ML20212M987

Proposed Tech Specs Allowing Performance of Hydrostatic or Leak Testing W/Noncritical Reactor Core

ML20212M987
Person / Time
Site:	Hatch
Issue date:	03/04/1987
From:	GEORGIA POWER CO.
To:
Shared Package
ML20212M979	List: ML20212M977 ML20212M987
References
NUDOCS 8703120302
Download: ML20212M987 (6)

Text

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LIMITING CON 0!TIONS FOR OPERATION SURVE[LLANCE REQUIREMENTS 3.5.C.3.

Two Pumos inocerable 4.5.C.3.

Two Pumos inocerable If two RHR When two RHR service water cumps inoperable,, service water pumps arethe reactor *may remain-are inoperable, the remaining

• in operation for a perico not to operable RHR servAce water exceed seven (7) days provided all subsystems and their associated redundant active comconents in both diesel generators shall be of the RHR service water subsystems demonstrated to De operable are operable, insnediately and daily thereaf ter for seven (7) days or until the inoperable comconents are returned to normal operation.

4 Shutdown Reauirements i

l If Specifications 3.5.C 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 />.

O.

Hiah Pressure coolant Iniection fHPCI)

O.

Hiah Pressure Coolant Infection (HPCI) System

}y11gg 1.

Normal System Availability 1.

Normal Coerational Tests HPCI system testing shall be performed as follows:

1133 Frecuency a.

The HPCI $ystem shall be 4.

Si.aulated Once/ Operating operable automatic Cycle.

actuation 1.

Prior to reactor startup test from a cold condition, or D.

Flow rate at Once/3 months 2.

When irradiated fuel is in normal reactor the reactor vessel and the vessel oper-reactor pressure is greater ating pressure than 150 psig, except as and

.1ow rate at once/ Operating stated in Specification g

3.5.0.2.

• 150 psig Cycle reactor pressure l

l l

t

• HPCI is not required to be operable for performance of inservice hydrostatic or leak testing with reactor pressure greater than 150 psig and all control rods inserted.

l HATCH = UNIT 1 3.$-6 Amendment No. 107 0703120302 070304 l

I,Dit ADOCK 05000321 P

l PDit 1

LIMITING CONDITIONS Foe OPERATION SURVElltANCE REQUIRENENTS 3.5.E.1. Normal Swstem Availability (Cont.)

4.5.E.1. Norwal Onorational Tests (Cont.)

a.(2) When there is irradiated

b. Verifying that suc-Once/ Operating fuel in the reactor vessel tion for the RCIC Cycle and the reactor pressure system is automati-is above 150 psig except cally transferred as stated in Specification l

from the CST to the suppression pool on 3.5.E.2.

• a simulated low CST level or high suo-pression pool level

signal,

c. Flow rate at once/3 months normal reactor vessel operating pressure and Flow rate at Once/ Operating 150 psig Cycle reactor pressure.

The RCIC pump shall deliver at least 400 gpm during each flow test.

d. Pump Operability Once/ month

e. Motor Operated Once/ month valve operability

2. Oneration with inocerable 2.

Surveillance with Inonerable Comnonents Commonents if the RCIC system is inoperable, When the RCIC system is inoper-the reactor may remain in oper-able, the HPCI system shall be ation for a period not to exceed demonstrated to be operable seven (7) days if the HPCI system immediately and daily thereaf ter is operable during such time, until the RCIC system is returned to normal operation.

3. If Specification 3.5.E.1. or 3.5.E.2. is not met, an orderly shutdown shall be initiated and the reactor shall be depressurized to less than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• RCIC is not required to be operable for performance of inservice hydrostatic or leak testing with reactor pressure greater than 150 psig and all control rods inserted.

HATCH - UNIT 1 3.5-8 Amendment No. 101. 107

4 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE #ENTS 3.5.F.

Automatic Deoressurization System 4.5.F.

Automatie Oeoressurization System lA0IL1 110.21 1.

Norgel Operational Tests 1.

Normal System Availability The seven valves of the Automatic a.

A simulated automatic actuation Depressurization System shall be test shall be performed on the operable:

A05 prior to startup af ter each refueling outage. Surveillance a.

Prior to reactor startup from a of all relief valves is covered cold shutdown, or in Specification 4.6.H.

b.

When there is irradiated fuel in b.

A leak rate test of each A05 the reactor vessel and the valve accumulator, check valve, reactor is above 113 psig except and actuator assembly shall be as stated in Specification performed during each refueling 3.5.F.2.

• I outage at a pressure of 90 t 18 psig. The leakage rate shall be verified to be 14.5 SCFH.

2.

Operation with Inocerable 2.

Surveillance with Inocerable Components Commonents If one of the seven A05 valves is When it is determined that one of known to be incapable of automatic the seven A05 valves is incapable of operation, the reactor may remain in automatic operation, the HPCI system operation for a period not to exceed and the actuation logic of the other seven (7) days, provided the HPCI A05 valves shall be demonstrated to I

system is operable. (Note that the be operable immediately and daily pressure relief function of these thereafter until all seven A05 valves is assured by Specification valves are capable of automatic 3.6.H.; Specification 3.5.F. only operation, l

applies to the ADS function).

