ML20137C870
| ML20137C870 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/21/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137C873 | List: |
| References | |
| NUDOCS 9703250153 | |
| Download: ML20137C870 (26) | |
Text
,
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UNITED STATES y
j NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. Sam M
\\
/
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION I
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 1
EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated October 7,1996, 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 Comission'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; j_
and l
E.
The issuance of this amendment is in accordance with 10 CFR Part l
M of the Commission's regulations and all applicable requirements te e been satisfied.
I 9703250153 970321 PDR ADOCK 05000321 p
PDR l
i
. 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.
l DPR-57 is hereby amended to read as follows:
Technical Specifications i
The Technical Specifications contained in Appendix A and the Environmental-Protection Plan contained in Appendix B, as revised through Amendment No. 204, are hereby incorporated in the license. The licensee 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 prior to startup from the Unit I refueling outage scheduled for fall 1997.
FOR THE NUCLEAR REGULATORY COMMISSION er ert N.
eAow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: March 21, 1997 e
ATTACHMENT TO LICENSE AMENDMENT NO. 204 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 Paaes Insert Paoes 3.1-23 3.1-23 3.4-7 3.4-7 3.4-8 3.4-8 3.5-1 3.5-1 3.5-2 3.5-2 3.5-3 3.5-3*
3.5-4 3.5-4*
3.5-5 3.5-5*
3.5-6 3.5-6*
3.6-18 3.6-18 i
- no change - overflow page i
T 1
c 1
(
SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued) i SURVEILLANCE FREQUENCY SR 3.1.7.5 Verify the concentration of sodium 31 days pentaborate in solution is within the Region A limits of Figure 3.1.7-1.
&HD Once within i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is restored within the Region A t
limits of Figure 3.1.7-2 SR 3.1.7.6 Verify ear.h SLC subsystem manual and power 31 days operated valve in the flow' path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.
SR 3.1.7.7 Verify each pump develops a flow rate In accordance at 41.2 gpm at a discharge pressure with the a: 1232 psig.
Inservice l
l Testing program SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel.
STAGGERED TEST BASIS (continued)
HATCH UNIT 1 3.1-23 Amendment No.
204
S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety / Relief Valves (S/RVs)
LC0 3.4.3 The safety function of 10 of 11 S/RVs shall be OPERABLE.
l APPLICABILITY:
MODES 1, 2, and 3.
l I
ACTIONS l
l CONDITION REQUIRED ACTION COMPLETION TIME l
A.
Two or more S/RVs A.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
bNQ 1
l A.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 1
i l
i i
l
\\
HATCH UNIT 1 3.4-7 Amendment No. 204
i S/RVs l
3.4.3 SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY l
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) 11 1150
- 34.5 Following testing, lift settings shall be within
- 1%.
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 each S/RV opens when manually 18 months i
actuated.
1 4
HATCH UNIT 1 3.4-8 Amendment No.204
ECCS - Operating i
3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM i
3.5.1 ECCS - Operating j
LCO 3.5.1 Each ECCS injection / spray subsystem and the Automatic Depressurization System (ADS) function of six of seven I
safety / relief valves shall be OPERABLE.
APPLICABILITY:
MODE 1 MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with 4
reactor steam dome pressure s 150 psig.
1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS A.1 Restore low pressure 7 days injection / spray ECCS injection / spray subsystem inoperable.
subsystem to OPERABLE status.
B.
Required Action and B.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion j
Time of Condition A E
not met.
l B.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.
HPCI System C.1 Verify by I hour inoperable.
administrative means RCIC System is OPERABLE.
M C.2 Restore HPCI System 14 days to OPERABLE status.
(continued)
HATCH UNIT 1 3.5-1 Amendment No. 204
_~.-.
ECCS - Operating 3.5.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME l
D.
HPCI System D.1 Restore HPCI System 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
to OPERABIE status.
MD E
One low pressure ECCS D.2 Restore low pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> injection / spray ECCS injection / spray i
subsystem is subsystem to OPERABLE inoperable.
status.
o i
E.
Two or more ADS valves E.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l
ma 1
E E.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l
l Required Action and dome pressure to associated Completion s 150 psig.
Time of Condition C or j
D not met.
F.
Two or more low F.1 Enter.LCO 3.0.3.
Immediately l
pressure ECCS injection / spray subsystems inoperable.
