ML20154D094
| ML20154D094 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/06/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20154D092 | List: |
| References | |
| TAC-69408, NUDOCS 8809150143 | |
| Download: ML20154D094 (9) | |
Text
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1.0 Definitions The following terms are defined so that a uniform interpretation of these specifications may be achieved.
A.
(Deleted) 8.
Cold Shutdown Condition - Cold shutdown condition means reactor operation with the Mode Switch in the SHUT 00WN position, coolant temperature 5 212'F, and with no core alterations permitted.
During the performance of inservice hydrostatic or leak-age testing with all control.ods fully inserted and reactor coolant temperature > 212*F, and/or reactor vessel pressurized, the reactor may be considered to be in the Cold Shutdown Condition for the purpose of determining Limiting Condition for Operation applic-ability. Note that the Cold Shutdown Condition may be referred to in different ways throughout the Technical Specifications.
For example, "reactor suberitical and reactor coolant temperature
< 212*F," "irradiated fuel in the reactor vessel and the reactor is depressurized," "reactor water temperature < 212'F and reactor coolant system vented," or "reactor is not pressurized (i.e.,
5 212*F)" should be interpreted as COLO SHUTOOWN.
- However, compliance with an ACTION requiring COLD SHUT 00WN shall require a reactor coolant temperature 5 212*F.
In addition, compliance with the following Specifications is required when performing the hydrostatic or leakage testing under the identified conditions:
3.5.B.I.b. 3.5.C.l.c 3.6.F.2.d, :.7.C.l.a(7), 3.9.c, and applicable notes in Table 3.2-1.
HATCH - UNIT 1
- 1. 0-1 Proposed TS/0249q/231-18 8009150143 000906 PDR ADOCK 05000321 P
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C.
Core Alteration - Core alteration shall be the addition, removal, relocation, or movement of fuel, sources, incore instruments, or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of core alterations shall not preclude completion of the movement of a component to a safe conservative position.
D.
Desian Power - Design power refers to the power level at which the reactor is producing 105 percent of reactor vessel rated steam flow.
Design power does not necessarily correspond to 105 percent of rated reactor power. The stated design power in megawatts thermal (MWt) is the result of a heat balance for a particular plant design.
For Hatch Nuclear Plant Unit I the design power is approximately 2537 MWt.
E.
Enaineered Safety Features - Engineered safety features are those features pr,;vided for mitigating the consequences of postulated accidents, including for example containment, emergency core cooling, and standby gas treatment system.
F.
Hot Shutdown Condition - Hot shutdown condition means reactor operation with the Mode Switch in the SHUT 00WN position, coolant temperature
> 212'F, and no core alterations are permitted.
During the performance of inservice hydrostatic or leakage testing with all control rods fully inserted and reactor coolant temperature > 212*F, and/or reactor vessel pressurized, the reactor may be considered to be in the Cold Shutdown Condition for the purpose of determining Limiting Condition for Operation applicability.
However, compliance with an ACTION requiring COLD SHUT 00WN shall require a reactor coolant temperature < 212*F.
G.
Hot Standby Condition - Hot standby condition means reactor operation with the Mode Switch in the START & HOT STANDBY position, coolant temperature greater than 212*F, reactor pressure less than 1045 psig, critical.
H.
Imediate - Immediate means that the required action shall be initiated as soon as practicable, considering the safe operation of the Unit and the importance of the required action.
I.
Instrument Calibration - An instrument calibration means the adjustment of an instrument output signal so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors.
J.
Instrument Channel - An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel.
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.l' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.5.A.2.
Operation with inoperable 4.5.A.2.
Surveillance with InoDerable Componer.ts Components If one CS system loop is inoper-When it is determined that one able, the reactor may remain in core spray loop is inoperable operation for a period not to at a time when operability is exceed seven (7) days providing required, the other core spray all active components in the loop and the RHR system LPCI other CS system loop, the RHR mode shall be demonstrated to system LPCI mode and the diesel be operable immediately. The generators (per Specification operable core spray loop shall 4.9. A.2.a) are operable.
be demonstrated to be operable When performing an inservice daily until both loops are hydrostatic or leakage test returned to normal operation, with the reactor coolant temperature above or below 212'F the CS system is not required to be operable.
3.
Shutdown Reauirements If Specification 3.5. A.I.a or 3.5.A.2. cannot be met the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Residual Heat Removal (RHR) 8.
Residual Heat Removai (RHR)
System (LPCI and Containmen1 System (LPCI and Containment Coolina Mode)
Coolina Mode) 1.
