ML20084C141
| ML20084C141 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/18/1995 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20084C138 | List: |
| References | |
| NUDOCS 9505310436 | |
| Download: ML20084C141 (5) | |
Text
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4 Attachment II Marked-un Technical Specification Page 9505310436 950518 PDR ADOCK 05000413 P
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t No CHANGES THis PAGE.
CONTAINMENT LEAKAGE F0tlNFORMA110N 0NLY:
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LIMITINGCON0!TIONFOROPERATION I
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1 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage r te of:
LessthanorequaltoL,,b.305byweightofthecontainment l
1) 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, or 1
2)
(Unit 1)LessthanorequajtoL,0.122%byweightofthe g
containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P '
t 7.34 psig.
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b.
A combined leakage rate of lessithan 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,,
and l
Alcombinedbypassleakageratedf'lessthand.07L,forall
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senetrations identified in Table 3.6-1 as secondary containment synass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
i With (a) the measured overall integrate containment leakage rate exceeding 0.75 i
L, or 0.75 L, as applicable, or (b) the measured combined leakage rate for all t
penetrations landvalvessubjecttoTypesBandCtestsexceeding0.60L,,or (c) the combined bypass leakage rate exceeding 0.07 L,, restore the overall integrated leakage rate to less than 0.75 !L, or less than 0.75 L, as appitcable, g
and the combined leakage rate for all penetrations and valves subject to Type B andCteststolessthan0.60L,,andthe;combinedbypassleakagerateto less than 0.07 L, prior.to increasing the Reactor Coolant System temperature above 200*F.
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SURVEILLANCE REQUIREMENTS l
Thelicontainment leakage rates shall be demonstrated at the following 4.6.1.2 test scheJule and shall be determined in conformance with the criteria speci-fledinI,ppepdixJof10CFRPart50usingthemethodsand-provisionsofANSI N45.4-1972 os the mass plot method:
CATAWBA - UNITS 1 & 2 3/4 6-2 Amendment No. 41 Unit 1)
Amendment No. 34 Unit 2) l
' CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)
)
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 i 10 month intervals during shutdown at either P,14.68 psig, or (Unit 1) at P*' 7.34 psig, during each 10-year service period.* The third test of each set shall be con-l ducted during the shutdown for the 10-year plant inservice inspection; b.
If any periodic Type A test fails to meet either 0.75 L or (Unit 1) 0.75 L,, the test schedule for subsequent Type A tests s, hall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L shall be performed at least every, or (Unit 1) 0.75 L,, a Type A test 18 months until two consecutive Type A tests meet either 0.75 L, or (Unit 1) 0.75 L, at which time the above test schedule may be resumed; The accuracy of each Type A test shall be verified by a supplemental c.
test which:
1)
Confirms the accuracy of the test by verifying that the supple-mental test result, L,is equal to or less than 0.25 L, or minus the sum of the Type A and the superimposed leak, L,
(Unit 1) 0.25 L,;
2)
Has a duration sufficient to establish accurately the change in
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leakage rate between the Type A test and the supplemental test; and 3)
Requires that the rate at which gas is injected into the con-tainment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L, or (Unit 1) 0.75 L, and 1.25 L,.
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 l
for tests involving:
1)
Air locks, 2)
Purge supply and exhaust isolation valves with resilient material seals, and 3)
Dual-ply bellows assemblies on containment penetrations between the containment building and the annulus.
W for Catawba Unit 1, a one-time change is granted to extend this interval b
- etween t te second test (performed 3/91) and the third test to 60 i 10 months.
Also, th test 6will not be performed during the 10-year ISI refueling outage.L This represents an exemption to 10 CFR 50, Appendix J.
(o pA 7pg CATAUBA Up)[T 2, A ORT /pf6 GHAA)6( is GR ro
" Nf (Q//t. 6&EJE&J The..sEcor)b 1EST(PWoVMM &) W
,tyyg, CATAWBA - UNITS 1 & 2 3/4 6-3 Amendmentk.
(Unit 1)
Amendment No.
(Unit 2)
cunsaannent avartna-I
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SURVEILLANCE REQUIREMENTS (Continued) i I
e.
The combined ass leakage rate shall be detemined to be less than 0.07 L*for penetrations which 'are not individually testable; p by app icable Type 8 and C tests at least once per 24 months except tiene not individually testabl.e shall be determined to have no detect-able leakage when tested with' soap b@bles while the containment is pressurizedtoP,,14.68psig,;or(Unit 1)P,7.34psig,duringeach
+
Type A test-g I
i f.
Purge supply and exhaust isolation valves with resilient material t
seals shall be tested and demonstrated OPERA 8LE by the requirements of Specification 4.6.1.9.3 or 4.6.1.9.4, as applicable; g.
Air locks shall be tested and, demonstrated OPERABLE by the requirements of Specification 4.6.1.3; I
h.
The space between each dual ply bellows assembly on containment gianatrations between the contairment building and the annulus shall be vented to the annulus during Type A tests. At least once per 24 months, the space between each dual ply bellows assembly shall be s'ubjected to a low pressure test at 3 to 5 psig to verify no detect-i, a'ble leakage or the dual ply bel. lows assembly shall be subjected to a Teak test with the pressure on the containment side of the dual ply b' llows assembly at P,,.14.68 psig, to verify the leakage to be within e
thelimitsofSpecification4.f.1.2e.;and l
1.
The provisions of Specificatio' 4.0.2 are not applicable.
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FOR INFORMATION ONLY CATAWBA - U11TS 1 & 2 3/4 6-4 Amendment No. a(Unit 1)
Amendment No. 1(Unit 2)
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7/3/86
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Attachment III No Significant Hazards Analysis The following analysis is presented, pursuant to 10 CFR 50.91, to demonstrate that the proposed change will not create a SigniGcant Hazard Consideration.
- 1. The proposed change will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Containment leak rate testing is not an initiator of any accident; the proposed interval extension does not affect reactor operations or accident analysis, and has no perceptible radiological consequences. Therefore, this proposed change will not involve a signincant increase in the probability or consequences of any previously-evaluated accident.
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- 2. The proposed change will not create the possibility of any new accident not previously evaluated.
The proposed change does not affect normal plant operations or configuration, nor does it affect leak rate test methods. The test history at Catawha (no ILRT failures) provides continued assurance of the leak tightness of the containment structure.
- 3. There is no significant reduction in a margin of safety.
It has been documented in draft NUREG-1493 that an increase in the ILRT interval from 1 test every 3 years to I test every 10 years would result in an increase in population exposure risk in the vicinity of 5 representative plants from.02% to.14%. The proposed change included herein, an increase from 40 i 10 months to s 70 months, represents a small fraction of that already very small increase in risk.
Therefore, it may be concluded that no signiGeant reduction in a margin of safety will occur.
Based on the above, no significant hazards consideration is created by the proposed change.