ML20137N175
| ML20137N175 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/04/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137N171 | List: |
| References | |
| NUDOCS 9704080278 | |
| Download: ML20137N175 (18) | |
Text
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UNITED STATES p'
y j
NUCLEAR REOULATCRY COMMISSION 2
WASHINGTON, D.C. mi
\\...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION lDlICIPAL ELECTRIC AUTHORITY OF GEORGIA CI1Y OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, i
Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, and Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for themselves, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated September 19, 1996, as supplemented December 17, 1996, January 23 and 31, March 21 and April 4,1997, 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 thi>.mendment 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
{R04080278 97o4o4 p
ADOCK 05000321 PDR
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l
).
E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the j
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:
Technical Snecifications The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 206
, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Enviromental 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 J
L erbert N. Berkow, Director Froject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
April 4, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 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 Insert 3.4-22 3.4-22 3.4-23 3.4-23 3.4-24 3.4-24 3.4-25 3.4-25 3.4-26 3.4-26 3.4-27 3.4-27 l
l l
l
j RCS P/T Limits 3.4.9 i
.i ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME J
J C.
- -------NOTE---------
C.1 Initiate action to Immediately I
Required Action C.2 restore parameter (s) shall be completed if to within limits.
this Condition is entered.
&HQ C.2 Determine RCS is Prior to Requirements of the acceptable for entering 3
LCO not met in other operation.
MODE 2 or 3 than MODES 1, 2, 3
and 3.
SURVEILLANCE REQUIREMENTS i
SURVEILLANCE FREQUENCY i
SR 3.4.9.1 Verify:
30 minutes a.
RCS pressure and RCS temperature are within the limits specified in Figures 3.4.9-1 and 3.4.9-2 during RCS inservice leak and hydrostatic testing, and during RCS non-nuclear heatup and cooldown operations; and b.
RLS heatup and cooldown rates are 1 100*F in any I hour period during RCS heatup and cooldown operations, and RCS inservice leak and hydrostatic testing.
(continued)
HATCH UNIT 1 3.4-22 Amendment No. 206
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.2
NOTE-------------------
Only required to be met when the reactor is critical and immediately prior to control rod withdrawal for the purpose of achieving criticality.
Verify RCS pressure and RCS temperature are Once within 15 within the criticality limits specified in minutes prior Figure 3.4.9-3.
to initial l
control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3
NOTE-------------------
Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation i
pump.
Verify the difference between the bottom Once within 15 head coolant temperature and the reactor minutes prior pressure vessel (RPV) coolant temperature to starting an is 5 145*F.
idle recirculation pump SR 3.4.9.4
NOTE-------------------
Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.
Verify the difference between the reactor Once within 15 coolant temperature in the recirculation minutes prior loop to be started and the RPV coolant to starting an temperature is s 50*F.
idle recirculation pump (continued)
HATCH UNIT 1 3.4-23 Amendment No. 206
_ ~.
RCS P/T Limits i
3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.5
NOTE-------------------
Only required to be met when tensioning /
detensioning the reactor vessel head bolting studs.
Verify reactor vessel flange and head Once within flange temperatures are 2 76*F.
30 minutes j
prior to tensioning /
detensioning the reactor vessel head bolting studs and every 30 minutes thereafter I
NOTE-------------------
Only required to be met when the reactor vessel head is tensioned.
