ML20138H878
| ML20138H878 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/01/1997 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20138H870 | List: |
| References | |
| NUDOCS 9705070313 | |
| Download: ML20138H878 (49) | |
Text
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Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.
l APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Containment A.1 Restore containment I hour inoperable.
to OPERABLE status.
B.
Required Action and 8.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
AND B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l
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Crystal River Unit 3 3.6-1 Amendment No. 149 9705070313 970501 l
PDR ADOCK 05000302 P
PDR l
I e
Containment 3.6.1 l
SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY l
SR 3.6.1.1 Perform required visual examinations and leakage rate testing except for containment air lock testing, in accordance with the 1
l Containment Leakage Rate Testing Program.
I 1
The maximum allowable leakage rate, L In accordance 0.25% of containment air weight per d, is ay at with the the calculated peak containment pressure, Containment P,.
Leakage Rate l
Testing Program.
SR 3.6.1.2 Verify containment structural integrity In accordance in accordance with the Containment Tendon with the Surveillance Program.
Containment Tendon l
Surveillance Program i
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l Ciystal River Unit 3 3.6-2 Amendment No.
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Containment Air Locks 3.6.2 l
3.6 CONTAINMENT SYSTEMS l
l 3.6.2 Containment Air Locks LC0 3.6.2 Two containment air locks shall be OPERABLE.
i APPLICABILITY:
MODES 1, 2, 3, and 4.
l.
ACTIONS
NOTES------------------------------------
1.
Entry and exit is permissible to perform repairs on the affected air lock components or for emergencies involving personnel safety.
2.
Separate Condition entry is allowed for each air lock.
3.
Enter applicable Conditions and Required Actions of LC0 3.6.1,
" Containment," when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.
CONDITION REQUIRED ACTION COMPLETION TIME i
l I
A.
One or more
NOTES----------
l containment air locks 1.
Required Actions A.1, with one air lock door A.2, and A.3 are not l
inoperable, applicable if both doors in the same air lock are inoperable and Condition C is entered.
2.
Entry and exit is permissible for 7 days under adminstrative controls if both air locks are inoperable.
A.1 Verify the OPERABLE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> door is closed in the affected air lock.
t AND i
l (continued) l l
t l
Crystal River Unit'3 3.6-3 Amendment No.
l
Containment Air Locks 1
3.6.2 l
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.2 Lock the OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> door closed in the affected air lock.
AND A.3 Verify the OPERABLE Once per 31 door is locked closed days in the affected air lock.
B.
One or more
NOTES------------
containment air locks 1.
Required Actions B.1, with containment air B.2, and B.3 are not lock interlock applicable if both doors mechanism inoperable.
in the same air lock are inoperable and Condition C is entered.
2.
Entry and exit of containment is permissible under the adminstrative control of a dedicated individual.
B.1 Verify an OPERABLE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> door is closed in the affected air lock.
AND (continued)
Crystal River Unit 3 3.6-4 Amendment No. 149
Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.2 Lock an OPERABLE door 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> closed in the affected air lock.
AND B.3 Verify an OPERABLE Once per 31 door is locked closed days in the affected air lock.
C.
One or more
NOTE-----------
containment air locks Successful performance of an inoperable for reasons overall leakage rate test of other than Condition A the affected air lock may be or B.
used to satisfy Required Actions C.1 and C.3 when Condition C is entered as a result of a failure of the i
door seal leakage rate test.
C.1 Initiate action to Immediately evaluate overall 1
containment leakage rate.
AND C.2 Verify a door is I hour closed in the affected air lock.
AND C.3 Restore air lock to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
(continued)
Crystal River Unit 3 3.6-5 Amendment No. 149
Containment Air Locks 3.6.2 i
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion lime not met.
AND D.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 1
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l' i-Crystal-River Unit 3 3.6-6 Amendment No. 149
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Containment Air Locks l
3.6.2 l
l SURVEILLANCE FREQUENCY l
l SURVEILLANCE FREQUENCY SR 3.6.2.1
.....--------------NOTES-------------------
l 1.