E l
1 l
HPCI System and two or l
more ADS valves inoperable.
l l
HATCH UNIT I 3.5-2 Amendment No.204
ECCS -- Operating 3.5.1
-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l
SR 3.5.1.1 Verify, for each ECCS injection / spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
NOTE--------------------
Low pressura coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) low pressure permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
l SR 3.5.1.3 Verify ADS air supply header pressure is 31 days I
k 90 psig.
SR 3.5.1.4 Verify the RHR System cross tie valve 31 days is closed and power is removed from the l
valve operator.
SR 3.5.1.5 Verify each LPCI inverter output voltage is 31 days k 570 V and s 606 Y while supplying the I
respective bus.
i (continued)
I HATCH UNIT 1 3.5-3 Amendment No. 204
ECCS -- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.6
NOTE--------------------
l Only required to be performed prior to entering MODE 2 from MODE 3 or 4, when in MODE 4 > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Verify each recirculation pump discharge 31 days valve cycles through one complete cycle of full travel or is de-energized in the closed position.
SR 3.5.1.7 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the corresponding to the s'pecified reactor Inservice pressure.
Testing Program SYSTEM HEAD NO.
CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE EMBES PRESSURE OF CS a: 4250 gpm 1
a 113 psig LPCI a: 17,000 gpm 2
at 20 psig SR 3.5.1.8
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 1058 psig 92 days and a: >20 psig, the HPCI pump can develop a i
flow rate at 4250 gpm against a system head corresponding to reactor pressure.
l (continued) f HATCH UNIT 1 3.5-4 Amendment No.204
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 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.
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.
1 (continued)
HATCH UNIT 1 3.5-5 Amendment.tNo.20k
ECCS -- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.12
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 l
adequate to perform the test.
Verify each ADS valve opens when manually 18 months actuated.
HATCH UNIT 1 3.5-6 Amendment No.204
LLS Valves 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Low-Low Set (LLS) Valves LC0- 3.6.1.6 The LLS function of three of four safety / relief valves shall I
be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1
l A.
Two or more LLS valves A.]
Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
AND 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> A.2 Be in MODE 4.
l l
l i
I 4
d l
l HATCH UNIT 1 3.6-18 Amendment No. 204 l
- u UNITED STATES
[n j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20606 4001 l
s...../
GEORGIA POWER COMPANY
_0GLETHORPE 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. 145 License No. NPF-5 i
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, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated October 7, 1996, 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; 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the commen defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Comission's regulations and all applicable requirements have been satisfied.
l l
I
l
, 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:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 145are hereby incorporated in the license.
The licensee 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 prior to startup from the Unit 2 refueling outage currently scheduled for March 15, 1997.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 21, 1997 l
l
a ATTACHMENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 l
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 Paaes Insert Paaes 3.1-23 3.1-23 3.4-7 3.4-7 3.4-8 3.4-8 3.5-1 3.5-1 3.5-2 3.5-2 3.5-3 3.5-3*
i 3.5-4 3.5-4*
3.5-5 3.5-5*
3.5-6 3.5-6*
1 3.5-6a 3.5-6b 3.6-18 3.6-18
- no change - overflow page
SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.7.5 Verify the concentration of sodium 31 days pentaborate in solution is within the Region A limits of Figure 3.1.7-1.
M Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after i
water or sodium pentaborate is added to solution l
M Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is l
restored within the Region A l
limits of l
Figure 3.1.7-2 SR 3.1.7.6 Verify each SLC subsystem manual and power 31 days operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.
l SR 3.1.7.7 Verify each pump develops a flow rate In accordance a 41.2 gpa at a discharge pressure with the a 1232 psig.
Inservice l
Testing Program l
SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel.
STAGGERED TEST BASIS
)
(continued)
HATCH UNIT 2 3.1-23 Amendment No.145
S/RVs j
3.4.3 4
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety / Relief Valves (S/RVs)
LC0 3.4.3 The safety function of 10 of 11 S/RVs shall be OPERABLE.
l l
APPLICABILITY:
MODES 1, 2, and 3.
I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l
A.
Two or more S/RVs A.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
MD l
A.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> I
l I
l l
l l
l l
l 1
i HATCH UNIT 2 3.4-7 Amendment No. 145
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 Inservice Number of Setpoint Testing Program S/RVs (nsia) 11 1150
- 34.5 Following testing, lift settings shall be within i 1%.
