ML20217N447

Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431

ML20217N447
Person / Time
Site:	Davis Besse
Issue date:	02/27/1998
From:	CENTERIOR ENERGY
To:
Shared Package
ML20217N445	List: ML20217N439 ML20217N447
References
RTR-NUREG-1431 NUDOCS 9803090025
Download: ML20217N447 (5)

Text

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1 AR.97-0005 Revision 1 Page 8 '

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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION i

3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

L With one control room emergency ventilation system inoperable, restore the inoperable system 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 />.

b. With one channel of Station Vent Normal Rance Radiation Monitorine instrumeTitation inonerable. restore the inonerable channel to OPERABLE status. or isolate the control room normal ventilation system and olace at least one control room emergency ventilation system train in ooeration within 7 days.

c. With both channels of Station Vent Normal Ranee Radiation Monitorinc instrumentation inonerable. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. isolate the control room normal ventilation system and olace at least one control room emergency ventilation system train in ooeration.

' SURVFII I ANCE REOUIREMENTS i 4.7.6.1 Each control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 110 F when the control room emergency ventilation system is operating. I

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b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

c. At least once each REFUELING INTERVAL or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or i chemical release in any ventilation zone communicating with the system by: l DAVIS-BESSE, UNIT 1 3/4 7-17 Amendment No. 135,155.217, l l 9903090025 980227 PDR ADOCK 05000346 ,

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. LAR 97-0005 Revision 1 Page 9 - , ,

PLANT SYSTEMS SURVEH LANCE REOUIREMENTS (Continued) j i

1. )

Verifying that the cleanup system satisfies the in-place penetration and bypass <

leakage testing acceptance criteria ofless than 1% and uses the test procedure guidance in Regulatory Positions C,5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3300 cfm 10%;

2. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory _

testing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide peaetration ofless than 1%; and

3. Verifying a system flow rate of 3300 cfm i10% during system operation when

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tested in accordance with ANSI N510-1980.

d. 'After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of

, Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%.

c. At least once each REFUELING INTERVAL by:

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1. Verifying that the pressure drop across the combined HEPA filters and charcoal .!

adsorber banks is less than 4.4 inches Water Gauge while operating the system at  !

a flow rate of 3300 cfm *10%;

2. Verifying that the control room normal ventilation system is isolated by a SFAS test signal and a Station Vent Normal Rance Radiation Monitorine Radiatien High-test signal; and i

The test is performed in accordance with ASTM D 3803-1979 with the following conditions: 1) equilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 30 Cn0% relative humidity (RH),2) challenge for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30 Cn0% RH,3) clution for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30 Cn0% RH. i i

DAVIS-BESSE, UNIT 1 3/4 7-18 Amendment No. 134,135,155, 209,217, ,

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LdR 97-0005 Revision 1 PtANT SYSTEMS Tills PAGE PROV10ED SURVEILLANCE REQUIREMENTS (Continued)

FORINFORIRTION OM

3. Verifying that the makeur flow of the system is 300 cfm i 10% l when supplying the control room with outside air,

f. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a D0P test aerosol while operating the system at a flow rate of 3300 cfm i 10%.

g. After each complete er partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a halogenated hydro-carbon refrigerant test gas while operating the system at -a flow rate of 3300 cfm i 10%.

DAVIS-BESSE, UNIT 1 3/4 7-19 Amendment No.155

LAR 97-0005 Revision 1 THIS PAGE PROVIDED

_ BASES FORINFORMAT10N OfM

'the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handvheels for all manual valves and the presence of either handvheels or available power supply for motor operated valves.

3/4.7.2 STEAN CENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator press < re and temperature ensures that the pressure induced stresses in the st am generators do not exceed the maximum allowable fracture toughness stresa limits,. The limitations of 110*F and 237 psig are based on a steam gererator RT of 40'F and are sufficient to prevent brittle fracture, NDT 3/4.7.3 COMPONENT COOLING VATER SYSTEM The OPERABILITI of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related-equipment during normal and accident conditions. The '

redundan' t cooling capacity of this 'system, assuming a single failure, is consis' tent with the assumptions used in the safety analyses.

3/4.7.4 SERVICE VATER SYSTEM The OPERABILITI of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal'and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with ,

the assumptions used in the safety analysgs. l 3/4.7.5 ULTIMATE HEAT SINK I

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The limitations on the ultimate heat si+ ievel and temperature  !

ensure that sufficient cooling capacity L available to either 1) provide normai cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

• The limitations on minimum vater level and maximum temperature are based on providing a 30 day cooling vater supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants" March 1974.

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM I The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allovable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the untrol room will remain habitable for operations personnel during aad following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personn'e l occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",

10 CFR 50.

DAVIS-EESSE. UNIT I B 3/4 7-4 Amendment No.103

1 LAR 97-0005 Revision i Page 12 , ,

PLANT SYSTEMS BASI 3S The StatjanYent Normal Rance Radiation Monitorine isolation function nrovides that under thefepuimd conditions. an isolation sienal will be niven. The Station Vent Normal Rance '

Radiation Monitors nrovide isolation and shutdown of the control room normal ventilation system.

l Mqtthe nronosed Action statements for inonerable Station Vent Normal Rance Radiatica Monitorine instrumentation. should the control room normal ventilation system he isolated and at least orie train of the control room emercency ventilation system be olaced in oneration. there systems would be in a state eauivalent to that which thev would be in followinc naactual high radiation condition. Plant ooeration can continue indefinitely in this state.

nrovided that control room temperature can be maintained in an accentable rance. with the )

control room emereency ventilation system obtainine fresh-air makeuo as described in the Undated Safety Analysis Reoort Section 9.4.1. " Control Room." '

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,S-BESSE. UNIT 1. B 3/4 7-4a Amendment No.