Normal System Availability 1.
Normal Operational Tests RHR system testing shall be performed as follows:
Item Freauency a.
The RHR System shall be operable:
- a. Air test on Once/5 years drywell head-(1) Prior to reactor startup ers and nozzles from a cold condition, or and air or water test on (2) When irradiated fuel is in torus headers the reactor vessel and the and nozzles reactor pressure is greater than atmospheric except as stated in Specification 3.5.8.2.
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HATCH - UNIT 1 3.5-2 Proposed TS/0247q/231-147
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LIMITING CONDITIONS FOR OPERAil0N SURVEILLANCE REQUIREMENTS 3.5.B.l.
Normal System Availability (Cont.)
4.5.B.I.
Normal Operational Tests b.
One RHR loop with two pumps or two l Item Frecuency loops with one pump per loop shall be operable in the shutdown cool-b.
Simulated Once/ Operating ing mode when irradiated fuel is Automatic Cycle in the reactor vessel and the reac-Actuation tor pressure is atmospheric except Test prior to a reactor startup as stated in Specification 3.5.B.I.a.
During an inservice hydrostatic or leak-age test, one RHR loop with two pumps or two loops with one pump per loop shall also be operable c.
System flow Once/3 months in the LPCI mode, rate: Each RHR pump c.
The reactor shall not be started up shall deliver with the RHR system supplying at least 7700 cooling to the fuel pool, gpm against a system head of d.
During reactor power operation, the at least 20 psig.
LPCI system discharge cross-tie valve, E11-F010, shall be in the d.
Pump Opera-Once/ month closed position and the associated bility valve motor starter circuit breaker shall be locked in the e.
Motor Oper-Once/ month off position. In addition, an ated valve annunciator which indicates that operability the cross-tie valve is not in the fully closed position shall be f.
Both recirculation pump discharge available in the control room.
valves shall be tested for oper-ability dt. ring any outage exceeding e.
Both recire.ulation pump discharge 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have valves shall be operable prior to nct been performed during the reactor startup (or closed if per-preceding month, mitted elsewhere in these spect-fications).
2.
ODeration with Inoperable 2.
Surveillance with InoDerable Componen_11 Components a.
One LPCI P,ymo InoDerable a.
One LPCI Pumo InoDerable If one LPCI pump is inoperable,the When one LPCI pump is inoperable, reactor may remain in operation for the remaining LPCI pumps and asso-a period not to exceed seven (7) ciated flow paths and the Core days provided that the remaining Spray system shall be demonstrated LPCI pumps, both LPCI subsystem to be operable immediately and flow paths, the Core Spray system, daily thereafter, until the inoper-and the associated diesel genera-able LPCI pump is restored to tors are operable (per Specifica-normal service, tion 4.9.A.2.a).
b.
One LPCI Subsystem inoperable b.
One LPCI Su_bjystem InoDerable A LPCI subsystem is considered to When one LPCI subsystem is inoper-be inoperable if (1) both of the able, all active components of the LPCI pumps within that system are remaining LPCI subsystem and the inoperable or (2) the active Core Spray system shall be demon-valves in the subsystem flow path strated to be operable, imediately are inoperable.
HATCH - UNIT 1 3.5-3 Proposed TS/02470/243-147
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
3.5.8.2. Operation with inocerable 4.5.8.2. Surveillance with Inocerable Components (Continued)
Components (Continued) b.
If one LPCI subsystem is inoper-and daily thereafter, until able, the reactor may remain in the inoperable LPCI subsystem operation for a period not to is restored to normal service exceed seven (7) days provided that all active components of the remaining LPCI subsystem, the Core Spray system, and the associated diesel generators are operable (per Specification 4.9.A.2.a).
c.
When performing an inservice hydrostatic or leakage test with the reactor coolant temperature above or below 212'F. comply with Specification 3.5.8.1.b.
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i PAICH - UNIT 1 3.5-4 Proposed TS/0247a/243-147 I
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,r LIMlJIM_G?_N0!TIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.5.B.3.
Shutdown Peauirements If Specification 3.5.B.1.a. or 3.5.B.2. cannot be mtt, the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
+
C.
RHR Service Water System 4.5.C.
RHR Service Water System 1.
Normal System Availability 1.
Normal Operational Tests The RHR service w. iter system RHR service water system testing shall be operable:
shall be performed as follows:
ltem Freauency
[
a.
Prior to reactor startup
- a. Pump & Valve Once/3 months from a Cold Shutdown Operability Condition, or
- b. Pur.; G pacity After pump b.