An inoperable air lock door does not invalidate the previous successful per formance of the overall air lock leakage test.
2.
Results shall be evaluated against acceptance criteria of SR 3.6.1.1 in accordance with the Containment Leakage Rate Testing Program.
l Perform required air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program.
The acceptance criteria for air lock testing are:
In accordance a.
Overall air lock leakage rate is s 0.05 L, when with the tested at 2 P,.
Containment Leakage Rate b.
For each door, leakage rate is s 0.01 L, when Testing tested at > 8.0 psig.
Program.
NOTE-----
Only required to be performed when an air lock is used for entry into containment.
184 days Verify only one door in the air lock can be opened at a time.
E Crystal River Unit 3 3.6-7 Amendment No.
Containment Isolation Valves 3.6.3 I
3.6 CON" MENT SYSTEMS 3.6.3 Ce,tainment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
L ACTIONS i
-NOTES------------------------------------
l 1.
Penetration flow paths except for 48 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.
2.
Separate Condition entry is allowed for each penetration flow path.
3.
Enter applicable Conditions and Required Actions for system (s) made inoperable by containment isolation valves.
I 4.
Enter applicable Conditions and Required Actions of LC0 3.6.I, l
" Containment," when purge valve leakage results in exceeding the overall containment leakage rate acceptance criteria.
CONDITIONS REQUIRED ACTIONS COMPLETION TIME A.
NOTE---------
A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Only applicable to penetration flow path penetration flow paths by use of at least i
with two containment one closed and isolation valves, de-activated automatic valve, closed manual valve, One or more blind flange, or penetration flow paths check valve with flow with'one containment through the valve 1
l isolation valve secured.
inoperable (except for l
48 inch purge valve AND l
leakage not within limit).
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(continued) i s
4 i
Crystal River Unit 3 3.6-8 Amendment No.
Containment Isolation. Valves 3.6.3
' ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME a
A.
(continued)
A.2
NOTE--------
Valves and blind flanges in high radiation areas may j
be verified by use of I
administrative means.
Verify the affected Once per penetration flow path 31 days for is isolated.
isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued) j Crystal River Unit.3 3.6-9 Amendment No. 149
Containment Isolation Valves 3.6.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
NOTE---------
B.1 Isolate the affected I hour Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves or de-activated' I
penetration flow paths automatic valve, with one containment closed manual valve, isolation valve and no or blind flange.
closed system.
AND One or more B.2
NOTE--------
penetration flow paths Valves and blind with all containment flanges in high isolation valves radiation areas may inoperable (except for be verified by use of 48 inch purge valve administrative means.
I leakage not within limit).
Verify the affected Once per penetration flow path 31 days for is isolated.
isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued)
Crystal River Unit 3 3.6-10 Amendment No.
Containment Isolation Valves 3.6.3 i
ACTIONS (continued) j CONDITION REQUIRED ACTION COMPLETION TIME i
e C;
NOTE---------
C.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I
Only applicable to penetration flow path penetration flow paths by use of at least 4
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with only one one closed and containment isolation de-activated valve and.a closed automatic valve, system.
closed manual valve, or blind flange.
One or more A_N.D penetration flow paths with one containment C.2
NOTE-------
isolation valve Valves and blind inoperable or the flanges in high
]
closed system radiation areas may breached.
be verified by use of administrative means.
Verify the affected Once per penetration flow path 31 days is isolated.
4 D.
One or more D.1 Restore purge valve 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow paths leakage to within l
r.
with one or more 48 limits.
inch containment purge valves not within j
d purge valve leakage
)
limits.
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E.
Required Action and E.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
AND E.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Crystal River Unit 3 3.6-11 Amendment No.
k Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1' Verify each 48 inch purge valve is sealed 31 days closed except for one purge valve in a penetration flow path while in Condition D of the LCO.
SR 13.6.3.2 Verify each 6 inch post accident hydrogen 31 days purge valve is closed except when the 6 inch post accident hydrogen purge valves are open for pressure control, ALARA or air quality considerations for personnel entry, i
or for Surveillances that require the valves to be open.
