ML20151B060
| ML20151B060 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/11/1988 |
| From: | NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20151B063 | List: |
| References | |
| NUDOCS 8807200222 | |
| Download: ML20151B060 (12) | |
Text
'
o 3/4.6 CONTAINMENT SYSTEMS c
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATI0r4
- 3. 6.1.1 Primary _ CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restcre CONTAINMENT INTEGRITY within one hour 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 />.
$_URVEILLANCE REQUIREMENTS
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment hutomatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
c.
After each closing of each penetration subject to Type B testing, j
except the containment air locks, if opened following a Type A or j
D test, by.eak rate testing the seal with gas at P,, 12 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
i
- Except valves, blind flanges, and deactivated automatic valves which are,
located inside the annulus or containment and-are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed, more often than once per 92 days.
SEQUOYAH - UNIT 1 3/4 6 1 Amendment No. 12 8807200222 830711 PDR ADOCK 05000327 P
"CONTAINMENT-SYSTEMS e
. CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containme.n leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to L '
a O.25 percent 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, 12 a
p s.i g,
b.
A combined leakage rate uf less than or equal to 0.60 L, for all penetrations and valves subject to Type B and C tests, wnen pressurized to P
- a c.
A combined bypass leakage rate of less than or equal to 0.25 L for a
all penetrations identified in Table 3.6-1 as secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to P'
a APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations a
and valves subject to Types B and C tests exceeding 0.60 L,, or (c).with the combined bypass leakage rate exceeding 0.25 L, for BYPASS LEAKAGE PATHS TO THE
^
AUXILIARY BUILDING, restore the overall integrated leakage rate to less than or
~
equal to 0.75 L,, the combined leakage rate for all penetrations and valves subject to Type B and C tests to less tt 1 se equal to 0.60 L,, the combined bypass leakage rate from BYPASS LEAKAGt rATHS TO THE AUXILIARY BUILDING to less than or equal to 0.25 L,, prior to increasing the 3eactor Coolant System temp-4 erature above 200 F.
SEQUOYAH - UNIT 1 3/4 6-2 Amendment No, p 71
o CONTAINMENT SYSTEMS g
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following-test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A tests (Overall Integrated Containment t.eakage Rate).
shall be conducted at 40 + 10 month intervals during shutdown at Pa.
(12 psig) during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year j
plant inservice inspection.
If any periodic Type A test fails to meet 0.75 L,, the test schedule b.
for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L,,
a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L at which time the above test a
schedule may be resumed.
i c.
The accuracy of each Type A test shall be Vtrified by a supplemental test which:
l.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,.
2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at Pa (12 psig).
SEQl>0YAH - UNIT 1 3/4 6-3
s CONTAINMENT SYSTEMS A
SURVEILLANCE REQUIREkENTS (Continued) d.
Type B and C tests shall be conducted with gas at P,-(12 psig) at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and 3.
Valves pressurized with fluid from a~ seal system.
e.
The combined BYPASS LEAKAGE RATE TO THE AUXILIARY BUILDING shall be determined to be less than or equal to 0.25 L, by applicable Type B and C' tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested witn soap bubbles while the containment is pressurized to P, (12 psin) during each Type A test.
f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 Pa (13.2 psig) and the seal systern capacity is adequate to maintain systein pressure (or fluid head for the containment spray system valves at penetrations 48 A and 48 B) for at least 30 days.
h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at P,'(12 psig) at intervals no greater than once per 3 years, i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shill be performed to'-
select a balanced integrated leakage measurement system.
J.
The provisic-of Specification 4.0.2 a're not applicable.
SEQUOYAH - UNIT 1 3/4 6-4
-m
.w TABLE 3.6-1 u, -
E BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING 8
SECONDARY CONTAINMErdi BYPASS LEAKAGE PATHS x-PENETRATION DESCRIPTION RELEASE: LOCATION.
- e-i X-2A' Personnel Lock Auxiliary Area
[
X-28' Personnel Lock Auxiliary Area X-3 Fuel ~ Transfer Tube Auxiliary Area
- t X-15 Letdown Auxiliary Area X-23 Postaccident Sampling, Hot Leg 3
. Auxiliary Area X-25A Pressurizer Gas Sample Auxiliary Area j
X-250 Pressurizer Liquid Sample Auxiliary Area X-268 Control Air Auxiliary Area X-27C ILRT Auxiliary Area X-29 CCS Auxiliary Area X-30 Accumulator Fill Auxiliary Area
{
R X-34 Control Air Auxiliary Area X-35 CCS Auxiliary Area T' X-39A N to Accumulators
. Auxiliary. Area 2
u' X-2%
N to Pressurizer Relief Tank Auxiliary Area 2
X-400 Hydrogen Purge Auxiliary Area X-41 Normal RB Sump
. Auxiliary Area LX-42 Primary Water Auxiliary Area
~
i X-44 RCP Seal Water' Injection Return Auxiliary Area' r
X-45 P,C Drain Tank Auxiliary Area X-46 RC Drain Ta'nk Auxiliary Area l
X-47A Glycol Auxiliary Area X-478
. Glycol
- Auxiliary Area X-50A
- CCS Auxiliary Area j
. CCS Auxiliary Area X-508-g.
