ML17349A879

Proposed TS 5.2.2, Design Pressure & Temp.

ML17349A879
Person / Time
Site:	Turkey Point
Issue date:	05/21/1993
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17349A878	List: ML17349A877 ML17349A879
References
NUDOCS 9306020384
Download: ML17349A879 (16)

Text

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specifications Pages, 5-1 B 3/4 6-1 B 3/4 6-2'9306020384'30521 PDR ADOCK 05000250 ,.P,, PDR

,pp ll 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-1.MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND L U FLU N 5.1.3 Information regarding radioactive gaseous and liquid effluents, which.will allow identification of structures and release points shall be as shown'n Figure 5.1-2.Definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5, 1-1.5.2 CONTAINMENT CONFIGURATION 5.2.1 The con'tainment building is a steel-lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features: a.Nominal inside diameter=116 feet.b.Nominal inside height=170.6 feet.c.Minimum thickness of concrete walls=3.75 feet.d.Minimum thickness of concrete roof=3.25 feet.e.Minimum thickness of concrete floor pad=10.5 feet.f.Nominal thickness of steel liner=0.25 inches.g.Nominal net free volume=1 550 000 cubic feet.DESIGN PRESSURE AND TEMPERATURE des)'5.2.2 The c'nt buildi maximums, n ernal pressure o tainment building is also str vacuum of 2.5 psig.is designed and shall be maintained for a psig and a temperature of 283'F.The con-urally designed to withstand an internal TURKEY POINT-UNITS 3 8 4 5-1 AMENDMENT NOS.137 AND 132 t t k'~A 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure;P.As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test to account for a possible degradation of the containment leakage barriers between leakage tests.The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.3/4.6.l.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door inter-lock may provide the required locking.In addition, the outer air lock door is secured under administrative controls.3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1)the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, d (2)the containment peak pressure does not exceed the desi n ressure of~sig during LOCA co e.a.t cm(a.R Pc v-The maxim m~pea pressure a LOCA event is 49.9 psig assuming an initial co ainment pressure of 0.3 p5sg.An initial positive pressure of as much as si would result in a maximum containment pressure that is less than desig pressure and is consistent with the safety analyses.TURKEY POINT-UNITS 3 8(4 B 3/4 6"1 AMENDMENT NOS.137AND132 V I r>>~ye%Eg't A'0 (..-)(-ro'".>:.,">jg qi.>>s~~a W m~-<<m~w~iP ISO~~g" I~Q3 4~-.>>spado~)A CONTAINMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the design limits for a LOCA are not exceeded, and that the environmental qualifica-

'ion of equipment is not impacted.If temperatures exceed 120 F, but remain below 125'F for up to 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> during a calendar year, no action is required.If the 336-hour limit is approached, an evaluation may be performed to extend the limit if some of the hours have been spent at less than l25'F.Measurements shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY~~~~++~'P~4 This limitation ensures that the ructural integrity of the containment will be maintained comparable to original design standards for the life of the facility.Structural int>ty is required to ensure that the containment will'ithstand the maximum ressure of 49.9 psig in the event of a LOCA.The measurement of containment endon lift"off force, the tensile tests of the tendon wires or strands, the visual examination of tendons, anchor ages and exposed interior and exterior surfaces of the containment, and the Type A leakage test are sufficient to demonstrate this capability.

Some containment tendons are inaccessible at one end due to interferences and safety considerations.

These tendons, if selected for examination, will be exempted from the full surveillance requirements, and will be subjected only to lift-off testing at the accessible end.Due to tendon configuration, lift-off values may differ considerably at the two ends.Therefore, when only one end is accessible, it is considered that up to a 4X tolerance from the predicted lower limit is acceptable.

The required Special Reports from any engineering evaluation of contain-ment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, the results of the engineering evaluation, and the corrective actions taken.3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during a LOCA.When not purging, power to the purge valve actuators will be removed{sealed closed)to pr event inadvertent opening of these values.Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioactive materials will not be released via the Containment Purge System.Leakage integrity tests with a maximum allowable leakage rate for contain-ment purge supply and exhaust supply valves will provide early indication of TURKEY POINT-UNITS 3 8 4 8 3/4 6"2 AMENDMENT NOS.137AHD 132 I~i"~.4/~J ari>~W"A ATTACHMENT 4 CORRECTED TECHNICAL SPECIFICATIONS PAGES 5-1 B 3/4 6-1 B 3/4 6-2 iP' 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-1.MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LI UID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points shall be as shown in Figure 5.1-2~Definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall"be as shown in Figure 5.1-1.5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment building is a steel-lined, reinforced concrete building of cylindri.cal shape, with a dome roof and having the following design features: a~b.Ca d.e.g, Nominal inside diameter 116 feet.Nominal inside height 170.6 feet.Minimum thickness of concrete walls 3.75 feet.Minimum thickness of concrete roof 3.25 feet.Mini.mum thickness of concrete floor pad 10.5 feet.Nominal thickness of steel liner 0.25 inches.Nominal net free volume 1 550 000 cubic feet.DESIGN PRESSURE AND TEMPERATURE 5,2.2 The containment building is designed and shall be maintained for a maximum design internal pressure of 55 psig and a temperature of 283'F.The containment building is also structurally designed to withstand an i.nternal vacuum of 2.5 psig.TURKEY POINT-UNITS 3&4 AMENDMENT NOS.AND

~'I;g1~

3 4.6 CONTAINMENT SYSTEMS BASES~34.6.1 PRYMARY CONTAINMENT 3 4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

3 4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P~.As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to OA75 L~during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.3 4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests~In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door interlock may provide the required locking.In addition, the outer air lock door is secured under administrative controls.3 4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1)the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, and (2)the containment peak pressure does not exceed the design pressure of 55 psig during LOCA conditions.

The maximum analyzed peak pressure calculated for a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig.An initial positive pressure of as much as 3 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses.TURKEY POINT-UNITS 3&4 B 3/4 6-1 AMENDMENT NOS.AND k

CONTAINMENT SYSTEMS BASES 3 4.6.1.5 AIR TEMPERATURE The limitations on containment average aiz temperature ensure that the design limits for a LOCA are not exceeded, and that the environmental qualification of equipment is not impacted.If temperatures exceed 120 F, but remain below 125 F for up to 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> during a calendar year, no action is required.If the 336-hour limit is approached, an evaluation may be performed to extend the limit if some of the hours have been spent at less than 125'F.Measurements shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.

3 4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment ,will be maintained comparable to the original design standards for the life of the facility.Structural integrity is required to ensure that the containment will withstand the maximum analyzed peak pressure of 49.9 psig in the event of a LOCA.The measurement of containment tendon lift-off force, the tensile tests of the tendon wires or strands, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test are sufficient to demonstrate this capability.

Some containment tendons are inaccessible at one end due to interferences and safety considerations.

These tendons, if selected for examination, will be exempted from the full surveillance requirements, and will be subjected only to lift-off testing at the accessible end.Due to tendon configuration, lift-off values may differ considerably at the two ends.Therefore, when only one end is accessible, it is considered that up to a 4%tolerance from the predicted lower limit is acceptable.

The required Special Reports from any engineering evaluation of contain-ment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, the results of the engineering evaluation, and the corrective actions taken.3 4.6.1.7 CONTA1NMENT VENTILATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during a LOCA.When not purging, power to the purge valve actuators will be removed (sealed'losed) to prevent inadvertent opening of these values.Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioactive materials will not be released via the Containment Purge System..Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust supply valves will provide early indication of TURKEY POINT-UNITS 3&4 B 3/4 6-2 AMENDMENT NOS.AND n x, P l J e 1 1t'