ML19345E676

Proposed Tech Specs Changes to Sections 3 & 4 Re Reactor Bldg Cooler Surveillance & Svc Water Chlorination Procedures

ML19345E676
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/30/1981
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19345E675	List: ML19345E674 ML19345E676
References
NUDOCS 8102050488
Download: ML19345E676 (5)

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T BASIS FOR CHANGE

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Per AP&L's commitment in our November 6,1980 letter we are submitting the attached Technical Specification change to cover similar surveillance

! and chlorination procedures on the Reactor Building coolers as already

exist on ANO-2. With the addition of flow instrumentation in the service

' water lines to the Reactor Building coolers this~ change -is possible.

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systems which will not remove more than one train of each system from service. Maintenance shall not be performed on components which would make the affected system train inoperable for more than 24 consecutive hours. Prior to initiating maintenance on any component of a train in any system, the redundant component of that system shall be demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the maintenance.

3.3.6 If the conditions of Specifications 3.3.1, 3.3.2, 3.3.3, 3.3.4 and 3.3.5 cannot be met except as noted in 3.3.7 below, reactor shutdown shall be initiated and the reactor shall be in hot shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and, if not corrected, in cold shutdown condition within an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.3.7 Exceptions to 3.3.6 shall be as follows:

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(A) If the conditions of Specification 3.3.1(F) cannot be met, reactor operation is permissible only during the succeeding seven days unless such components are sooner made operable, provided that during such seven days the other BWST level instrument channel shall be operable.

(B) If the conditions of Specification 3.3.3(D) cannot be met, reactor operation is permissible only during the succeeding seven days unless such components are sooner made operable, provided that during such seven days the other CFT instrument channel (pressure of level) shall be operable.

(C) If the conditions of Specification 3.3.4(A) cannot be met because one group of the required reactor building emergency cooling units is inoperable but both reactor building spray systems are operable, restore the inoper-able group of cooling units to operable status within 7 days or be in at least hot standby _within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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(D) If the conditions of Specification 3.3.4(A) cannot be met because two groups of the reqaired reactor building emergency cooling units are inoperable but bova reactor building spray. systems are operable, restcre at least one group of cooling units to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot standby within.the~next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore both above required groups of cooling

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units to operable status within 7 days of initial: loss or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown'within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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(E) If the conditions of Specification 3.3.4(A) cannot be a

met because one group of the required reactor building cmergency cooling units are inoperable and one reactor building spray system is inoperable, restore the inoper-able spray system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or ,

be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and .

in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore the inoperable group of reactor building emergency cool- -

ing units to operable status within 7 days of initial '

loss or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

-(F) If the conditions of Specification 3.3.4(A) cannot be met because any cooling units of the required groups is inoperable because its associated f an is inoperable, verify that the operable cooling unit in that group has a service water flow rateit 1200 gpm through its cooling coils or restore the inoperable cooling unit to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Bases The requirements of Specification 3.3.1 assure that below 350F, adequate long term core ccoling is provided. Two low pressure injection pumps are specified. However, only one is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident.

The post-accident reactor building cooling and long-term pressure reduction may be accomplished by four cooling units, by two spray units or by a cambi-nation of one cooling unit and one spray unit. Post-accident iodine removal may be accomplished by one of'the two spray system strings. The'specified

- requirements assure that the required post-accident components are available for both reactor building cooling and iodine removal. Specification 3.3.1

assures that the required equipment is operational.

The borated water storage tank is used for three purposes:

(A) As a supply of borated water for accident conditions.

(B) As an alternate supply of borated. water for reaching cold shutdown.(2).

(C) As a supply of borate ater-for flooding the fuel transfer canal during refuelit operation.(3)

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4.5.2 Reactor Building Cooling Systems Applicability Applies to testing of the reactor building cooling systems.

Objective To verify that the reactor building cooling systems are operable.