NOTE-------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
Verify each containment isolation manual 31 days valve and blind flange that is located outside containment and is required to be closed during accident conditions is closed, except for containment isolation valves-that are open under administrative controls.
(continued) i Crystal River Unit 3 3.6-12 Amendment No.
Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.3.4
NOTE-------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
Verify each containment isolation manuel Prior to valve and blind flange that is located entering MODE 4 inside containment and required to be from MODE 5 if closed during accident conditions is not performed closed, except for containment isolation within the valves that are open under administrative previous controls.
92 days SR 3.6.3.5 Verify the isolation time of each power In accordance operated and each automatic containment with the isolation valve that is not locked, sealed, Inservice or otherwise secured in the isolation Testing Program position, is within limits.
NOTE--------------------
Results shall be evaluated against acceptance criteria of SR 3.6.1.1 in accordance with the Containment Leakage Rate Testing Program.
Perform leakage rate testing for each 48 Within 92 days inch containment purge valve.
after opening the valve AND 24 nionths (continued)
Crystal River Unit 3 3.6-13 Amendment No.
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Containment Isolation Valves 3.6.3 i
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SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY i
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NOTE--------------------
Not applicable in MODE 4.
1 j-Verify each automatic containment isolation 24 months
~ valve that is not locked, sealed, or otherwise secured in the isolation
+
position, actuates to the isolation i
i position on an actual or simulated actuation signal.
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Crystal River' Unit 3 3.6-14 Amendment No. 149 1
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Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.20 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate
-testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
4 This program shall.be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak Test Program," dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 54.2 psig.
The containment design pressure is 55 psig.
The maximum allowable primary containment leakage rate, L,, at P,,
shall be 0.25% of primary containment air weight per day 2
Leakage Rate acceptance criteria are:
i 1.
Containment leakage rate ar u nce criterion is 5 1.0 L,.
During the first unit sta.
sollowing testing in y
accordance with this program, the leakage rate acceptance criteria are 5 0.60 L,ts.for the Type B and Type C Tests and 1 0.75 L, for Type A Tes 2.
Air 'ock testing acceptance criteria are:
j a.
Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.
b.
For each coor, leakage rate is s 0.01 L, when tested at 2 8.0 psig.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
Crystal River Unit 3 5.0-23A Amendment No.
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SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY t
BASES e
6 s
l SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all i
Specifications and apply at all times, unless otherwise stated.
l t
SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits.
Failure to meet a Surveillance within the_ specified Frequency, in accordance i
with SR 3.0.2, constitutes a failure to meet an LCO.
Systems and components are assumed to be OPERABLE wher, the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:
a.
The systems or components are known to be inoperable, although still meeting the SRs; or b.
The requirements of the Surveillance (s) are known not to be met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. The SRs associated with a PHYSICS TEST Exception LC0 are only applicable when the PHYSICS TEST Exception LCO is used as an allowable exception to the requirements of a Specification.
Surveillances, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. SRs have to be met in accordance with SR 3.0.2 prior to returning equipment to OPERABLE statu>.
Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE.
This includes meeting applicable SRs in accordance with SR 3.0.2.
Post maintenance testing may not be possible in the current MODE or other specified (continued)
Crystal River Unit 3 B 3.0-16 Amendment No.
e SR Applicability B 3.0 4
t BASES t
SR 3.0.1 conditions in the Applicability due to the necessary unit (continued) parameters not having been established.
In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function.
This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be i
completed.
t SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..."
s interval.
SR 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
t The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is-the verification of conformance with the SRs.
The exceptions to SR 3.0.2 are those Surve;11ances for i
which the 25% extension of the interval specified in the Frequency does not apply.
These exceptions are stated in the individual Specifications. The requirements of 2
regulations take precedence over the TS.
Therefore, when a test interval is specified in the regulations, the test 4-interval cannot be extended by the TS, and the SR include a Note in the Frequency stating, "SR 3.0.2 is not applicable."
An example of an exception when the test interval is not specified in the regulations is the Note in the Containment Leakage Rate Testing Program, "SR 3.0.2 is not applicable."
This exception is provided because the program already includes extension of test intervals."