Verify reactor vessel flange and head Once within flange temperatures are 1 76*F.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature is < 106*F in MODI 4, and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND Once within 30 minutes after RCS temperature is s 86*F in MODE 4, and 30 minutes thereafter HATCH UNIT 1 3.4-24 Amendment No 206
RCS P/T Limits 3.4.9 1600 EFPY 16 32 1400 r
l'
.,,I g
I l I
1200 g
f
- J
}
2 I ;
I g icoO
.I Ii
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u fI l
II
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1 a
II h
b.'
f,I /
a I
600
,/'
)
/
g I
m
'l 400 BE' TLINE LIMITS l 312 PSIG
- -BOTTOMHEAD J
[
106'F LIMITS j
l
- - UPPER VESSEL i
LIMITS 200 j
i e
BELTLNE 4D l
90TTOM HEAD 681
' FLANGE 111010S 764 0
O.0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE l'F)
Figure 3.4.9-1 (page 1 Of 1)
Pressure / Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests i
HATCH UNIT 1 3.4-25 Amendment No. 206
RCS P/T Limits 3.4.9 j
j 1000 EFPY 32 f6 1400 I
e l
i I
I 1200 I
I O
I I
g
,~0 s
j a
l 1
)-
Y j
=
s 8
800 b
/~
!;f I
I j
600
/
l
)
D
/
E f
400 BELTLINE LIMITS i
- -BOTTOM HEAD LIMITS
-
- UPPER VESSEL LIMITS s
200 l
/
o BELTLINE.oD
/
g DOTTON! HEAD 68*F e
FLANGE REGION is*F 0
O.0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)
Figure 3.4.9-2 (page 1 Of 1)
Pressure / Temperature Limits for Non-Nuclear Heatup, i
Low Power Physics Tests, and C00ldown Following a Shutdown HATCH UNIT 1 3.4-26 Amendment No. 206
RCS P/T Ltits 3.4.9 j
1600 EFPY 16 32 f
i
, 1200 i
0 g 1000 W
y i
to
==
x
/
i E
I E
I s-600 d
i
'E R
E 400 l
-BELTLINE AND NON BELTLINE:
goo LIMITS i
[
T 76 4 0
0.0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)
~
Figure 3.4.9-3 (page 1 Of 1)
Pressure / Temperature Limits for Criticality HATCH UNIT 1 3.4-27 Amendment No. 206
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i UNITED STATES j
NUCLEAR REGULATORY COMMISSION I e WASHINGTON, D.C. 20566 4001
'49.....,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 I. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY' OPERATING LICENSE Amendment No. 147 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by the Georgia Power Company, and Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for themselves, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated September 19, 1996, as supplemented December 17, 1996, January 23 and 31, March 21 and April 4, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; i
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 set j
forth in 10 CFR Chapter I; 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
. i i
i E.
The issuance of this amendment is in accordance with 10 CFR i
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license i
amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 147 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 'iicense amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
F THE NUCLEAR REGULATORY COMMISSION H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes i
Date of Issuance: April 4, 1997 i
4 i
i l
ATTACHMENT TO LICENSE AMENDMENT NO.147 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 vertical lines indicating the areas of change.
Remove Insert 3.4-22 3.4-22 3.4-23 3.4-23 3.4-24 3.4-24 3.4-25 3.3-25 3.4-26 3.4-26 3.4-27 3.4-27
RCS P/T Lisits 3.4.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
NOTE---------
C.1 Initiate action to Immediately Required Action C.2 restore parameter (s) shall be completed if to within limits, this Condition is entered.
AliD C.2 Determine RCS is Prior to Requirements of the acceptable for entering LCO not met in other operation.
MODE 2 or 3 than MODES 1, 2, and 3.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify:
30 minutes a.
RCS pressure and RCS temperature are within the limits specified in Figures 3.4.9-1 and 3.4.9-2 during RCS inservice leak and hydrostatic testing, and during RCS non-nuclear heatup and cooldown operations; and b.
RCS heatup and cooldown rates are s 100*F in any I hour period during RCS heatup and cooldown operations, and RCS inservice leak and hydrostatic testing.
(continued) i HATCH UNIT 2 3.4-22 Amendment No. 147
RCS P/T Liaits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.2
NOTE-------------------
Only required to be met when the reactor is critical and immediately prior to control rod withdrawal for the purpose of achieving criticality.
Verify RCS pressure and RCS temperature are Once within 15 within the criticality limits specified in minutes prior Figure 3.4.9-3.
to initial l
control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3
NOTE-------------------
Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.
