ML20095F589
| ML20095F589 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/12/1995 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20095F581 | List: |
| References | |
| NUDOCS 9512190116 | |
| Download: ML20095F589 (13) | |
Text
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I LAR 95-0017 Page 9 l
1 INDEI LIMITING CONDITIONS FOR OPERATION AND SURVII11ANCE REQUIREMEN13 I
PACI SECTION i
2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 FRIMARY CONTAINMElff I
containment Integrity...............
3/4 6-1 t
Containment Leakage................
3/4 6b2 3
Containment Air Locks...............
3/4 6-4 4
i Internal Pressure.................
3/4 6-7 i
3/4 6-4 Air Temperature..................
$ ten $ ; 'W- ' " - tural Intgity-......
3/4'6-9 a
3/4 6-10 Containment Ventilation System 3/4.6.2 DEPRESSURIZATION AND COOLING ST5TEMS 3/4'6-11 Containment Spray System 3/4 6 13 Containment Cooling Systes 3/4 6-14 3/4.6.3 CONTAINMElff ISOLATION VALVES 3/4.6.4 COMBUSTIB12 GAS CONTROL 3/4 6-23 Hydrogen Analyzers Deleted......................
3/4 6-24 Containment Hydrogen Dilution Systes 3/4 6-13 Hydrogen Purge Systes...............
3/4 6-26 l
3/4.6.5 SEIELD BUILDING 3/4 6-28 Emergency Ventilation System 3/4 6-31 gegdgldingIntegrity.............
-Shield-Suilding4tructural-Integrity........
3/4 6-32 l
4 i
DAVIS-BESSE. UNIT 1 VI Amendment No. AS. #,
i 9512190116 951212 PDR ADOCK 05000346 PDR p
LAR 95-0017 Page 10 DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
)
1.
Capable of being closed by the Safety Features Actuation System, or 2.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except those approved to be open under administrative controls, j
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3,
)
d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
QlANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CilECK 1.10 A CIWINEL CilECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
DAVIS-BESSE, UNIT 1 1-2 Amendment No. 93,135,147,194
l LAR 95-0017' Page 11 3/4.6-CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINHENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore 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 />.
C c. 6 y pa,s.,d m e s 4 4 vdv I wwin-sm C +L An'n~+ vme I a n L A sLIJ soJ.) iny
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y SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that:
1.
All penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in 1
their positions, except those valves that may be opened under t
administrative controls per Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealed.
b.
By verifying that each containment air lock is in compliance with
(
the requirements of Specification 3.6.1.3
- Except valves, blind flanges, and deactivated automatic valves which are located inside the Shield Building (including the annulus and j
containment) and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days.
DAVIS-BESSE, UNIT 1 3/4 6-1 Amendment No. /lAl i
LAR'95-0017 Page 12 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMiTINGCONDITIONFOROPERATION 3.6.1.2 containment leakage rates shall be limited to:
1 0.50 percent by weight An overall integrated leakage rate of s L,38 psig.
i a.
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,
1 b.
A combined leakage rate of s 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,.
A combined leakage rate of s 0.03 L, for all penetrations that are c.
secondary containment bypass leakage paths, when pressurized to P,.
l A single penetration leakage rate of s 0.15 Lpurge and exhaust d.
j APPLICABILITY: MODES 1, 2, 3 and 4.
a S I e-H~
ACTION:
a.
With eith : a) the m red overall integrated containment leakage rate excee ng 0.75 L
) with the measured combined leakage rate for all penetrations valves subject to Type B and C tests exceeding 0.60 L,, or (c) with the combined bypass leakage rate exceeding 0.03 L, restore the leakage rate ( ) to within the limit (s) prior to increasing the Reactor Coo ant System temperature i
above 200*F.
b.
With a single containment purge and exhaust isolation valve penetration having leakage rate exceeding 0.15 L ; restore the leakage rate to within limits in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be In at least HOT STANDBi O thin.'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 />.
SURVEILLANCE REQUIREMENTS
- 1 Jollows :
4.6.1.2 The containment leakage rates shall be desnonstrated et-the follcwing--
3 test schedde cad shah-be-determined-4n conformence with the criteH+
specified-in-Appendix J cf 10 Ofn 50 using the-methods and previsiens of ANS!
-N45.4 1072;
)
Pe rL~
3 ype A tests {0veran-Integr+ted-Genta 4nmentr-beakege Rctc) :bli k T
a.
eenduc4e4 in accordance with the recuirement: :pecified in=
Appendix J cf 10 CFR 50, c: modif4c: by cpproved exempt 4ensr-t o L FA S o, Appeh x *r* Op% 6, a m ed M%.J by qpeweel
,\\
e-w.yk > m L 2-<y Is b
(>v', L - I. l C 3.
y V
DAVIS-BESSE - UNIT 1 3/4 6-2 Amendment No.-90rf46rt
LAR 95-0017 Page 13 CONTAINMENT SYSlf31 i
SURVEILLANCE REQUIREMENTS (Continued) l b./If any periodic Type A test fails to meet 0.75 L, the u
for subsequent Type A tests 1 be re pproved by the Delefe commission.
if two conseco pe tests fail to meet 0.7s t, a I
Type A test sha ormed at least every 18 months until tw,o
)
i epm :stiva ype A tests meet 0.75 L,.
j "The accuracy of each Type A test shall be verified by a suppleme c.
test which:
l
'1.