As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis.
The (continued)
Crystal River Unit 3 8 3.0-17 Amendment No.
4 SR Applicability l
B 3.0 i
BASES SR 3.0.2 25% extension applies to each performance after the initial (continued) performance.
The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.
The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals or periodic Completion Time intervals beyond those specified.
SR 3.0.3 SR 3.0.3 cstablishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.
This delay period provides an adequate time limit to complete Surveillances that have been missed, This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of-the Surveillance. The basis for.this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable i
result of any particular Surveillance being performed is the verification of conformance with the SRs.
When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, SR 3.0.3 allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the Surveillance.
(continued)
Crystal River Unit 3 B 3.0-18 Amendment No.
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c SR Applicability r
B 3.0 3
BASES i
SR 3.0.3-Failure to comply with specified Frequencies for SRs is (continued)'
expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend j-Surveillance intervals.
If a Surveillance is not completed within the allowed delay i
period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable Specification Conditions begin immediately upon expiration
-of the delay period.
If a Surveillance is failed within the a
delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable
~,
Specification Conditions begin immediately upon the failure l
of the Surveillance.
i Completion of the Surveillance within the delay period i
allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.
SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified i
condition in the Applicability.
~
This Specification ensures that system and component i-OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure i
safe operation of the unit. This Specification applies to j
changes in MODES or other specified conditions in the Applicability associated with unit shutdown as well as startup. However, in certain circumstances, failing to meet an SR will not result in SR 3.0.4 restricting.a MODE change or other specified condition change.
When a system, j
subsystem, train, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed (per SR 3.0.1).
Surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the
'SR(s) to be performed is removed.
i (continued)
Crystal River Unit 3 B 3.0-19 Amendment No.
d i
j SR Applicability-B 3.0 BASES SR 3.0.4 Therefore, failing to perform the Surveillance (s) within the (continued) specified Frequency.'does not result in an SR 3.0.4 restriction to changing MODES ~or,other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.
The provisions of SR 3.0.4 shall not prevent ent y into MODES or other specified conditions in the Applicuility that are required to comply with ACTIONS.
The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs in accordance with the requirements of SR 3.0.4 are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition (s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated Specification prior.to the performance or completion of a Surveillance. A-Surveillance that could not be performed until after entering the Specification Applicability would have its Frequency specified such that it'is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required to be performed until a particular event, condition, or time has been reached. The SRs are annotated consistent with the requirements of Section 1.4, Frequency.
Crystal River Unit 3 8 3.0-20 Amendment No.
4 Containment B 3.6.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.1 Containment BASES BACKGROUND The containment consists of the concrete reactor building (RB), its steel liner, and the penetrations through this structure. The structure is designed to contain water and steam, as well as radioactive material that may be released from the reactor core following a Design Basis Accident (DBA). Additionally, this structure provides shielding from the fission products that may be present in the containment atmosphere following accident conditions.
The containment is a reinforced concrete structure with a cylindrical wall, a flat foundation mat, and a shallow dome roof. The cylinder wall is prestressed with a post tensioning system in the vertical and horizontal directions, and the dome roof is prestressed using a tnree way post tensioning system. The inside surface of the containment has a carbon steel liner to ensure a high degree of leak tightness during operating and accident conditions.
The concrete RB is' required for structural integrity of the containment under DBA conditions.
The steel liner and its penetrations establish the leakage limiting boundary of the containment. Maintaining the containment OPERABLE limits the leakage of fission product radioactivity from the containment to the environment.
SR 3.6.1.1 leakage rate requirements comply with 10 CFR 50, Appendix J, Option B (Ref. 1).
The isolation devices for the penetrations in the containment boundary are a part of the containment leak tight barrier. To maintain this leak tight barrier:
a.
All penetrations required to be closed during accident conditions are either:
1.
capable of being closed by an OPERABLE automatic containment isolation system, or 2.
closed by manual valves, blind flanges, or de-activated automatic valves secured in their closed positions, except as provided in LC0 3.6.3, " Containment Isolation Valves";
(continued)
Crystal River Unit 3 B 3.6-1 Amendment No.
e Containment B 3.6.1 BASES BACKGROUND b.
