ML20100P052

Proposed Tech Specs Re Rev to 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment

ML20100P052
Person / Time
Site:	Catawba
Issue date:	03/04/1996
From:	DUKE POWER CO.
To:
Shared Package
ML20100P039	List: ML20100P038 ML20100P052
References
NUDOCS 9603110022
Download: ML20100P052 (14)

Text

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I' CONTAINMENT SYSTEMS i

CONTAINMENT VESSEL STRUCTURAL INTEGRITY l LIMITING CONDITION FOR OPEnnTION l

3.6.1.6 The structural integrity of the containment vessel shall be '

maintained at a level consistent with the acceptance criteria in Specification l 4.6.1.6.

1 APPLICABILITY: MODES 1, 2, 3, and 4. I 1

ACTION:

With the structural .ntegrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F. I SURVE[igCEREQUIREMENTS 4.6.1.6 The structural integrity of the containment vess:1 shall be l determined by a visual inspection of the exposed accessible interior and l exterior the Typesurfaces of the leakage A containment vessel. This insp(ection rate test shall reference be performed Specification priortoto 4.6.1.2)  ;

verify no apparent changes in appearance of the surfaces or other abnormal I degradation. If the Type A test is performed at 10-year intervals, two '

additional inspections shall be performed at approximately equal intervals ,

during shutdowns between Type A tests. Any abnormal degradation of the  !

containment vessel detected during the above required inspections shall be  !

reported to the Commission within 15 days as a Special Report pursuant to l Specification 6.9.2. '

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l 9603110022 960304 l PDR ADOCK0500g3 P

CATAWBA - UNIT 1 3/4 6-12 Amendment No, i

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l CONTAINMENT SYSTEMS l 1

REACTOR BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION l

3.6.1.7 The structural integrity of the reactor building shall be maintained l at a level consistent with the acceptance criteria in Specification 4.6.1.7. ,

l APPLICABILITY: MODES 1, 2, 3, and 4. '

ACTION:

With the structural inte5rity of the reactor building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4.6.1.7 The structural integrity of the reactor building shall be determined .

during the shutdown for each Type A containment !eakage rate test (reference i Specification 4.6.1.2) by a visual inspection of the exposed accessible l interior and exterior surfaces of the reactor building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation. If the Type A test is performed at 10-year intervals, two additional inspections shall be performed at approximately equal intervals during shutdowns between Type A tests. Any abnormal degradation of the  ;

reactor building detected during the above required inspections shall be i reported to the Commission within 15 days as a Special Report pursuant to Specification 6.9.2.

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CATAWBA - UNIT 1 3/4 6-13 Amendment No.

CONTAINMENT SYSTEMS

. BASES INTERNAL' PRESSURE (Continued)

The maximum peak pressure expected to be obtained from a LOCA event is

'14.68 psig. The limit of 0.3 psig for initial positive containment pressure j is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that: (1) the containment air mass is limited to an initial mass sufficiently low to prevent exceeding the design pressure during LOCA conditions, and (2) the ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and. instrumentation located within containment. Measurements shall be made.at all operating ventilation unit locations, whether by fixed or-portable instruments, prior to determining the average air temperature.

The containment pressure transient is sensitive to the initially contained air mass during a LOCA. The contained air mass increases with decreasing temperature. The lower temperature limit of 100'F for the lower compartment and 75'F (60*F when in MODE 2, 3 or 4) for the upper compartment will limit the peak pressure to 14.7 psig which is less than the containment design pressure of 15 psig. The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based pri-marily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the safety analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCIURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 15 psig in the event of a LOCA. A periodic visual inspection is sufficient to demonstrate this capability.

3/4.6.1.7 REACTOR BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment reactor. building will be maintained comparable to the original design stan-dards for the life of the facility. Structural integrity is required to pro-vide: (1) protection for the steel vessel from external missiles, (2) radia-tion shielding in the event of a LOCA, and (3) an annulus surrounding the steel vessel that can be maintained at a negative pressure during accident conditions. A visual inspection is sufficient to demonstrate this capability.