Confirms the accuracy of the Type A test b fying that the I
difference between supplemental and test data is within I
i i
l 0.25 L,.
l l
2.
Has a duration suffic to establish accurately the change in l
l 1eakage between ype A test and the supplemental test.
I j
3.
Requir at the rate at which gas is injected into the
)h ainment or bled from the containment during the l
_ supplemental test is between 0.75 L, and 1.25 L..
d i
ful.+
d.
, Type B and C tests ch:11 be conducted "ith ga:
t ",, 30 psig, at intervals ne greatcr th;n 24 :: nth: x:cpt for test., involving air
.;ccgg, _,k a u e e d.us w, % to ces-so, App eak T op +,4r A,
1 n a.sk.a sy -pf we d < wp+,ans -
e.
The combined bypass leakage rate shall be determined to be < 0.03 L, by applicable Type B and C tests at least once every 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,, 38 psig, during each Type A test, i
i f.
Air locks shall be in compliance with the requirements of Specification 3/4.6.1.3.
DAVIS-BESSE - UNIT 1 3/4 6-3 Ame nt No.40,120.160,1%,
'Page 14 CONTAINMETIT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
I l
g.
Each time the containment purge and exhaust isolation valves are l
opened, a special test shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve closure or prior to entering MODE 4 from MODE 5..whichever is later. The special test is conducted by pressurizing the piping section including one valve inside and one valve outside the containment to a pressure greater or equal to 20 psig. The leakage rate per penetration shall not exceed 0.15 t.a*
The special test as defined in Surveillance Requirement 4.6.1,lves
.29 h.
shall be perfonned for the containment purge and isolation va when the plant has been in any combination of MODES 3, 4, 5 or 6 for..more than 72. hours provided that the : test required'.by Surveil-lance Requirement 4.6.1.2 9 has not been performed in the previous 6 months.
L Delc h.L 1.
ATT4.esJ_ leakage rates shall be calculated using observed data "
l converted to absolute vduer Error a shall be performed to select a balanced integrated leakage measuremen J
m j.
The provisions of Specification 4.0.2 are not applicable.
i l
9 DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90,
LAR 95-0017' Page 15 ONTAINMENT SYSTEMS CkNTAINMENT VESSEL STRUCTUPAL INTEGRITY i
L.!M G CON 0!TIONS FOR O'PERATION 3.6.1.6 Th structural integrity of the containment ves shall be i
naintained a a level consistent with the acceptance er eria in specification 6.1.6.
APPLICABILITY: M ES 1, 2, 3 and 4.
ACTION:
dith the structural inte (ity of the containm t vessel not confonning to the above requirements, re tore the structur 1 integrity to within the limits prior to increasing e Reactor Coo nt System temperature above 200*F.
SURVEILLANCE REQUIREMENTS, 4.6.1.6 The structura integrity of the contai ent vessel shall be determined during thi shutdown for each Type A co ainment leakage rate i
test (referenceSpe fication 4.6.1.2) by a visual nspection of the l
accessible interio and exterior surfaces of the ves el and verifying I
no apparent chan s in appearance of the surfaces or ther abnormal degradation. A abnormal degradation of the contai t vessel detected during the abo e required inspections shall be reported o the Co: mission.
VIS-BESSE. UNIT 1 3/4 6-9 Amendment No. 9
. Dv$"
IJ.R 95-0017 Page 16 Page 3/4 6-9 is Deleted.
Next Page is 3/4 6-10, DAVIS-BESSE, UNIT 1 3/4 6-9 Amendment No. gg,
.Page 17 CCNTAINMENT SYSTEMS i
i i
SHIELD 9UILDING STRUCTURAL !NTEGRITY 1
i L! TING CON 0! TION FOR OPERATION 3.6.5.3 The structural integrity of the shield building shal be maintain at a level consistent with the acceptance criter in 1
]
Specificati 4.6.5.3.
APPI.!CABILITY: MODES 1, 2, 3 and 4.
i ACTION:
With the structural ntegrity of the shield bull ng not conforming to the original acceptan standards, restore the tructural integrity to within the limits prio to increasing the Rea r Coolant System j
temperature above 200*F.