Each air lock is OPERABLE, except as provided in (continued)
LCO 3.6.2, " Containment Air Locks".
APPLICABLE The safety design basis for the containment is that the SAFETY ANALYSES containment must withstand the pressures and temperatures of the limiting DBA without exceeding the design leakage rate.
The DBAs that result in a challenge to containment from high pressures and temperatures are a loss of coolant accident (LOCA), a steam line break, and a rod ejection accident (REA) (Ref. 2).
In addition, release of significant fission product radioactivity within containment can occur from a LOCA or REA.
In the analyses of DBAs involving release of fission product radioactivity, it is assumed that the containment is OPERABLE so that the release to the environment is controlled by the rate of containment leakage. The containment was designed with an allowable leakage rate of 0.25% of containment air weight per day (Ref. 3). This leakage rate, used in the evaluation of offsite doses resulting from accidents, is defined in 10 CFR 50, Appendix J, Option B (Ref.1), as L.:
the I
maximum allowable leakage rate at the calculated maximum peak containment pressure (P.) resulting from the limiting DBA. The allowable leakage rate represented by L. forms the basis for the acceptance criteria imposed on all containment leakage rate testing.
L. is assumed to be 0.25% of containment air weight per day in the safety analysis at P. - 54.2 psig (Ref. 3).
The acceptance criteria applied to accidental releases of radioactive material to the environment are given in terms of total radiation dose received by a hypothetical member of the general public who is assumed to remain at the exclusion area boundary for two hours following onset of the postulated fission product release. The limits established in 10 CFR 100 (Ref. 5) are a whole body dose of 25 Rem or a 300 Rem dose to the thyroid from iodine exposure.
The containment satisfies Criterion 3 of the NRC Policy Statement.
(continued)
Crystal River Unit 3 B 3.6-2 Amendment No.
Containment B 3.6.1 BASES (continued)
LCO Containment OPERABILITY is maintained by limiting leakage to less than the acceptance criteria of the. Containment Leakage l Rate Testing Program.. Compliance with this LCO will ensure i
a containment configuration, including equipment hatches, l
that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis.
Individual leakage rates specified for the containment air lock (LC0 3.6.2) and purge valves with resilient seals (LC0 3.6.3) are not specifically part of the acceptance criteria of SR 3.6.1.1.
Therefore, leakage rates exceeding these individual limits only result in the containment being inoperable when the total leakage exceeds the acceptance criteria of the Containment Leakage Rate Testing Program.
l 1
APPLICABILITY In MODES 1, 2, 3, and 4, a DBA could cause a release of radioactive material into containment.
In MODES 5 and 6, l
the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES. Therefore, containment is not required to be i
OPERABLE in MODE 5.
The requirements for containment during MODE-6 are addressed in LC0 3.9.3, " Containment i
' ACTIONS A_d In the event containment is inoperable, containment must be restored to OPERABLE status within I hour.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining containment during MODES 1, 2, 3, and 4.
This time period also ensures the probability of an accident (requiring containment OPERABILITY) occurring during periods when i
containment is inoperable is minimal.
B.1 and B.2 If containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be placed in a MODE in which the LC0 does not apply. To achieve this (continued)
Crystal River Unit 3 B 3.6-3 Amendment No.
l Containment B 3.6.1 BASES i
ACTIONS B.1 and B.2 (continued) status, the plant must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full l
power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.1.1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing l
Program.
Failure to meet air lock and purge valve with resilient seal leakage limits for SR 3.6.2.1 and 3.6.3.6 does not constitute a failure of this Surveillance unless the contribution from these penetrations causes overall Type A, B, and C leakage to exceed limits.
SR Frequencies are as required by the Containment Leakage Rate TestingThus, S Program.
does not apply. These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.
SR 3.6.1.2 This SR ensures that the structural integrity of the containment will be maintained in accordance with the i
provisions of the Containment Tendon Surveillance Program.
Testing and Frequency are consistent with the recommendations of NRC Regulatory Guide 1.35, Revision 3.