When irradiated fuel is in Test:
maintenance the reactor vessel and the Each RHR ser-and once/3 reactor vessel pressure is vice water months greater than atmospheric pump shall pressure except as stated in deliver at Specification 3.5 C.2.
least 4000 gpm at a system head of at least 847 feet.
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c.
When irradiated fuel it in the reactor vessel and the reactor is depressurized at least one RHR service water loop shall be I
l operable.
f 2.
One Pumo Inocerakh 2.
One Pumo InoDerabh i
If one RHR service water When one RHR service water i
a i
pump is inoperable the pump is inoperable the remaining l
reactor may remain in operation active components of both RHR l
for a period not to exceed service water subsystems shall be l l 30 days provided all demonstrated to be operable
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other active components of t,oth imediately. An operable RHR l
subsystems are operable.
Service water pump shall be l
1 When performing an inservice demonstrated to be operable hydrostatic or leakage test, daily thereafter until the comply with Specification inoperable pump is returned to j
3.5.C.I.c.
normal service.
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HATCH - UN!T 1 3.5-5 Proposed TS/02474/231-72 i
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1
,,o LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS I
3.6.F.2.c.
When the time limits or maxi-4.6.F.2.c.3.
Primary coolant pH shall mum conductivity or chloride be measured at least once concentration limits are ex-every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever coeded, an orderly shutdown reactor coolant conduc-shall be initiated and the tivity is > 2.09mho/cm reactor shall be in the Cold at 25'C.
Shutdown Condition within 24
- hours, d.
Whenever the reactor is not pressurized, a sample of the reactor coolant shall be analyzed at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for chloride ion content and pH.
G.
Reactor Coolant Leakace*
l G.
Reactor Coolant Leakage 1.
Unidentified and Total Unidentified sources of reactor Any time irradiated fuel is in coolant system leakage shall be the reactor vessel and reactor checked by the drywell floor coolant temperature is above drain sump system and 212'F:
recorded at 1Past once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Identified sources of a.
reactor ccolant system leak-reactor coolant System age into the primary contain-leakage shall be checked by l
ment from unidentified sources the equipment drain sump shall not exceed 5 gpm when system and recorded at least i
averaged over a 24-hour period; once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The readings l
provided by the primary l
b.
reactor coolant system leakage containment atmosphere I
into the primary containment particulate radioactivity from unidentified sources monitoring system, the
(
shall not increase more than primary containment radio-2 gor when averaged over a iodine monitoring system.
l 24-hour period; and and the primary containment gaseous radioactivity t
c.
the total reactor coolant sys-monitoring system shall I
tem leakage into the primary also be recorded at least containment shall not exceed once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
25 gpm when averaged over a 24-hour period; when checked in accordance with 4.6.G.
l 2.
Leakaae Dete: tion Systemt l
a.
At les1t one of the leakage l
measurement instruments assoc-isted with each sumo shall be operable and two of the other three leakage detection systems identified in Table 3.2-10, note c shall be operable when irradiated fuel is
- Not required during performance of an inservice hydrostatic or leakage test even if reactor coolant temperature is above 212'F.
i HATCH - UNIT 1 3.6 7 Proposed TS/025C1/231-93
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.; w LIMITING CONDITIONS FOR OPERATION SURVE!LLANCE REQUIREMENTS C.
- C.
- 1. Secondary Containment Intearity 1.
Surveillance While Intearity Mainta'ned 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 subcritical and Specification #.3.A. is met.
a.
A preopertional secondary contain-
[
ment capability test shall be (2) The reactor water temperature is conducted after isolating the below 212*F and the reactor secondary containment and placing 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 (< $ mph) conditions with each filter train flow rate not (4) The fuel cask or irradiated fuel more than 4000 cfm.
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 1 of water vacuum under calm wind secondary containment and
(< 5 mph) conditions with each j
Unit 2 secondary containment filter train flow rate not more are closed and sealed.
than 4000 cfm shall be demonstrated f at each refueling outage, prior to (6) At least one door in each refueling.
access path between Unit 1
(
secondary containment and Unit 2 secondary containment is closed.
i (7) Inservice hydrostatic or 4
leakage test cf reactor I
vessel is not in progress.
L b.
Integrity of the Unit I secordary ccntainment shall be maintained i
>Juring all modes of Unit 2 plant operations except OperationJ1 Condition 4 as defined in the j
Unit 2 Technical Specifications.
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1 For secondary containment during 1982 refueling outage, see page 3,7-12a.
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i HATCH - UNIT 1 3.7-12 Proposed T5/02480/231-91 1
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