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 each S/RV opens when manually 18 months-actuated.
j l
l HATCH UNIT 2 3.4-8 Amendment No.145
ECCS -- Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION CO (RCIC) SYSTEM 3.5.1 ECCS -- Operating LC0 3.5.1 Each ECCS injection / spray subsystem and the Automatic Depressurization System (ADS) function of six of seven I
safety / relief valves shall be OPERABLE.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) i and ADS valves are not required to be OPERABLE with reactor steam dome pressure s 150 psig.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS A.]
Restore low pressure 7 days injection / spray ECCS injection / spray subsystem inoperable.
subsystem to OPERABLE status.
B.
Required Action and 8.1 Be in' MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND l
not met.
l B.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.
HPCI System C.)
Verify by I hour inoperable.
administrative means RCIC System is OPERABLE.
AND C.2 Restore HPCI System 14 days to OPERABLE status.
(continued) i
. HATCH UNIT 2 3.5-1 Amendment No.145
)
+
j ECCS -- Operating i
3.5.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
HPCI System D.1 Restore HPCI System 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
to OPERABLE status.
AND QB Dne low pressure ECCS D.2 Restore low pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> injection / spray ECCS injection / spray subsystem is subsystem to OPERABLE inoperable.
status.
E.
Two or more ADS valves E.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
AND QB E.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l
Required Action and dome pressure to associated Completion s 150 psig.
{
Time of Condition C or D not met.
i l
F.
Two or more low F.1 Enter.LCO 3.0.3.
Immediately l
pressure ECCS injection / spray subsystems inoperable.
more ADS valves inoperable.
HATCH UNIT 2 3.5-2 Amendment No. 145
.e ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection / spray 31 days subsystem, the piping is filled with water l
from the pump discharge valve to the injection valve.
l i
l l
NOTE--------------------
I Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE l
during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) low pressure permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.1.3 Verify ADS air supply header pressure is 31 days I
a 90 psig.
SR 3.5.1.4 Verify the RHR System cross tie valve 31 days is closed and power is removed from the valve operator.
SR 3.5.1.5 Verify each LPCI inverter output voltage is 31 days a 570 V and :s; 606 Y while supplying the l
respective bus.
(continued)
HATCH UNIT 2 3.5-3 Amendment No. 145 l
v
ECCS -- Operating i
3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.6
NOTE--------------------
Only required to be performed prior to entering MODE 2 from MODE 3 or 4, when in MODE 4 > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
i Verify each recirculation pump discharge 31 days i
valve cycles through one complete cycle of full travel or is de-energized in the closed position.
SR 3.5.1.7 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice pressure.
Testing Program i
SYSTEM HEAD NO.
CORRESPONDING OF TO A REACTOR 11SlEM FLOW RATE PUMPS PRESSURE OF CS a: 4250 gpm 1
a: 113 psig 4
LPCI at 17,000 gpm 2
a: 20 psig 6
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 i
adequate to perform the test.
j l
Verify, with reactor pressure s 1058 psig 92 days and a 920 psig, the HPCI pump can develop a flow rate at 4250 gpm against a system head corresponding to reactor pressure.
(continued)
HATCH UNIT 2 3.5-4 Amendment No.145
1._.
\\
i i
i ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued.)
SURVEILLANCE FREQUENCY i
NOTE--------------------
i 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 i
the HPCI pump can develop a flow rate a: 4250 gpm against a system head corresponding to reactor pressure.
i 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 exc.luded.
Verify the ADS actuates on an actual or 18 months i
simulated automatic initiation signal.
l l
l SR 3.5.1.12
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 each ADS valve opens when manually 18 months actuated.
(continued) i I
HATCH UNIT 2 3.5-5 L Amendment No.145
ECCS -- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) i l
SURVEILLANCE FREQUENCY i
SR 3.5.1.13
NOTE--------------------
i ECCS injection / spray initiation instrumentation response time may be assumed from established limits.
Ver'ify each ECCS injection / spray subsystem 18 months 1
ECCS RESPONSE TIME is within limits.
s i
i HATCH UNIT 2 3.5-6 Amendment No.145
A a
m
as--
E o2--,.
.n 4
i LLS Valves 3.6.1.6 i
3.6 CONTAINMENT SYSTEMS 3-3.6.1.6 Low-Low Set (LLS) Valves LC0 3.6.1.6 The LLS function of three of four safety / relief valves shall I
be OPERABLE.
l APPLICABILITY:
MODES 1, 2, and 3.
1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Two or more LLS valves A.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
AE A.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> i
l HATCH UNIT 2 3.6-18 Amendment No.145