The guidance in Regulatory Guide 1.35 should be followed in the event abnormal degradation of the containment tendons is detected.
This includes testing additional tendons and submitting a Special Report to the NRC (Refer to Specification 5.7.2.b).
The impact of large-scale tendon degradation should also be evaluated with respect to Containment OPERABILITY.
In this context, containment structural integrity is analogous to containment OPERABILITY.
(continued)
Crystal River Unit 3 B 3.6-4 Amendment No.
_.. - = -... - -. -.. _ -.
. ~....... -
Containment B 3.6.1
.i.
. BASES (continued).
REFERENCES 1.
10 CFR 50, Appendix J, Option B l
2.
FSAR, Sections 14.2.2 3.
'FSAR, 5.2.1.1 l
3 4.
Regulatory Guide 1.35, Rev.3, 1990.
i-5.
4 6.
NEI 94-01, Revision 0, " Industry Guideline for l
Implementing Performance-Based 00 tion of 10 CFR 50, Appendix J" P
7.
ANSI /ANS-56.81994, "American National Standard for l
Containment System Leakage Testing Requirement" l
t i
1 i
i 1
i:
1 l.
o I
l e
I
- i Crystal River Unit 3 B 3.6-5 Amendment No.
i l
Containment Air Locks B 3.6.2 i
B 3.6 CONTAINMENT SYSTEMS B 3.6.2 Containment Air Locks j
BASES BACKGROUND Containment air locks form part of the containment pressure l
boundary and provide a means for personnel access during all MODES of operation.
Each air lock is nominally a right circular cylin' der,10 ft in diameter, with a door at each end. The doors are interlocked to prevent simultaneous opening. During-periods L
when containment.is not required to be OPERABLE, the door interlock mechanism may be disabled, allowing both doors of 4
an air lock to remain open for extended periods when f.
frequent containment entry is-necessary.
Each air lock: door
{'
has been designed and is tested to verify its ability to i
withstand a pressure in excess of the maximum expected pressure following a Design Basis Accident (DBA) in-containment. Therefore, closure of a single door supports containment OPERABILITY.
Each of the doors contain two gasketed seals:and local leakage rate testing capability to ensure pressure. integrity. To effect a leak tight seal, the air lock design uses pressure seated doors (i.e., an increase in containment internal pressure results. in increased sealing force on each door).
Each personnel air lock door is provided with limit switches that provide control' room indication of door position.
i Additionally, control room indication is provided to alert the operator whenever_ an air lock door interlock mechanism is defeated.
The containment air locks form part of the containment 1
. pressure boundary.
Their integrity and leak tightness is essential for maintaining the containment leakage rate within limit.in the event of a DBA.- Not maintaining air lock integrity or leak tightness may result in a leakage i
rate in excess of that assumed in the unit safety analysis.
All leakage rate requirements are in conformance with j
10 CFR 50, Appendix J, Option B (Ref. 1).
l l
(continued)
Crystal River Un'it 3-B 3.6-6 Amendment No.
i j
Containment Air Locks B 3.6.2 BASES (continued)
APPLICABLE The DBAs that result in a release of radioactive material SAFETY ANALYSES within containment are a loss of coolant accident (LOCA), a steam line break, and a rod ejection accident (Ref. 2).
In the analysis of each of these accidents, it is assumed that containment is OPERABLE so that release of fission products to the environment is controlled by the rate of containment leakage.
The containment was designed with an allowable leakage rate of 0.25% of containment air weight per day (Ref. 3).
This leakage rate is defined in the Containment Leakage Rate Testing Program, as L.:
the maximum allowable containment leakage rate at the calculated maximum peak containment pressure (P.) following a DBA.
This allowable leakage rate forms the basis for the acceptance criteria imposed on the SRs associated with the air lock.
L. is 0.25% of containment air weight per day and P. is 54.2 psig.
resulting from the limiting design basis LOCA.
The acceptance criteria applied to DBA releases of radioactive material to the environment are given in terms of total radiation dose received by a member of the general public who remains at the exclusion area boundary for two hours following onset of the postulated fission product release. The limits established in 10 CFR 100 (Ref. 4) are a whole body dose of 25 Rem or a 300 Rem dose to the thyroid from iodine exposure.
