ML19210C309

Safe Shutdown Capability

ML19210C309
Person / Time
Site:	Robinson
Issue date:	10/25/1979
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML14190A536	List: ML14190A535 ML19210C309
References
NUDOCS 7911140059
Download: ML19210C309 (7)

Text

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s STAFFPOSITION SAFE SHUTDOWN CAPASILITY Staff Concern During the staff's evaluation of fire ' protection programs at operating plants, one or more specific plant areas may be identified in which the staff does not have adequate assurance that a postulated fire will not damage both redundant divisions of shutdown systers.

This lack of assurance in safe shutdown capability has resulted from one or both of the folicwing situations:

• - Case A: The licensee has not adequately identified the systems and components required for safe shutdown and their location in specific fire areas.

• Case B: The licensee har not demonstrated that the fire pectaction for specific plant areas will prevent damage to both redundant divisions of safe shutdown connenents identified in these areas.

For Case A, the staff has required that an adequate safe shutdown analysis be performed. This evaluation includes the identification

, of the systems required for safe shutdown and the location of the system components in.the plant. Where it is determined by this evaluation that safe shutdown components of both redundant divisions are located in the same fire area, the licensee js required to demonstrate that a postulated fire will not damage both divisions or provide alternate shutdown capability as in Case B.

For Case B, the staff may have required that an alternate shutdown capability be provided with is independent of the area of concern or the licensee may have proposed such a capability in lieu of certain additional fire protection modifications in the area. The specific modifications associated with the area of concern along with other systems and equipment already independent of the area form the alternate shutdown capability. For each plant, the modifications needed and the combinations of systems which prqvide the shutdown functions may be unique for each critical area; however, the shQtdown functions provided should maintain plant parameters within the bounds of the limiting safety consequences deemed acceptable fo'r the design basis event.

Staff Position Safe shutdown capability should be demonstrated (Case A) or alternate shutdown capability provided (Case B) in accordance with the guidelines provided below:

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1. Desien Basis Event The design basis event for considerin'g the need for alternate shutdown is a postulated fire in a specific fire area containing redundant safe shutdown cables /equirment in close proximity where it has been determined that fire protection means cannot assure that safe shutdown capability will be preserved. Two cases should be considered:

(1) offsite power is available; and (2) offsite power is not available.

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. 2. Limitinc Safety Consecuences and Recuired Shutdcwn Functions 2.1 No fission product boundary in'tegrity shall be affected:

a.

No fuel cisd damage; b.

No rupture of any primary coolant boundary; c.

No rupture of the containment boundary.

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2.2 The reactor coolant system process variables shall be within those predicted for a loss of normal ac power.

2.3 The alternate shutdown capability shall be able to achieve and maintain subcritical conditions in the reactor, maintain reactor coolant inventory, achieve and maintain hot standby

• conditions (hot shutdown

• for a BWR) for an extended period of time, achieve cold shutdown

• conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and maintain cold shutdown conditions thereafter.

As defined in the Standard Technical Specifications.

3. Perfomance Goals 3.1 The' reactivity control function shall be capable of achieving and maintaining cold shutdown reactivity conditions.

3.2 The reactor coolant makeup function shall be capable of maintaining the reactor coplant level above the top of the core for BWR's and in the pressurizer for PWR's.

3.3 The reactor heat removal function shall be capable of achieving and maintaining decay heat removal.

3.4 The process monitoring function shall be capable of providing direct readings of the process variables necessary to perform and control the above functions.

3.5 The supporting function shall'be capable of providing th'e process cooling, lubrication, etc. necessary to pennit the operation of the equipment usied for safe shutdown by the systems identified in 3.1 - 3.4.

3.6 The equipment and systems used to achieve and maintain hot standby conditions (hot shutdown for a BWR) should be (1) free of fire damage; (2) capable of maintaining such conditions for an extended time period longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the equipment required to achieve and maintain cold snutdown is not available due to fire damage; and (3) capable of being powered by an onsite emergency power system.

3.7 The equipment and systems used to achieve and maintain cold shutdown conditions should be either free of fire damage or the fire damage to such systems should be limited such that repairs can be~ma e and cold shutdown conditions achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Equipment and systems used prior to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the fire should be.apable of being powered by an onsite emergency power system; thum 'ised after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be powered by 1 233

. offsite power.

38 These systems need not be designed to (1). seismic category I criteria; (2) single failure criteria; or (3) cope with other plant accidents such as pipe breaks or stuck valves

( Appendix A BTP 9.5-1), except those portions of these systems which interface with or impact existing safe,ty systems.

1. PWR Eouioment Generally Necessary For Hot Standby (1)

Reactivity control' Reactor trip capability (scram). Beration capability e.g.,

charging pump, makeup pump or high pressure injection pump taking suction from concentrated borated water supplies,

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and letdown system if required.

(2)

Reactor Coolant Makeuo Reactor coolant makeup capability, e.g., charging pumps or the high pressure injection pumps.

Power operated relief valves may be required to reduce pressure to allow use of the

.high pressure injection pumps.

(3) Reactor Coolant System Pressure Control Reactor pressure control capability, e.g., charging pumps or pressurizer heaters and use of the letdown systems if required.

(4)

Decay Heat Removal Decay heat removal capability, e.g., power operated relief valves.(steam generator) or safety relief valves for heat removal with a water supply and emergency or auxiliary feedwater pumps for makeup to the steam generator.

