Attachm'ent:
Technical Specification Changes Date of issuance: June 9, 1999
c
, ATTACHMENT TO LICENSE AMENDMENT NO. 216 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical
' lines indicating the areas of change.
Remove Insert 3.3-5G 3.3-56 3.3-62 3.3-62 I
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Pricary Containment isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 2 of 4)
Primary Containment Isolation Instrumentation APPLICAgLE CONDITIONS MODES OR REQUIRED REFERENCED OTNER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWAglE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALLE 2.
Primary Containment isolation (continued) c.
Drywell 1,2,3 1
F sa 3.3.6.1.1 s 138 R/hr Radiation Nigh sa 3.3.6.1.2 54 3.3.6.1.5 54 3.3.6.1.6 d.
Reactor guilding 1,2,3 2
G sa 3.3.6.1.1 s 80 mm/hr Exhaust se 3.3.6.1.3 Radietion - Nigh SR 3.3.6.1.6 e.
Refueling Floor 1,2,3 2
G SR 3.3.6.1.1 5 80 mA/hr l
Enhaust sa 3.3.6.1.3 Radletion - Nigh
$4 3.3.6.1.6 3.
Nigh Pressure Coolant injection (NPCI) System isolation a.
NPCI Steam Line 1,2,3 1
F sa 3.3.6.1.1 s 303% rated F L ou - N igh SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 sa 3.3.6.1.6 b.
NPCI Steam S p ty Line 1,2,3 2
F st 3.3.6.1.1 2 100 pois Pressure - Low SR 3.3.6.1.2 sa 3.3.6.1.5 st 3.3.6.1.6 c.
NPCI Turbine 1,2,3 2
F SR 3.3.6.1.1 s 20 psig Exhaust Diaphrage sa 3.3.6.1.2-Pressure - Nish st 3.3.6.1.5 SR 3.3.6.1.6 d.
Drywel1 Pressure - Nigh 1,2,3 1
F st 3.3.6.1.1 s 1.92 psig sa 3.3.6.1.2 sa 3.3.6.1.5 sR 3.3.6.1.6 e.
NPCI Pipe Penetration 1,2,3 1
F st 3.3.6.1.1 s 169'F Room Temperature - Nigh sa 3.3.6.1.2 SR 3.3.6.1.5 sa 3.3.6.1.6 f.
Suppression Pool 1,2,3 1
F sa 3.3.6.1.1 f 169'F Area Ambient SR 3.3.6.1.2 Teepersture - Nigh st 3.3.6.1.5 SR 3.3.6.1.6 (continued)
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HATCH UNIT 1 3.3-56 Amendment No. 195,216
Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Contalrunent Isolation Instrumentation APPLICA8LE M(BES OR REQUIRED OTNER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWASLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE 1.
Reactor vessel Water 1,2,3, 2
sa 3.3.6.2.1 2 -47 inches Level - Low Low, Level 2 (a)
SR 3.3.6.2.2 st 3.3.6.2.4 st 3.3.6.2.5 2.
DryweL L Pressure - High 1,2,3 2
sR 3.3.6.2.1 s 1.92 psis sa 3.3.6.2.2 sa 3.3.6.2.4 st 3.3.6.2.5 3.
Reactor Building Exhaust 1,2,3, 2
sa 3.3.6.2.1 s 80 met /hr l
Radiat ion - NIgh (a) sR 3.3.6.2.3 sR 3.3.6.2.5 4.
Refueling Floor Exhaust 1,2,3, 2
SR 3.3.6.2.1 s 80 aft /hr
{
Radiation - Nigh
$(a) (b) sr 3.3.6.2.3 sa 3.3.6.2.5 (a) During operations with a potentist for draining the reactor vessel.
(b) During CORE ALTERATIONS and daring movesment of irradiated fuel assembLlos in secondary containment.