X-51 Fire Protection Auxiliary Area CCS to RCP Oil Cooler Auxiliary _ Area-
[.X-52
=
X-56 ERCW Auxiliary Area :
3 g
X-57 ERCW Auxiliary Area X-58
- ERCW Auxiliary' Area
^
, ' X-59 ERCW Auxiliary Area-o ERCW-Auxiliary Area-U
,X ~ Auxiliary Area X-61 ERCW X-62
- ERCW Auxiliary Area
- X-63 ERCW
. Auxiliary Area i.
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TABLE 3.6-1 (Continued)
- m o'"
BYPASS LEAKAGE PATHS 10 lilE AUXILIARY BUILDING 8
SECONDARY CONIAINMENT BYPASS LEAKAGE PATHS I
I
- r PENETRATION DESCRIPTION RELEASE LOCATION w
X-64 A/C Chilled Water (ERCW)
Auxiliary Area X-65 A/C Chilled Water (ERCW)
Auxiliary Area X-66 A/C Chilled Water (ERCW)
Auxiliary Area X-67 A/C' Chilled Water (ERCW)
Auxiliary Area X-68 ERCW Auxiliary Area X-69 ERCW Auxiliary Area X-70 ERCW Auxiliary Area X-71 ERCW Auxiliary Area X-72 ERCW Auxiliary Area X-73 ERCW Auxiliary Area X-74 ERCW Auxiliary Area R
X-75 ERCW Auxiliary ~ Area X-76 Service Air Auxiliary Area m
X-77 Ocmineralized Water Auxiliary Area m
X-78 Fire Protection Auxiliary Area X-81 RC Drain Tank Auxiliary Area X-82 Fuel Pool Auxiliary Area X-83
-Fuel Pool Auxiliary Area
'X-84A' Pressurizer Relief Tank Gas Sample Auxiliary Area X-85A Excess Letdown Heat Exchanger Auxiliary Area X-90 Control Air Auxiliary Area X-91 Postaccident Sampling, Hot leg 1 Auxiliary Area X-93 Accumulator Sample Auxiliary Area X-94ABC Radiation Sample Auxiliary Area X-95ABC Radiation San.ple Auxiliary Area
' y X-96C Hot Leg Sample Auxiliary Area g
X-98 ILRT Auxiliary Area g-X-101 Postaccident Sampling, Containment Auxiliary Area
-g X-103 Postaccident Sampling, Liquid Discharge '
Auxiliary Area c+
to Containment g
X-106 Postaccident Sampling, Air Discharge Auxiliary Area to Containment y
X-108 UHI Auxiliary Area O
J m
m m
ur DEFINITIONS-e SOLIDIFICATION 1.31 SOLIDIFICATIOh shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.32 A SOURCE CHECK shall be the. qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
STAGGERED TEST BASIS 1.33 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains or other designated components obtained by' dividing the specified test interval into n equal subintervals, b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER 1.34 THERMAL POWER shall be the total reactor core heat transfer Ytte to the reactor coolant.
UNIDENTIFIE0_ LE AKAGE i
1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED' AREA 1.36 An UNRESTRICTED AREA shall be any area, at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commer-cial, institutional, and/or recreational purposes.
SEQUOYAH - UNIT 2 7.- 7 Amendment No.63
~
DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM 1.37 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing todines or partic-ulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.38 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
L 4
L 1
4 l
l SEQUOYAH - UNIT 2 1-8 Amendment No. 63 i
i
m C01.TAINMENT SYSTEMS
)
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using-the methods and provisions of ANSI N45.4-1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 1 10-month intervals during shutdown at P,, 12 psig, during each 10 year service period.
The third test of each set shall be conducted during the shutdown Tor the 10 year plant inservice inspection.
b.
If any periodic Type A test fails to meet 0.75 L, the test schedule for suosequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.0.75 L, a a
Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed.
The accuracy of eaca Type A test shall be verified M a supplemental c.
test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,,
2.