Service water or other pumps may be required to provide water for auxiliary feed pump suction if the condensate storage tank capacity is not adequate for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

(5)

Process Monitoring Instrumentation Process monitoring capability e.g., pressurizer pressure and level, steim generator level.

(6)

Succort.

The equipment required to support operation of the above described shutdown equipcent e.g., component cooling water service water, etc. and onsite power sources ( AC, DC) with their associated electrical distribution system.

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5. PWR Eouiement Generally Necessary For Cold Shutdown *

(1) Reactor Cool.at System Pressure Reduction to Residual Heat Removal System RhR Cacao 111 ty Reactor coolant system pressure reduction by cooldown using steam generator power operated nelief valves or atmospheric dump valves.

(2) Decay Heat Removal Decay heat removal capability e.g., residual heat removal system, component cooling water system a.id service water system to removal heat and maintain cold shutdown.

(3) Suecort Support capability e.g., onsite cower sources (AC & DC) or offsite after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and the associated electrical distribution system to supply the e.8 cve equiprent.

2 Equipment necessary in addition to that already provided to maintain hot standby.

6. BWR Eouiement Generally Necessary For Hot Shutdowr (1) Reactivity Control Reactor trip capability (scram).

(2) Reactor Coolant Makeuo Reactor coolant inventory makeup capability e.g., reactor core isolaticn cooling system (RCIC) or the high pressure coolant injection system (HPCI).

(3) Reactor Pressure Control and 6ecay Heat Removal De' pressurization system valvt: of safety relief valves for dump to the suppression pool. The. residual heat removal system in steam condensing node, and service water system may also be used for heat removal to the ultimate heat sink.

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(4) Sucoression Pool Cooline Residual heat removal system (in suppression pool cooling mode) service water system to maintain hot shutdown.

(5) Process Monitorinc Process monitoring capability e.g., reactor vessel level and pressure and suppression pool temoerature.

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. (6) Succort Support capability e.g., onsite power source (AC & DC) and their associated distribution systems to provide for the shutdown equipment.

7. BWR Eouicment Generally Necessary For Cold Shutdown

• At'this point the equipment necessary for hot shutdown has reduced the primary system pressure and temperature to where the RHR system may be placed in service in RHR cooling mode.

(1) Decay Heat Removal Residual heat removal system in the RHR cooling mode, service water system.

(2) Succort Onsite sources (AC & DC) or offsite after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and their associatad distribution systems to provide for shutdown equipment.

Equipment provided in addition to that for achieving het shutdcwn.

8. Inf;rmation Recuired For Stzff Reybw,

(a) Description of the systems' or portions thereor used to provide the shutdown capability and modifications required

,to achieve the alternate shutdown capability if required.

(b) System design by drawings which show normal and alternate

. shutdown control and power circuits, location of components, and that wiring which is in the area and the wiring which is out of the area that required the alternate system.

(c)

Demonstrate that changes to la'fety systems will not degrade safety systems.

(e.g., new isolation switches and control switches should meet design criteria and standards in FSAR for electrical equipment in the system that the switch is te be installed; cabinets that the switches are to be mounted in should also meet the same criteria (FSAR) as other safety related cabinets and panels; to avoid inadvertent isolation from the control room, the isolation switches should be keylocked, or alarred in the control room if in the " local" or " isolated" position; periodic checks should be made to verify switch is in the procer position for normal coeration; and a single transfer switch or other new device should not be a source for a single failure to cause loss of redundant safety systems).

(d)

Demonstrate that wiring, including power sources for the control circuit and equipment operation for the alternate shutdown method, is independent of equipment wiring in the area to be avoided.

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(e)

Demonstrate that alternate shutdown power sources, including all breakers, have isolation devices on control circuits that are routed through the area to be avoided, even if the breaker is to be operated manually.

(f)

Demonstrate that licensee procedure (s) have been developed which describe the tasks to be parfomed to effect the shutdown me thod. A suc=ary of these procedures should be reviewed by the staff.

(>g)

Demonstrate that spare fuses are a'tailable'for control circuits where these fuses,may be required in supplying power to control circuits used for the shutdown method and may be blown by the effects of a cable spreading room fire. The spare fuses should be located convenient to the existing fuses. The shutdown procedure should infom the operator to check these fuses.

(h)

Demonstrate that the manpower required to perfom the shutdown functions using the procedures of (f) as well as to provide fire brigade members to fight the fire is available as required by the fire brigade technical specifications.

(i) Demon' strate that adequate acceptance tests are perfomed.

These should verify that: equipment operates from the local control station when the transfer or isolation switch is placed in the " local" nosition and that the equipment cannot be operated from the control room; and that equip-ment operates from the control room but cannot be operated at the local control station when the transfer or isolation switch is in the " remote" position.

(j) Technical Specifications of the surveillance requirements and limiting conditions for operation for that equipment not already covered -by existing Tech. Specs. For example, if new isolation and control gwitches are added to a service water system, the existing Tech. Spec. surveillance require-ments on the service water system should add a statemnt similar to the following:

"Every third pump test should also verify that the pu=p starts from the alternate shutdown station after moving all service water system isolation switches to the local control position."

(k) Demonstrate that the systems available are adequate to perfom the necessary shutdown functions. The functions required should be based on previous analyses, if possible (e.g.,

in.he FSAR), such as a loss of normal a.c. power or shutdown on a Group I isolation (BWR). The equipment required for the alternate ca;: ability should be the same or ecuivalent to that relied on in the above analysis.

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7 (1)

Demonstrate that repair procedures for cold shutdewn systems are developed and material for repairs is maintained en si'a.

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