CATAWBA - UNIT 1 B 3/4 6-2

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CONTAINMENT SYSTEMS l CONTAINMENT VESSEL STRUCTURAL INTEG9ITY LIMITING CONDITION FOR OPERATION 4 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test (reference Spe:ification 4.6.1.2) to verity no apparent changes in appearance of the surfaces or other abnormal degradation. If the Type A test is performed at 10-year intervals, two additional inspections shall be performed at approximately equal intervals during shutdowns between Type A tests. Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission within 15 days as a Special Report pursuant to Specification 6.9.2.

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l CATAWBA - UNIT 2 3/4 6-12 Amendment No. I l

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l CONTAINMENT SYSTEMS  !

BEACTOR BUILDING STRUCTURAL INTEGRITY l LIMITING CONDITION FOR OPERATION 4

3.6.1.7 The structural integrity of the reactor building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.7.

APPLICABILITY: MODES 1, 2, 3, and 4. i i

ACTION:

With the structural integrity of the reactor building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.7 The structural integrity of the reactor building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the reactor building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal dr yad tion. If the Type A test is performed at 10-year intervals, two addit %al inspections shall be performed at approximately equal intervals during shutdowns between Type A tests. Any abnormal degradation of the reactor building detected during the above required inspections shall be reported to the Commission within 15 days as a Special Report pursuant to Specification 6.9.2.

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CATAWBA - UNIT 2 3/4 6-13 Amendment No.

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CONTAINMENT SYSTEMS BASES INTERNALPRESSURE(Continued)

The maximum peak pressure expected to be obtained from a LOCA event is j 14.68 psig. The limit of 0.3 psig for initial positive containment pressure is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that: (1)  ;

the containment air mass is limited to an initial mass sufficiently low to l prevent exceeding the design pressure during LOCA conditions, and (2) the  !

ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment. Measurements shall be made at all operating ventilation unit locations, whether by fixed or portable instruments, prior to determining the average air temperature.

The containment pressure transient is sensitive to the initially contained air mass during a LOCA. The contained air mass increases with decreasing temperature. The lower temperature limit of 100*F for the lower compartment and 75'F (60*F when in MODE 2, 3 or 4) for the upper compartment will limit the peak pressure to 14.7 psig which is less than the containment design pressure of 15 psig. The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based pri-marily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the safety analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 15 psig in the event of a LOCA. A periodic visual inspection is sufficient to demonstrate this capability.

3/4.6.1.7 REACTOR BUILDING STRUCTURAL INTEGRITY I This limitation ensures that the structural integrity of the containment reactor building will be maintained comparable to the original design stan-dards for the life of the facility. Structural integrity is required to pro-vide: (1) protection for the steel vessel from external missiles, (2) radia-i tion shielding in the event of a LOCA, and (3) an annulus surrounding the steel vessel that can be maintained at a negative pressure during accident conditions. A visual inspection is sufficient to demonstrate this capability.

i CATAWBA - UNIT 2 B 3/4 6-2

i Attachment IB New original pages in combined format TS 4.6.1.6 and 4.6.1.7 l

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CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test (reference Specification 4.6.1.2) to verify no apparent changes in appearance of the surfaces or other abnormal degradation.

If the Type A test is performed at 10-year intervals, two additional inspections shall be performed at approximately equal intervals during shutdowns between Type A tests. .Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission within 15 days as a Special Report pursuant to Specification 6.9.2.

CATAWBA - UNITS 1 & 2 3/4 6-12 Amendment No. Unit 1 Amendment No. Unit 2

CONTAINMENT SYSTEMS REACTOR BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

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, 3.6.1.7 lhe structural integrity of the reactor building shall be maintained l at a level consistent with the acceptance criteria in Specification 4.6.1.7.

1 APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the structural integrity of the reactor building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE RE0VIREMENTS l 1 l 1 l 4.6.1.7 The structural integrity of the reactor building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the reactor building and verifyisg no apparent changes in appearance of the concrete surfaces or other abnormal

, degradation. If the Type A test is performed at 10-year intervals, two l additional inspections shall be performed at approximately equal intervals i

during shutdowns between Type A tests. Any abnormal degradation of the reactor building detected during the above required inspections shall be reported to the Commission within 15 days as a Special Report pursuant to Specification 6.9.2. I i

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i j CATAWBA - UNITS 1 & 2 3/4 5-13 Amendment No. (Unit 1) '

Amendment No. (Unit 2) b -

CONTAINMENT-SYSTEMS BASES INTERNAL PRESSURE (Continued)

The maximum peak pressure expected to be obtained from a LOCA event is 14.68 psig. The limit of 0.3'psig for initial positive containment pressure is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that:

(1) the containment air mass is limited to an initial mass sufficientl prevent exceeding the design pressure during LOCA conditions, and the (2) y low to ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment. Measurements shall be made at all operating ventilation unit locations, whether by fixed or portable instruments, prior to determining the average air temperature.