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i HATCH UNIT 1 3.3-62 Amendment No. 195, 216
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'l UNITED STATES g*
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2056H001 o
'+9.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 License No. NPF-5
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 2 (the facility)
Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated January 21,1999, which superseded your application dated July 22, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; J
B. The facility will operate in conformity with the application, the 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 I
be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance cf this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
.u
. 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph
' 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.157 are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Richard L. Emch, Jr., Chief, Section 1
{
Project Directorate il i
Division of Licensing Project Management J
Office of Nuclear Reactor Regulation
Attachment:
~ Technical Specification Changes Date of issuance:
June 9, 1999 4
l
ATTACHMENT TO LICENSE AMENDMENT NO.157 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical I
lines indicating the areas of change.
e Remove Insert 3.3-57 3.3-57 3.3-63 3.3-63 I
e
1 Primary Containment Isolation Instrumentation 3 3.6.1 Table 3.3.6.1 1 (pose 2 of 4)
Primary Contaitunent isolation Instrtmentation APPLICA8LE CON 0lTIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED
$URVEILLANCE ALLOWABLE FUNCTION CEmDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE 2.
Primary Contaiteent Isolation (continued) c.
Drywell 1,2,3 1
F st 3.3.6.1.1 s 138 R/hr i
Radiation-Nigh SR 3.3.6.1.2
$R 3.3.6.1.5 st 3.3.6.1.6 d.
Reactor Building 1,2,3 2
G st 3.3.6.1.1 s 80 aft /hr Exhaust st 3.3.6.1.3 Radiatlon - High st 3.3.6.1.6 e.
Refusting Floor 1,2,3 2
G sa 3.3.6.1.1 s 80 mR/hr Enhaust SR 3.3.6.1.3 I
Radiation - Nigh SR 3.3.6.1.6 3.
High Pressure coolant Injection (NPCI) system Isolation a.
NPCI steen Line 1,2,3 1
F
$R 3.3.6.1.1 s 3031 rated F Low - Nigh SR 3.3.6.1.2 steam iLow sa 3.3.6.1.5
$4 3.3.6.1.6 b.
NPCI steen s p ly Line 1,2,3 2
F st 3.3.6.1.1 t 100 pois Pressure - Low
$4 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.6 c.
NPCI Turbine 1,2,3 2
F st 3.3.6.1.1 s 20 pelg Exhaust Diaphrase SR 3.3.6.1.2 Pressure - Nish st 3.3.6.1.5 st 3.3.6.1.6 d.
Drywell Pressure - Nigh 1,2,3 1
F st 3.3.6.1.1 s 1.92 poig SR 3.3.6.1.2
$R 3.3.6.1.5 st 3.3.6.1.6 e.
NPCI Pipe Penetration 1,2,3 1
F SR 3.3.6.1.1 s 169'F Room Temperature - Nish SR 3.3.6.1.2 sa 3.3.6.1.5 SR 3.3.6.1.6 f.
Supprecalon Pool 1,2,3 1
F st 3.3.6.1.1 s 169'F Area Astlant
$R 3.3.6.1.2 Temperature - High st 3.3.6.1.5 sa 3.3.6.1.6 (continued)
HATCH UNIT 2 3.3-57 Amendment No. 135, 157
Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2 1 (page 1 of 1) secondary Conteirunant Isolation Instrumentation APPLICABLE MtBES OR REQUIRED OTHER CNANNELS SPEClflED PER SURVEILLANCE ALLOWA8LE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE 1.
Reactor vessel Water 1,2,3, 2
SR 3.3.6.2.1 1 47 inches Level - Low Low, Level 2 (a)
SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 2.
Drywell Pressure-Nigh 1,2,3 2
SR 3.3.6.2.1 s 1.92 pois SR 3.3.6.2.2 st 3.3.6.2.4 st 3.3.6.2.5 3.
Reactor Building Exhaust 1,2,3, 2
SR 3.3.6.2.1 s 80 aft /hr l
Radiation - Nigh (a)
SR 3.3.6.2.3 st 3.3.6.2.5 4.
Refueling Floor Enhaust 1,2,3, 2
st 3.3.6.2.1 s 80 mR/hr l
Radt atIon - Nigh 5(*)*(b)
SR 3.3.6.2.3 st 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel.
(b) Durity CORE ALTERAfl0Ns and ducirs movement of irradiated fuel assemblies in secondary contairument.
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HATCH UNIT 2 3.3-63 Amendment No. 135, 157