Has a duration suf ficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P, 12 psig.
3 Type B and C tests shall be conducted with gas at P,,
12 psig, at d.
intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and SEQUOYAH - UNIT 2 3/4 6-3
CONTAINMENT SYSTEMS i
SURVEILLANCE REQUIREMENT 5 (Continued) 3.
Valves pressurized with fluid from a seal system, e.
The combined bypass leakage rate to the auxiliary building shall be
~
determined to be less than of equal to 0.25 L,-by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with-soap bubbles while the containment is pressurized to P,, 12 psig, during each Type A test.
f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1 3.
g.
Leakage from isolation valves that are-sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P ' 13'2 a
psig, and the seal system capacity is. adequate to maintain system pressure (or fluid head for the containment spray system valves at penetrations 48A and 488) for at least 30 days.
h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at P,,12 psig, at intervals no greater than once per 3 years, i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
3 The provisions of Specification 4.0.2 are not applicable.
l SEQUOYAH - UNIT 2 3/4 6-4 Amendnent N. 63
TABLE 3.6-1 f
BYPASS LEAKAGE PATHS TO IllE AUXILIARY BUILDING g
SECONDARY CONTAINMEN1 BYPASS LEAKAGE PAlll5 Y
x PENETRATION DESCRIPTION RELEASE LOCATION s
~
X-2A l'ersonnel Lock Auxiliary Area X-2B Personnel Lock Auxiliary Area X-3 Fuel Transfer Tube Auxiliary Area X-15 Letdown Auxiliary Area X-23 Postaccident Sampling,110t Leg 3 Auxiliary Area X-25A Pressurizer Gas Sample Auxiliary Area X-25D Pressurizer Liquid Sample Auxiliary Area X-26B Control Air Auxiliary Area X-27C ILRT Auxiliary Area X-29 CCS Auxiliary Area X-30 Accumulator fill Auxiliary Area w
X-34 Control Air
-Auxiliary Area 1
X-35 CCS Auxiliary Area 7
X-39A N to Accumulators Auxiliary Area 2
ei X-39B N to Pressurizer Relief Tank Auxiliary Area 2
X-400 Hydrogen Purge Auxiliary Area X-41 Normal RB Sump Auxiliary Area
.X-42 Primary Water Auxiliary Area X-44 RCP Seal Water Injection Return Auxiliary Area X-45 RC Drain Tank Auxiliary Area X-46 RC Drain Ttmk Auxiliary Area X-47A Glycol Auxiliary Area X-478 Glycol Auxiliary Area X-50A CCS Auxiliary Area X-SOB CCS Auxiliary Area
_w X-51 Fire Proteir. tion Auxiliary Area-if X-52 CCS to RCP Oil Cooler Auxiliary Area y
X-56 ERCW Auxiliary Area X-57 ERCW Auxiliary Area 5
.E
TABLE 3.6-1 (Continued) mE BYPASS LEAKAGE PATHS 10 IllE AUXILI ARY BUILDING 8
SEC0h3ARY CONTAINMENI BYPASS LEAKAGE PAllis s
1
.PENEIRATION DESCRIPTION RELEASE LOCATION sa X-58 ERCW Auxiliary Area X-59 ERCW Auxiliary Area X-F0 ERCW Auxiliary Area X-61 ERCW Auxiliary Area X-62 ERCW Auxiliary Area X-63 ERCW Auxiliary Area X-64 A/C Chilled Water (ERCW)
Auxiliary Area X-65 A/C Chilled Water (ERCW)
Auxiliary Arei C-66 A/C Chilled Water (ERCW)
Auxiliary Area X-67 A/C Chilled Water (ERCW)
Auxiliary Area X-68 ERCW Auxiliary Area R
X-69 ERCW Auxiliary Area X-70 ERCW Auxiliary Area e
X-71 ERCW Auxiliary Area e
X-72 ERCW Auxiliary Area X-73 ERCW Auxiliary Area X-74 ERCW Auxiliary Area X-75 ERCW Auxiliary Area 7-76 Service Air Auxiliary Area X-77 Demineralized Water Auxiliary Area X-78 Fire Protection Auxiliary Area X-81 RC Drain Tank Auxiliary Area X-82 Fuel Pool Auxiliary Area X-83 Fuel Pool Auxiliary Area X-84A Pressurizer Relief Tank Gas Sample Auxiliary Area y
X-85A Excess Letdown Heat Exchanger Auxiliary Area g
X-90 Control Air Auxiliary Area g
X-91 Postaccident Sampling, Hot Leg 1 Auxiliary Area
$e
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e P
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