The containment pressure transient is sensitive to the initially contained air mass during a LOCA. The contained air mass increases with decreasing temperature. The lower temperature limit of 100*F for the lower compartment and 75'F (60*F when in MODE 2, 3 or 4) for the upper compartment will limit the peak pressure to 14.7 psig which is less than the containment design pressure of 15 psig. The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based primarily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the safety analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures-that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum - .;ure of 15 psig in the event of a LOCA.

A' periodic visual inspection is sul.icient to demonstrate this capability.

3/4.6.1.7 REACTOR BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment reactor building will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to provide:

(1) protection for the steel vessel from external missiles, (2) radiation shielding in the event of a LOCA, and (3) an annulus surrounding the steel vessel that can be maintained at a negative pressure during accident conditions. A visual inspection is sufficient to demonstrate this capability.

CATAWBA - UNITS 1 & 2 B 3/4 6-2

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Attachment IC New original pages in combined format l TS 4.6.1.2 )

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of less than or equal to L,, 0.30%

by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,14.68 psig.

b. A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,, and

c. A combined bypass leakage rate of less than 0.07 L, for all pene-trations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P,.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With: (a) the measured overall integrated containment leakage rate exceeding 0.75 L,, or (b) the measured combined leakage rate for all penetrations and or (c) the combined bypass leakage rate to less than 0.75 L, andrate exceeding 0.07 L bined leakage the com

, restore the overa and valves subject to Type B and C tests to less than 0.60 L , and the combined bypass leakage rate to less than 0.07 L, prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated in accordance with 10 CFR 50.54(o) at a test schedule determined in conformance with Appendix J of 10 CFR Part 50, Option B, using the methods and provisions of Regulatory Guide 1.163, September,1995.

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CATAWBA - UNITS 1 & 2 3/4 6-2 Amendment No. Unit 1 Amendment No. Unit 2 l

CDNTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) ,

a.' Deleted

b. Deleted  !

c. The accuracy of each Type- A test shall be verified by a supplemental test in accordance with Regulatory Guide 1.163, September,1995.

d. Type B and C tests.shall be conducted with gas at a pressure not less than P ,14.68 psig, at intervals no greater than 24 months except forte $tsinvolving:

1) Air locks,

2) Purge supply and exhaust isolation valves with resilient material seals, and

3) Dual-ply bellows assemblies on containment penetrations between i the containment building and the annulus. l l

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1 CATAWBA - UNITS 1 & 2 3/4 6-3 Amendment No. (Unit 1 Amendment No. (Unit 2 ,

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j 3/4.6 CONTAINMENT SYSTEMS BASES ,

l 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive I 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 .

B0UNDARY radiation roses to within the dose guideline values of 10 CFR l Part 100 during accident conditions. )

1 3/4.6.1.2 CONTAINMENT LEAKAGE 1

The limitations on containment leakage rates ensure that the total  !

containment leakage volume will not exceed the value assumed in the safety l analyses at the peak accident pressure, P . As an added conservatism, the as- l 1 eft overall integrated leakage rate is further limited to less than or equal  !

to 0.75 L to account for possible degradation of the containment leakage  ;

barriersSetweenleakagetests.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50, Option B.

l 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 provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE I

The limitations on containment internal pressure ensure that: (1) the ,

containment structure is prevented from exceeding its design negative pressure '

differential with respect to the outside atmosphere of 1.5 psig, and (2) the l containment peak pressure does not exceed the design pressure of 15 psig I during LOCA conditions.

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l CATAWBA.- UNITS 1 & 2 B 3/4 6-1 Amendment No. Unit 1 Amendment No. Unit 2 l

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