1 Verify the difference between the bottom Once within 15 head coolant temperature and the reactor minutes prior pressure vessel (RPV) coolant temperature to starting an is s 145'F.
idle recirculation pump SR 3.4.9.4
NOTE-------------------
Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.
Verify the difference between the reactor -
minutes prior Once within 15 coolant temperature in the recirculation loop to be started and the RPV coolant to starting an temperature is s 50*F.
idle recirculation pump (continued)
HATCH UNIT 2 3.4-23 Amendment No. 147
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.5
NOTE-------------------
Only required to be met when tensioning /
detensioning the reactor vessel head bolting studs.
Verify reactor vessel flange and head Once within flange temperatures are 1 90*F.
30 minutes prior to tensioning /
1 detensioning the reactor vessel head 1
bolting studs and every 30 minutes thereafter i
NOTE-------------------
Only required to be met when the reactor vessel head is tensioned.
Verify reactor vessel flange and head Once within flange temperatures are 190*F.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after i
RCS temperature is 5 120*F in MODE 4, and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 88Q Once within j
30 minutes after RCS temperature is s 100*F in l
MODE 4, and 30 minutes thereafter 4
1
}
HATCH UNIT 2 3.4-24 Amendment No. 147 i
RCS P/T Limits 3.4.9 1600 1400 I I.l efI I,ll
,3m l
O l l l
llI 3 10 I)',I a
E l
I i
5 s00 C
i t
1 E
.1 a
i
!*i
)(/
l' i
l
/
l i /1 '
l E
i
/
j
/'le BELTLINE LIMITS (116.6'F SHIFT.
I E
l j g 32 EFPY) 1 i
e l '
UPPEH VESSEL LIMITS l
I i
j*I 312 PSIG--- - - BOTTOMMEAD LIMITS
}
120T l
l i
2m,
I l
i et l
l 4
Il I
i stLTuxt AND FLAsot Rio10N 90-r soTToM HEAD WF es j
i l
ll t
O 0.0 100.0 200.0 300.0 400.0 500.0 600.0 I
MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) i Figure 3.4.9-1 (page 1 Of 1)
Pressure / Temperature Limits for l
Inservice Hydrostatic and Inservice Leakage Tests HATCH UNIT 2 3.4-25 Amendment No. 147
O' d
RCS P/T Lisits 3.4.9 1600 l
2 1200 1
-i i
O 1000 g
.J E
1 I
=
W j
800
.I t
h I
E t:-
i I
l i
w
/
l I'
8 f
i i
t?
l E
l l
400 JLTLINE LIMITS (121.9'F I
k SHJT. 32 EFPY) f
. ' l - -BOTTOM HEAD LIMITS
~
- UPPER VESSEL LIMITS 1
2w
,j h
i l
r, ll l
l l
I I
SELTLNE
- D 3
901 TOM HEAD 6t*F l
l l
MGE ECM WF i
0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE l'F)
J Figure 3.4.9-2 (page 1 of 1)
Pressure / Temperature Limits for Non-Nuciear Heatup, Low Power Physics Tests, and Cooldown Following a Shutdown HATCH UNIT 2 3.4-26 Amendment No. 147-
o RCS P/T Limits 3.4.9 1600 1400 i
I l
1200 I
i g 1000 I
d S
5 i
- 1 u
m I
l I
i l
600 I
i l
l l
1 1
I i
E l
l 400
-6ELTLINE (121.9'F 32 EFPY).
l AND NON BELTLINE LIMITS l
l 1
I i
2w
/,
/
I l
1 1
{
l WINNUM CitmCAUTY
'l g
I TEMPutATUltz 901 0.0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1 Figure 3.4.9-3 (page 1 Of 1)
Pressure / Temperature Limits for Criticality HATCH UNIT 2 3.4-27 Amendment:NO. 147
-