ML20149M851

Proposed Tech Specs,Deleting Chlorine Detection Sys & Control Room Emergency Ventilation Sys

ML20149M851
Person / Time
Site:	Davis Besse
Issue date:	02/17/1988
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20149M846	List: ML20149M845 ML20149M848 ML20149M851
References
NUDOCS 8802290149
Download: ML20149M851 (3)

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. FORINFORMl0V DNLY PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one control room emergency ventilation system inoperable, restore ,

the inoperable system to OPERABLE status within 7 days or be in at least l 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 i 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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. j SURVEILLANCE REQUIREMENTS 4.7.6.1 Each control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hour1.388889e-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 < 110'F when the control room emergency ventilation system Ts operating.

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 per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone comunicating with the system by:

DAVIS.BCSSE, UNIT I 3/4 7 17 290149 880217 PDR ADOCK 05000346 DCD

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l

1. Verifying that with the system operating at a flow rate of 3300 cfm + 10% and exhausting through the HEPA filters and charcoal ~adsorbers, the total bypass flow of the system is < 1% when the system is tested by admitting DOP at the system intake.

2. Verifying that the system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.S.c and C.5.d of Regula-tory Guide 1.52 Pevision 1, July 1976, and the system flow rate is 3300 cfm 110%.

3. 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 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1 July 1976.* g 1

4. Verifying a system flow rate of 3300 cfm 110% during i system operation when tested in accordance with ANSI I

N 510-1975.

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 verify- )

ing within 31 days after removal that a laboratory analysis of l a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regula- l tory Position C.6.a of Regulatory Guide 1.52, Revision 1 July i 1976,

e. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 4.4 inches water Gauge while operating the system at a flow rate of 3300 cfm i 10%.

2. Verifying that the control room normal ventilation system is isolated by a SFAS test signal, c^^+m' oa^- Ye-ti'stie-Air h :k: Chl r'n C: ::ntr:th: "i;h ::t :i;n:1, and a Station Vent Radiation High test signal.

• The pre- and post-loading sweep medium temperature shall be 80'C for Test 5.b of Table 2, Regulatory Guide 1.52, Revision 1. July 1976.

1 DAVIS-BESSE, UNIT 1 3/4 7-18

.. 11118PAGE PRBMS

. _ BASES FORINFORMAIl0HWLV the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handwheels for all manual valves and the presence of either handvbeels or available power supply for actor operated valves.

3/4.7.2 STEAM CINERATOR PRES $tHtI/TD(PERATURE LIMITATI0W The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allevable fracture toughnese stress limits. The limitations of Il0'F and 237 peig are based on a steam generator RT of 40'P and are sufficient to prevent brittle fracture. #

3/4.7.3 COMPONENT COOLING VATER SYSTD(

The OPERABILITY of the component cooling water systen 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 analyses.

3/4.7.4 SERVICE VATER SYSTD4 The OPERABILITT of the service water systen 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 systes, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that auf ficieqt cooling capacity is available to either 1) provide normal cooldown of the f acility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are j based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistant with the recommendations of Regulatory Guide 1.27. "Ultimate Heat Sink for Nuclear Plants" March 1974 3/4.7.6 CONTROL ROOM DERGENCY VENT!!.ATION SYSTD( I The OPERABILITY of the control room emergency ventilation systen I ensures that 1) the ambient air temperature does not exceed the ,

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allevable temperature for continuous duty rating for the equipment and j instrumentation cooled by this system and 2) the control roce vill i reasin habitable for operations personnel during and following all credible accident conditions. The OPERASILITY of this systes in )

I conjunction with control room design provisions is based on limiting i the radiation exposure to personnel occupying the control room to 5 ren or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion if Appendix "A".

10 CTR 50.

DAVIS-SESS' WT 1 1 83/474 Amendment No.103 i

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