ML20050C959

Proposed Tech Specs for Amend to HPCI & Reactor Core Isolation Cooling Requirements

ML20050C959
Person / Time
Site:	Hatch
Issue date:	04/05/1982
From:	GEORGIA POWER CO.
To:
Shared Package
ML20050C957	List: ML20050C956 ML20050C959
References
TAC-48294, TAC-54495, NUDOCS 8204090450
Download: ML20050C959 (8)

Text

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1 ATTACHENT 1 I

NRC DOCKET 50-321 OPERATING LICENSE DPR-57

• EDWIN I. HATCH NUCLEAR PLANT UNIT 1 HPCI AND RCIC LCO CHANGE PROPOSAL

! . The proposed changes 'to ' Technical Specifications (Appendix A to

Operating License DPR-57) would be incorporated as follows

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8204090450 820405 PDR P

ADOCK 05000321 PDR  !

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I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 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 i j in operation for a period not to operable RHR service water sub- l exceed seven (7) days provided all systems and their associated redundant active components in both diesel generators shall be of the RHR service water subsystems demonstrated to be operable ere operable. - immediately and daily thereafter for seven (7) days or until the

inoperable components are i returned to normal operation.

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4. Shutdown Requirements If Specifications 3.5.C cannot be met, the reactor shall be placed in the Cold Shutdown Condition I

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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i D. High Pressure Coolant Injection D. High Pressure Coolant Injection (HPCI) System (HPCI) Syst em

1. Normal Syst em 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 f rom a Test cold condition, or (2) When irradiated fuel is in the reactor vessel and the reactor pressure is greater than 150 psig,l except as stated in Specification

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 3.5-6 l

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LIMITING CONDITIONS F0F OPEE.ATION SURVEILLANCE REQUIREMENTS 4.5.D.1. Ncruel Operational Tests (Continued)

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

Components

c. Pump Oper- Once/ month If the KPCI system is inoperable, ability the reactor may remain in oper.

ation for a period not to exceed . Not r Oper- Once/ month fourteen (14) days provided the ADS, ated valve CS system, RRR system LPCI rode, Operability and RCIC system are operable.

2. _ Surveillance with Ineperable 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 stea= pressure, the RCI C sys t em , the RHR system reactor startup is permit ted and LPCI mode, and the CS system the appropriate surveillance vill 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 adequate and ADS logic shall be demon-to perform the tests. strated to be operable daily thereafter until the HPCI system is returned to normal operation.

3. Shut dsen Requirerents If Specification 3.5.D.1 or 3.5.D.2 cannot be met, an orderly shutdovn shall be initisted 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 />.

E. Reactor Cere Isolation Cooling E. Reactor Core Isolatien Cooling (RCIC) System (RCIC) Syster

1. Norral Syster Availability

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

Item Fre qu en cy

a. Simulated Once/ Operating

a. The RE1C System shall be operable:

Automated Cycle (1) Prior to reacter startup Actuation f ror a cold condition, or Test Amendment No. 77 3.5-7

SLTRVEILI.ANCE REQUIRDENTS

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LIMITING CONDITIONS FOR OPERATION 4.5.E.1. Normal Operational Tests _ (Continued) 5.E.1. Normal System Availability (Continued) o.(2) when there is irradiated f uel in the reactor vessel

• and the reactor pressure is above 150 psig, except l [

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as stated in Specification .

3.5.E.2. Frequene_y Item

b. Flow rate at Once/3 menths normal reactor vessel oper-ating pressure and Once/ Operating

• Flow rate at 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 Ope r- Once/ month sted valve operability 2, Surveillance with inoperable

2. _ Operation with Inoperable Components Components When the RCIC system is inoper-If the RCIC system is inoperable, able, the HPCI system shall be the reactor may remain in oper- demonstrated to be operable ation for a period not to exceed immediately and daily thereafter seven (7) days if the HPCI system until the RCIC syste= is returned is eperable during such time. to normal operation

3. Shutdevn Requirements If Specification 3.5.E.1 or 3.5.E.2 is not met, an orderly shutdevn shall be initiated and 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 />.

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F Automatic Depressurization System 4.5.F Automatic Depressurization System (ADS) (ADS)

1. Normal System Availability 1. Normal Operational Tests Six of the seven valves of the A simulated automatic actuation Automatic Depressurization System test shall be performed on the shall be operable: ADS prior to startup af ter each refuelitig outage. Surveillance

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

h. When there is irradiated fuel in the reactor vessel and the l reactor is above 150 psig except l as stated in Specification 3.5.F.2.

. 2. Operation With Inoperable 2. Surveillance With Inoperable Components Components If two of the seven ADS valves are When it is determined that two known to be incapable of automatic of the seven ADS valves are operation, the reactor may remain incapable of automatic operation, in operation for a period not to the HPCI system and the actuation exceed thirty (30) days provided logic of the other ADS valves the HPCI systen is operable. (Note shall be demonstrated to be that the pressure relief function operable immediately and every of these valves is assured by Spec- seven (7) days thereafter until ification 3.6.H; Specification 3.5.F six ADS valves are capable of only applies to the ADS function). automatic operation.

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

Amendment No. 27 3.5-9 i

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BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l ,,

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 it. operability 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 clad 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.

The capacity of the system is nelected to provide this required core cooling. The HPCI pump is designed to pump 4250 gym 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 suppression pool into the reactor.

When the FPCI system begins operation, the reactor depressurizes more rapidly than would occur if RPCI was not initiated due to the conden-sation of steam by the cold fluid pumped into the reactor vessel by the HPCI system. As the reactor vessel pressure continues to decrease,

> the HPCI flow momentarily reaches equilibrium with the flow through the break. Centinued depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This ty,e i of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage nf any kind occurs for breaks that lie within the capacity range of the HPCI.

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BASES FOR LIMITING CONDITIONS _FOR OPERATION AND SUPVEILLANCE REQUIREMENTS 3.5.D.2. Operat ion With Inoperable Components The !!PCI 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 llPCI system for reactor depressurization for postulated transients and accidents. Both these systems are checked for operability if the llPCI 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 System Availability The various conditions under which the RCIC system plays an essential role in providing makeup water to the reactor vessel lave been identified by evaluating the various plant events over the full range of planned operations. The specifications ensure that the function for which the RCIC system was designed will be available when needed.

RCIC system design flow (400 gpm) in 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 Consideration of the availability of the RCIC system reveals that the average risk associated with f ailure 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 IIPCI system is operable during thin period.

F. Automatic Depressurization System (ADS)

1. Normal System Availability This specification ensures the operability of the ADS under all con-dit ions for which the depressurization of the nuclear system is an i essential response to unit abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for mall 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.

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ATTACHENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 hPCI AND RCIC LCO Ce.ANGE PROPOSAL Pursuant to 10 CFR 170.22, Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that:

a. The proposed amendment does not require evaluation of a new Safety Analysis Report and rewrite of the facility license;

b. The proposed amendment does not require evaluation of several complex issues, involve ACRS review, or require an environmental impact statement;

c. The proposed amendment does not involve a complex issue or more than one environmental or safety issue;

d. The proposed amendment does involve a single safety issue, namely that the Limiting Conditions for Operation of two safety-related systems are being altered;

e. The proposed amendment is therefore a Class Ill amendment.