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. Specification 4.5.2.1 System Tests 4.5.2.1.1 Reactor Building Spray System (a) Once every 18 months, a system test shall be conducted to demon-strate proper operation of the system. A test signal will be applied to demonstrate actuation of the reactor building spray aystem (except for reactor building inlet valves to prevent water entering nozzles). .

(b) Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray nozzles at least every five years.

(c) The test will be considered satisfactory it' visual observation and control board indication verifies that all components have responded to the actuation signal properly.

3 4.5.2.1.2 Reactor Building Cooling System (a) At least once per 14 days, each reactor building cooling group shall be tested to demonstrate proper operation of the system.

The test shall be performed in accordance with the procedure summarized below:

(1) Verifying a service water flow rate of > 1200 gpm to each group of cooling units.

(2) Chlorinating the service water during the surveillance in 4.5.2.1.2.a.1 above, whenever service water temperature is between 60F and 80F.

(b) At least once per 31 days, each reactor building cooling group shall be tested to demonstrate proper operation of the system.

The test shall be performed in accordance with the procedure summarized below:

(1) Starting (unless already operating) each operational cooling unit from the control room.

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9 (2) Verifying that each operational cooling unit operates for at least 15 minutes.

(c) Once every 18 months, a system test shall be conducted to demon-

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strate proper operation of the system. The test shall be per-formed in accordance with the procedure se=marized below:

(1) A test signal will be applied to actuate the reactor building cooling operation.

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(2) Verification of the engineered safety features function of the service water system which supplies the reactor building coolers shall be made to demonstrate operability of the coolers.

(3) The test will be considered satisf actory if control board indication verifies that all components have responded to the actuation signal properly.

4.5.2.2 Co=ponent Tests 4.5.2.2.1 Pu=ps .

At intervals not to exceed 3 months the reactor building spray pu=ps shall be started and operated to verify proper operation.

Acceptable performance will be indicated if the pump starts, operates for fifteen minutec, and the discharge pressure and flow are within 10% of a point on the pu=p head curve.

4.5.2.2.2 Valves

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At intervals not to exceed three months each engineered safety features valve in the reactor building spray and reactor building cooling system and each engineered safety features vr've assoc 1-ated with reactor building cooling in the service water system shall be tested to verify that it is operable.

Bases The reactor building cooling system and the reactor building spray system are redundant to each other in providing post-accident cooling of the reactor building atmosphere to prevent the building pressure from exceed-ing the design pressure. As a result of this redundancy in cooling capa-bility, the allowable out of service t'me requirements for the reactor building cooling system have been apprefriately adjusted. However, the allowable out of service time requirements for the reactor building spray system have been maintained consistent with that assigned other inoperable engineered safeguard equipment since the reactor building spray system also provides a mechanism for removing' iodine from the ~ reactor building atmosphere.

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Service water chlorination is performed during reactor building cooler surveillance to prevent buildup of Asian clams in the coolers when service water is pumped through the cooling coils. This is performed when service water temperature is between 60F and 80F since in this water temperature range Asian clams can spawn and produce larva which could pass through

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service water system strainers.

The delivery capability of one reactor building spray pump at a time can be tested by opening the valve in the line from the borated water storage

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tank, opening the corresponding valve in the test line, and starting the

. corresponding pump. Pump discharge pressure and flow indication demon-ctrate performance.

With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection valves can each be opened and closed by operator action. With the reactor building spray inlet valves closed, low pressure air or smoke can be blown through the test connections of the a reactor building spray nozzles to demonstrate that the flow paths are open.

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The equipment, piping, valves, and instrumentation of the reactor building

cooling system are arranged so that they can be visually inspected. The

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• cooling units and associated piping are located outside the secondary con-crete shield. Personnel can enter the reactor building during power oper-ations to inspect and maintain this equipment. The service water piping and valves outside the reactor building are inspectable at all times.

Operational tests and inspecticns will be performed prior to initial startup.

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