3.

Shutdown Reauirements i

If Specification 3.5.F.1. or 3.5.F.2.

cannot be met, an orderly shutdown will be initiated and the reactor i

pressure shall be reduced to 113 psig or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

J

• The ADS valves are not required to be operable for performance of inservice hydrostatic or leak testing with reactor pressure greater than 113 psig and all control rods inserted.

I l

l HATCH - UNIT I 3.5-9 Amendment No. 27, 27, 111 I

I

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.H.1.

Relief / Safety Valves 4.6.H.1.

Relief /Safetv Valves a.

When one or more relief / safety a.

End of Ooeratino Cycle valve (s) is known to be failed an orderly shutdown shall be initiated Approximately one-half of all and the reactor depressurized to relief / safety valves shall be benchchecked or replaced with less than 113 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Prior to reactor startup from a a benchchecked valve each re-cold condition all relief / safety fueling outage. All 11 valves valves shall be operable.**

l will have been checked or re-placed upon the completion of every second operating cycle.

b.

With one or more reitef/ safety b.

Each Operatino Cycle valve (s) stuck open, place the reactor mode switch in the shutdown position.

Once during each operating cycle, at a reactor pressure

> 100 psig each relief valve shall be manually opened until thermocouples downstream of the valve indicate steam is flow-ing from the valve.

c.

With one or more safety / relief valve c.

Intecrity of Relief Valve tailpipe pressure switches of a Bellows

• Safety / relief valve declared inoperable and the associated The integrity of the relief valve safety / relief valve (s) otherwise bellows shall be continuously indicated to be open, place the monitored and the pressure reactor mode switch in the Shut-Switch calibrated once per down position.

operating cycle and the accu-mulators and air piping shall be inspected for leakage once per operating cycle.

d.

With one safety / relief valve tailpipe d.

Relief Valve Maintenance pressure switch of a safety / relief valve declared inoperable and the asso-At least one relief valve shall ciated safety / relief valve (s) otherwise be disassembled and inspected indicated to be closed, plant operation each operating cycle.

may continue. Remove the function of that pressure switch from the low low e.

Ooerability of Tail pioe set logic circuitry until the next COLD Pressure Switches SHUT 00WN. Upon COLD SHUT 00WN, restore the pressure switch (es) to OPERA 8LE The tail pipe pressure switch status before STARTUP, of each relief / safety valve shall be demonstrated operable e.

With both safety / relief valve tailpipe by performance of a:

pressure switches of a safety / relief valve declared inoperable and the asso-1.

Functional Tests ciated safety / relief valve (s) otherwise indicatedtobec],osed,restoreatleast a.

At least once per 31 one inoperable switch to OPERABLE status days, except that all, within 14 days or be in at least HOT portions of instrumen-

$ HUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> tation inside the pri-and in COLD SHUTOOWN within the mary containment may be following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, excluded from the functional test, and

• • The Relief / Safety valves are not required to be operable for performance of inservice hydrostatic or pressure testing with reactor pressure atenter than 111 pois and a!!

control rode inserted. Overpreneurs protection will be provided as required by A5ME code.

HATCH - UNil 1 3.6 9 Amendment No. 56, 71, 103

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Based on Surveillance Test Results i

LINITING CON 0lfl0NS FOR OPERATION SURVEILLANCE REQUIRE 4ENTS 2.

Primary Containment Inteority 4.7.A.2.

Leak Testina to verify 1

Primarv Containment Intearity Primary containment integrity is required:

Primary containment integrity shall be demonstrated by the a.

Prior to withdrawing following test procedures:

control rods for the purpose of going critical.

4.

Tyne A Tests - Intearated leak Rate fest ( LLRT)*

b.

Whenever the reactor is critical.

Primary containment integrity is confirmed if the Icak rate does c.

Whenever the reactor water not exceed the maximum allow-temperature is above 212'F able leak rate, La* Of I 2 and fuel is in the reactor weight percent of the contained vessel.**

air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at the peak test pressure.

An exception is made while per-forming low power physics tests (1) Type A tests shall be performed at atmospheric pressure at power under the program established i

levels not to exceed 5 MWt, during in Appendix J of 10 CFR whici time primary containment Part 50. (Reference 1).

integrity is not required.

La - Maximum allowable peak pressure test leak rate - 1.2 weight percent i

per day e

t,g - Maximum allowable reduced pressure test leak rate Lam - Measured peak pressure test leak rate - values are subject to change with each ILRT performed L m

• Measured reduced pressure test leak rate - values are subject to i

t change with each ILRT performed Lao - Allowable operational leak rate for peak pressure tests - values are subject to change with each ILRT performed L o - Allowable operational leak rate for reduced pressure tests - values t

are subject to change with each (LRT performed (All leakage rates measured in weight percent of contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

Pa - Peak test pressure - $9 plig Pg - Reduced test pressure - 29.5 psig

• • Primary Containment Integrity is not required for performance of inservice hydrostatic or leak testing with reactor coolant temperature greater than 212.0F and all control rods inserted.

HATCH - UNtf 1 3.7-2

-