4 i
)
1 j
SURVEIL. LANCE REQUIREMENTS i
4.6.5.3 The structural tagrity of shield building shall be deter-j mined during the shutd for each Type containment leakage rate test i
(referenceSpecifica on 4.6.1.2) by a vis 1 inspection of the accessible l
interior and exteri surfaces of the shiel building and verifying no apparent changes 1 appearance of the concre surfaces or other abnormal degradation. An abnormal degradation of the hield building detected j
during the required inspections shall be rted to the Commission.
i i
2 Men ent No. 93 l
DAVIS-8 ESSE. UNIT 1 3/4 6-32 J
1 q
w h G9 @
i
~
LAR 95-0017 Page 18 Page 3/4 6-32 is Deleted.
Next Page is 3/4 6-33, DAVIS-BESSE, UNIT 1 3/4 6-32 Amendment No. //,
Page 19 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY; CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINHENT 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 restriction, in conjunction with the leakage rate limitation and air lock door requirements, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
o.s - / ek 3 /4.6.1. 2 CONTAINMENT LEAXAGE 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 of 38 pdgrP. As an added conservatism, the measured overaligntegrated leakag,e rate is further limited l
to s 0.75 L during performance of the periodic tests to account for possible degradation, f the containment leakage barriers between leakage tests.
o urwaillance testing for measuring leakage rates are consistent the requirement 7s o0-GFR32rt 50. AppendiG with the following exemation.
) The third test of each Type A testing set need^not be-condu hen tie plant j Lis shut down for the 10-year plant inservice inspections.
j The special test for the containment purge and exhaust isolation valves is intended to detect gross degradation of seals on the valve seats. The special test is performed in addition to the Appendix J requirements.
USAR 6.2.4 identifies all penetrations that are secondary containment bypass leakage paths.
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 CONTAINHENT 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 j
during the intervals between air lock leakage tests.
DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendme No. 90446A60, 1
-49
- - -.. -. - ~.. - - - -.. - - - - - -..
IIR 95-0017
-i Page 20 i
CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE 1
i The limitations on containment internal pressure ensure that 1) the l
l containment structure is prevented from exceeding its design negative i
pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.
I The maximum peak pressure obtained from a LOCA event is 37 psig.
j The limit of 1 psig for initial positive containment pressure will limit the total pressure to 38 psig which is less than the design pressure and j
is consistent with t,he safety analyse.s.
i 3/4.6.1.5 AIR TEMPERATURE 1
The limit'ations on containment average air temperature ensure that l
]
the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a 4
LOCA.
I i
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY Q I This limitation ensures that the structural integrity of anD ment steel vessel will be maintained y parable nal design standards for the life of the facili btructural integrity is required to ensure that the vessel stand the maximum pressure of 38 psig in the ev A visual inspection in conjunction with Type A e tests is sufficient to demonstrate this capability.
]
.1 't 4
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM v
j Q
The limitation on use of the Containment Purge and Exhaust System limits the time this system may be in operation with the reactor coolant system temperature above 200'F. This restriction minimizes the time that a direct open path would exist from the containment atmosphere to the outside atmosphere and consequently reduces the probability that an j
accident dose would exceed 10 CFR 100 guideline values in the event cf a V
LOCA' occurring coincident with purge system operation. The use of this j
system is therefore restricted to non-routine usage not to exceed 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in any consecutive 365 day period which is equivalent to approximately j
1% of the total possible yearly unit operating time.
3/4.6.2 DEPRESSURlZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM 4
The OPERABILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the
[
event of a LOCA. The presure reducticn and resultant lower containment I
j DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No.
' LAR 95-0017 Page 21 i
CONTAINMENT SYSTEMS BASES 3/4.6.5.2 SHIELD BUILDING INTEGRITY j
SHIELDING BUILDING INTEGRITY ensures that the release of radioactive material from the containment vessel vill be restricted to those leakage paths and associated leak rates assumed in the safety analysis. The closure of the airtight doorr and blovout panels listed in Tt;1e 4.6-1 ensure that the Emergency le.ilation System (EVS) can provide a negative pressure between 0.25 and 1.5 ine'es Vater Gauge within the annulus between the shield building and i
containmen. vessel and within the interconnecting mechanical penetration rooms after a 1<as-of-coolant accident (LOCA). This restriction, in conjunction with l
the opert:fon of the EVS, vill limit the site boundary radiation doses to within the limi s of 10 CFR 100 during accident conditions.
3/4.6.5 ', SHIELD BUILDING STRUCTURAL INTEGRITY eld
<-This li11tation ensures that the structural integrity of the containmen
-+*
s for the h i buildi g vill be maintained comparable to the original design s j
life c' the facility.
tural inte qu provide 1) protection f
es, 2) radiation shielding in the vent J l f
for tho steel vessel e
nnulus surrounding the steel vessel that can be maintained 4 of a L CA, and a
u,,at,g,n e pressure during accident conditions.
_)
b O
4 1
1 i
AnendmentNo.jfd!
DAVIS-BESSE, UNIT 1 s 3/4 6-5 j
.