ML20080J118

Proposed Tech Specs 3.5-6-8 & 3.5-16-17 Re Changes to HPCI & RCIC Sys Requirements

ML20080J118
Person / Time
Site:	Hatch
Issue date:	02/06/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20080J070	List: ML20080J068 ML20080J118 ML20080J142
References
TAC-48294, TAC-54495, TAC-98294, NUDOCS 8402140448
Download: ML20080J118 (5)

Text

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LIMITING CONDITIONS FOR OPFRATION SURVEILLANCE REQUIREMFF7S C.3. Two Pumps Inoperable 4.5.C.3. Two Pumps Inoperable If two RHR service water pumps are When two RHR service water pumps

-inoperable, the reactor may remain are inoperable, the remaining in operation for a period not to operable RdR service water sub-exceed seven (7) days provided all systems and their associated redundant active componenta in both diesel generators shall be of the RHR service water subsystems demonstrated to be operable l are operable. immediately and daily thereaf ter for seven (7) days or until the inoperable components are returned to normal operation.

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4. _Chutdown Requirements 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 />.

1 j D. High' Pressure Coolant Injection D. High Pressure Coolant Inj ec tion l (HPCI) System (HPCI) System '

l.' Normal System Availability 1. Normal Operational Tests HPCI System testing shall be performed as follows:

Item Frequency a.The HPCI System shall be operable: a. Simulated Auto- Once/ Operating matic Actuation Cycle (1) Prior to reactor startup from a Test cold condition, or (2) When irradiated fuel is in the reactor vessel and the reactor pressure is greater than 150 psig, except as stated in Specification l

3.5.D.2.

b. Flow rate at Once/3 months normal reactor vessel opera-ting pressure and Flow rate at Once/ Operating 150 psig Cycle reactor pressure

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRENENTS 4.5.D.I. Normal Operational Tests (Continued)

The HPCI pumps shall deliver Operation with Inoperable at least 4250 gym during each 3.5.D.2. flow rate test.

Components

c. Pump Oper- Once/ month If the HPCI system is inoperable, ability the reactor may remain in oper-ation for a period not to exceed d. M t r Oper- Once/ month foarteen (14) days provided the ADS, ated valve CS system, RRR system LPCI rode, operability and RCIC system are operable,

2. Surveillance with Inoperable ,

With the surveillance requirements of Specification.4.5.D.1 not per- When the HPCI system is inoper-formed at the required frequencies able, the ADS actuation logic, due to low reactor steam pressure, the RCIC system, the RHR system reactor startup is permitted and LPCI mode, and the CS system the appropriate surveillance will shall be demonstrated to be oper-be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after able immediately. The RCIC system reactor steam pressure is adequete and ADS logic shall be demon-to perform the tests. strated to be operable daily thereaf ter until the HPCI system is returned to normal operation.

3. Shutdown Requirements if Specification 3.5.D.1 or 3.5.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor vessel pressure shall be reduced to 150 psig or less l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Reactor Core Isolation Cooling E. Reactor Core Isolation Cooling E.

(RCIC) System (RCIC) System

1. Normal System Availability 1. Normal Operational Tests RCIC system testing shall be performed as follows:

Item Frequency

a. The RCIC System shall be operable: a. Simulated Once/OperatinE Automa ted Cycle (1) Prior to reactor startup Actuation from a cold condition, or Test 3.5-7

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 5. E.1. ' Normal System Availability (Continued) 4.5.E.1. Normal Operational Tests (Continued) a.(2) when there is irradiated fuel in the reactor vessel and the reactor pressure is above 150 psig, except l as stated in Specification 3.5.E.2.

Item Frequency

b. Flow rate at once/3 months normal reactor vessel oper-ating 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.

c. Pump Oper- Once/ month ability

d. Motor Oper- Once/ month ated valve operability

2. Operatien with Inoperable 2. Surveillance with Inoperable Components Componen ts 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 thereafter is operable during such time. until the RCIC system is returned to normal operation

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

A 3.5-8

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BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.5.C. RHR Service Water System

-1. Normal System Availability Since the RHR service water system supplies cooling water for decay heat removal from the RHR system under post accident conditions, it is required whenever irradiated fuel is in the reactor.

2. Operation With Inoperable Components Two RHR pumps are provided in each RHR subsystem. Two pumps are required for long term heat removal. Therefore, the 30 and 7 day repair times are justified for 1 and 2 pump inoperability respectively.

D. High Pressure Coolant Injection (HPCI) System  ;

1. Normal System Availability The HPCI system is provided to assure that the reactor core is adequately cooled to limit fuel'elad temperature in the event of a small break in the nuclear system and loss of coolant which does not result in rapid depressurization of the reactor vessel. The HPCI system permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCI system con-tinues to operate until reactor vessel pressure is below the pressure at which LPCI operation or core spray system operation maintains core cooling.

l The capacity of the system is selected to provide this required core j- cooling. The HPCI pump is designed to putp 4250 gpm at reactor pressures

( between 1120 and 150 psig. Two sources of water are available. Initially, water from the condensate storage tank is used instead of injecting water from the suppressius pool into the reactor.

- When the HPCI system begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the conden-sation of steam by the cold fluid pumpe* into the reactor vessel by the HPCI system. As the reactor vessel pressur continues to decrease, the HPCI flow momentarily reaches equilibrium with the flow through the break. Continued depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This type of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.

3.5-16

BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRMENTS 3.5.D.2. Operation With Inoperable Components The HFCI system serves as a backup to the RCIC system as a source of feedwater makeup during primary system isolation conditions. The ADS serves as a backup to the HPCI system for reactor depressurization for postulated transients and accidents. Both these systems are checked

, for operability if the HPCI system is determined to be inoperable.

Considering the redundant systems, an allowable repair time of seven (7) days was selected.

E. Reactor Core ' Isolation Cooling (RCIC) System

1. Normal Systen Availability The various conditions under which the RCIC system plays an essential role in providing makeup water to the reactor vessel have been identified by evale:. ting the various plant events over the full range of planned

. ope.ations. The specifications ensure that. the function for which the RCIC system was designed will be available when needed.

Because the low-pressure cooling systems (LPCI and Core Spray) are capable of providing all the cooling required for any plant event when

[ nuclear, sys .an pressure is below 150 psig, the RCIC system is not required below this pressure. RCIC system design flow (400 gpm) is sufficient to maintain water level above the top of the active fuel for a complete loss of feedwater flow at the design power.

2. Operation With Inoperable Components l

' Consideration of the availability. of the RCIC system reveals that the

' average risk ~a'ss~ocia' ted' with failure' of . the RCIC system to cool the core -

when required 'is not' increased if'the RCIC system is inoperable for no longer than seven (7) days, provided that the HPCI syst 3m is operable during this period.

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F.+ Automatic Depressurization System (ADS) l 2

1. Normal System Availability This sp cification, ensures the operability of the i ADS under all con-ditions.for. which the depressurization ~of the nuclear system is an essential response to unit abnormalities.

The nuclear system pressure relief system provides automatic nuclear

' system depressurization for small-breaks in the nuclear system so that .

the low-pressure coolant injection (LPCI) and the core spray system can operate to protect the fission product barrier. Note that this Specification applies to the automatic feature of the pressure relief system.

3.5-17 r.

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