ML020440315

License Amendment 240, Technical Specification Amendment

ML020440315
Person / Time
Site:	Three Mile Island
Issue date:	02/08/2002
From:	NRC/NRR/DLPM/LPD1
To:
References
TAC MB0067
Download: ML020440315 (2)

Text

The Emergency Feedwater System is provided with two channels of flow instrumentation on each of the two discharge lines. Local flow indication is also available for the emergency feedwater system.

Although the pressurizer has multiple level indications, the separate indications are selectable via a switch for display on a single display. Pressurizer level, however, can also be determined via the patch panel and the computer log. In addition, a second channel of pressurizer level indication is available independent of the NNI.

Although the instruments identified in Table 3.5-2 are significant in diagnosing situations which could lead to inadequate core cooling, loss of any one of the instruments in Table 3.5-2 would not prevent continued, safe, reactor operation. Therefore, operation is justified for up to 7 days (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for pressurizer level). Alternate indications are available for Saturation Margin Monitors using hand calculations, the PORV/Safety Valve position monitors using discharge line thermocouple and Reactor Coolant Drain Tank indications, and for EFW flow using Steam Generator level and EFW pump discharge pressure. Pressurizer level has two channels, one channel from NNI (3 D/P instrument strings through a single indicator) and one channel independent of the NNI. Operation with the above pressurizer level channels out of service is permitted for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Alternate indication would be available through the plant computer.

The operability of design basis accident monitoring instrumentation as identified in Table 3.5-3, ensures that sufficient information is available on selected plant parameters to monitor and assess the variables following an accident. (This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," Rev. 3, May 1983:)- These instruments will be maintained for that purpose.

3-40b Amendment No. 7-8, 4-00,4-44, 4-64-, 240

3.6 REACTOR BUILDING (Continued)

Bases that no steam will be The Reactor Coolant System conditions of COLD SHUTDOWN assure if the Reactor Coolant System formed and hence no pressure will build up in the containment of activities that are being ruptures. The selected shutdown conditions are based on the type carried out and will preclude criticality in any occurrence.

the Reactor Coolant System is A condition requiring integrity of containment exists whenever in the reactor coolant to maintain open to the atmosphere and there is insufficient soluble poison are withdrawn. The Reactor the core one percent subcritical in the event all control rods an external pressure 2.5 psi greater Building is designed for an internal pressure of 55 psig, and than the internal pressure.

an evaluation of the radiological An analysis of the impact of purging on ECCS performance and completed and accepted by consequences of a design basis accident while purging have been valve is capable of closing the NRC staff. Analysis has demonstrated that a purge isolation is limited to a nominal 300 against the dynamic forces associated with a LOCA when the valve open position.

POWER OPERATION Allowing purge operations during STARTUP, HOT STANDBY and SHUTDOWN from the (T.S. 3.6.10) is more beneficial than requiring a cooldown to COLD reactor coolant system and standpoint of (a) avoiding unnecessary thermal stress cycles on the challenges to the reactor its components and (b) reducing the potential for causing unnecessary trip and safeguards systems.

system to ensure adequate The hydrogertnixing is provided by the reactor building ventilation This mixing action will prevent mixing of the containment atmosphere following a LOCA.

limit.

localized accumulations of hydrogen from exceeding the flammable 3-41c Amendment No. 87, 08, 4-67-, 4--8, 2--0 240

TABLE 4.1-4 (D POST ACCIDENT MONITORING INSTRUMENTATION 3 CALIBRATE (D

FUNCTION INSTRUMENTS CHECK TEST REMARKS z

0 P 1. Noble Gas Effluent

a. Condenser Vacuum Pump Exhaust (RM-A5-Hi) W M F (1) Using the installed check source when background is less than twice the expected increase in cpm which would result from the check source alone.

Background readings greater than this N) value are sufficient in themselves to show 0 that this monitor is functioning.

b. Condenser Vacuum Pump W(1) M F Exhaust (RM-G25)

c. Auxiliary and Fuel Handling W M F W

Building Exhaust (RM-A8-Hi)

CD

d. Reactor Building Purge W M F Exhaust (RM-A9-Hi)

e. Reactor Building Purge W(1) M F Exhaust (RM-G24)

f. Main Steam Lines W(1) M F Radiation (RM-G26/RM-G27)

Containment High Range

2. W M R Radiation (RM-G22/G23)

3. Containment Pressure W N/A F

4. Containment Water Level W N/A R

5. DELETED

6. Wide Range Neutron Flux W N/A F

TABLE 4.1-4 (Continued)

POST ACCIDENT MONITORING INSTRUMENTATION

> FUNCTION INSTRUMENTS CHECK TEST CALIBRATE REMARKS 3

7. Reactor Coolant System Cold Leg W N/A R 3 Water Temperature CD

3 (TE-959, 961; TI-959A, 961A) z R o 8. Reactor Coolant System Hot Leg W N/A (TE-958, 960; TI-958A, 960A)

- 9. Reactor Coolant System Pressure W N/A R (PT-949, 963; PI-949A, 963)

10. Steam Generator Pressure W N/A R

• (PT-950, 951, 1180, 1184; NJ PI-950A, 951A, 1180,1184)

11. Condensate Storage Tank Water W N/A F Level (LT-1060, 1061, 1062, 1063; LI-1060, 1061, 1062, 1063)

(Page 4-38 deleted)

(Page 4-38a deleted)

Amendment No. 8-7, 1-58, 1-75, 4-98, 2725, 240

Bases Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter. Pressure drop should be determined at least once every refueling interval to show system performance capability.

The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with Halogenated hydrocarbon refrigerant shall be performed in accordance with approved test procedures. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. If test results are unacceptable all adsorbent in the system should be replaced with an adsorbent qualified according to ASTM D3803-1989. Tests of the HEPA filters with DOP aerosol shall also be performed in accordance with approved test procedures. Any HEPA filters found defective should be replaced with filters qualified according to Regulatory Guide 1.52, March 1978.

Fans AH-E7A & B performance verification is necessary to ensure adequate flow to perform the filter surveillance of T.S. 4.12.2.1 and 4.12.2.3 and can only be demonstrated by running both fans simultaneously. This can only be accomplished when purge valves are note limited to 300 open (i.e., cold shutdown).

The reactor building purge exhaust system no longer is relied upon to serve an operating accident mitigating (i.e. LOCA) function. The retest requirement of T.S. 4.12.2.2a has therefore been changed to reflect the same retest requirements as the auxiliary and fuel handling building ventilation system which similarly serves no operating accident mitigating function.

If significant painting, steam, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use. The determination of significant shall be made by the Vice President-TMI Unit 1.

References (1) UFSAR, Section 5.6 - "Ventilation and Purge Systems" 4-55c Amendment No. 55, 4-08, 4-,57, 4-7-, 24-8, 2-26 240