ML20217B101
| ML20217B101 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/05/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217B106 | List: |
| References | |
| NUDOCS 9709230231 | |
| Download: ML20217B101 (12) | |
Text
_ _ _ _
Metyk p
UNITED STATES
- r NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. steeH001 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.20A 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. DP.U7 filed by the Georgia Power Company and Southem Nuclear Operating Company, Inc. (Southem Nuclear),
acting for themselves, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated January 7,1997, as supplemented by letter dated July 2,1997, 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.
Tt'e issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
iVL.Dh 9709230231 970905 PDR ADOCK 05000321 P
PDR 1
7 2-2.
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 Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 208, are hereby incorporated in the license.
Southem 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 from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
H rbert N. Berkow, Director Project Directorate ll-2 Division of Reactor Projects -l/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: September 5, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 208 FACILITY OPERATING LICENSE NO. DPR 57 DOCKET NO. 60 321 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 areas of change.
Remove innan 3.4 8 3.4 8 3.5 6 3.5 6 3.6-19 3.6-19 t
=._
S/RVs 3.4.3
. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints In accordance of the S/RVs are as follows:
with the 1
Inservice Number of Setpoint Testing Program S/RVs (osio) 4 1110
- 33.3 4
1120
- 33.6 3
1130 2 33.9 Following testing, lift settings shall be 4
within
- 1%.
i HATCH UNIT 1 3.4-8 Amendment No. 208
e
\\
ECCS -- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.9
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 165 psig, 18 months the HPCI pump can develop a flow rate i
a: 4250 gpm against a system head corresponding to reactor system pressure.
4 SR 3.5.1.10
NOTE--------------------
Vessel injection / spray may be excluded.
Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal.
i SR 3.5.1.11
NOTE--------------------
Valve actuation may be excluded, 4
i Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal.
SR 3.5.1.12 Verify each ADS valve relief mode actuator 18 months strokes when manually actuated.
i e
i HATCH UNIT 1 3.5-6 Amendment No. 208 i
e
i LLS Valves 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l
SR 3.6.1.6.1 Verify each LLS valve relief mode 18 months actuator strokes when manually actuated.
NOTE-------------------
)
Valve actuation may be excluded.
Verify the LLS System actuates on an 18 months actual or simulated automatic initiation signal.
4 i
l i
s i
i HATCH UNIT 1 3.6-19 Amendment No. 208
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UNITED STATES s
{
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30666-0001
\\...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIAa CITY OF DALTON. GEORGIA DOCKET NO. 50-366 l
EDWIN 1. HATCH NUCLEAR PLANT. UNIT 2 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 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 the Georgia Power Company and Southem Nuclear Operating Company, Inc. (Southem Nuclear),
acting for themselves, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated January 7,1997, as supplemented by letter dated July 2,1997, 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 comme 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.
___________7___-________
- 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.15tre hereby incorporated in the license.
Southem 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 from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
n e
rt N. Berko, irector roject Directorate ll 2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: September 5, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 150 FACILITY OPERATING LICENSE NO. NPF 5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.
Remove Insert l
0 8
3.4-8 3.5-6 3.5-6 3.6 19 3.6 19
S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS i
SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints In accordance of the S/RVs are as follows:
with the Inservice Number of Setpoint Testing Program S/RVs (osia) 4 1120
- 33.6 4
1130
- 33.9 3
1140
- 34.2 Following testing, lift settings shall be within
- 1%.
l HATCH UNIT 2 3.4-8 Amendment No. 150
'V ECCS -- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.9
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 165 psig, 18 months the HPCI pun.p can develop a flow rate at 4250 gpm against a system head corresponding to reactor pressure.
SR 3.5.1.10
NOTE--------------------
Vessel injection / spray may be excluded.
Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal.
SR 3.5.1.11
NOTE--------------------
Valve actuation may be excluded.
Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal.
SR 3.5.1.12 Verify each ADS valve relief mode actuator 18 months strokes when manually actuated.
(continued) 1 HATCH UNIT 2 3.5-6 Amendment No. 150 t
LLS Valves 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 Verify each LLS valve relief mode 18 months actuator strokes when rinually actuated.
I TE-------------------
Valve actuation may se excluded.
Verify the LLS System actuates on an 18 months actual or simulated automatic initiation signal.
HATCH UNIT 2 3.6-19 Amendment No. 150
,