The containment air locks satisfy Criterion 3 of the NRC Policy Statement.
LC0 Each containment air lock forms part of the containment pressure boundary. As a part of containment, the air lock safety function is related to control of the containment leakage rate resulting from a DBA. Thus, each air lock's structural integrity and leak tightness are essential to the j
successful mitigation of such an event.
1 (continued)
Crystal River Unit 3 8 3.6-7 Amendment No, i
9 i
Containment Air Locks B 3.6.2 BASES LCO Each air lock is required to be OPERABLE.
For the air lock (continued) to be considered OPERABLE, the air lock interlock mechanism must be OPERABLE, the air lock must be in compliance with the Type B air lock leakage test, and both air lock doors must be OPERABLE. The interlock allows only one air lock door of an air lock to be opened at one time (Ref. 5).
This I provision ensures that a gross breach of containment does not exist when containment is required to be OPERABLE.
Closure of a single door in each air lock is sufficient to provide a leak tight barrier following postulated events.
Nevertheless, both doors are kept closed when the air lock i
is not being used for normal entry into and exit from containment.
APPLICABILITY In MODES 1, 2, 3, and 4, a DBA could cause a release of radioactive material to containment.
In MODES 5 and 6, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES.
Therefore, the containment air locks are not required in MODE 5 to prevent leakage of radioactive material from containment.
The requirements for the containment air locks during MODE 6 are addressed in LC0 3.9.3, " Containment Penetrations."
ACTIONS The ACTIONS are modified by a Note that allows entry and exit to perform repairs on the affected air lock component or for emergencies involving personnel safety.
If the outer door is inoperable, then it may be easily accessed to repair.
If the inner door is the one that is inoperable, however, then a short time exists when the containment boundary is not intact (during access through the outer door).
In this context, repairs include follow-up actions to an initial failure of the air lock door seal SR in order to determine which air lock door (s) is faulty.
There are circumstances where an at-power containment entry would be required during the period of time that one air lock was inoperable.
In this case, entry would be made through the OPERABLE air lock if ALARA conditions permit.
However, the (continued)
Crystal River Unit 3 B 3.6-8 Amendment No.
Containment Air Locks B 3.6.2 BASES ACTIONS containment is a harsh environment with bulk average (continued) temperatures typically in excess of 120 F and self-contained breathing apparatus may be required with the reactor at power.
In the event something was to happen to the individual who had entered containment, plant personnel would proceed through the most expeditious rescue path in order to get that individual out and provide medical care.
Thus, the Note allows entry and exit through the inoperable door for_ personnel safety reasons when the quickest path to the person happens to be through the inoperable door.
The ability to open the OPERABLE door, even if it means the containment boundary is temporarily not intact, is acceptable due to the low probability of an event that could pressurize the containment during the short time in which the OPERABLE door is expected to be open. After each entry and exit the OPERABLE door must be immediately closed.
If ALARA conditions permit, entry and exit should be via an OPERABLE air lock.
A second Note has been added to provide clarification that, for this LCO, separate Condition entry is allowed for each air lock.
In the event the air lock leakage results in exceeding the-overall containment leakage rate, Note 3 directs entry into 3
the applicable Conditions and Required Actions of LC0 3.6.1,
" Containment."
A.1. A.2 and A.3 With one air lock door inoperable in one or more containment air locks, the OPERABLF door must be verified closed (Required Action A.1) in each affected containment air lock.
This ensures that a leak tight containment barrier is maintained by the use of an OPERABLE air lock door.
This action must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
This specified time period is consistent with the ACTIONS of LCO 3.6.1, which requires containment be restored to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
(continued)
Crystal River Unit 3 B 3.6-9 Amendment No.
=
Containment Air Locks B 3.6.2 BASES ACTIONS A.l. A.2 and A.3 (continued)
In addition, the affected air lock penetration must be isolated by locking closed-the remaining OPERABLE air lock door within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is considered reasonable for locking the OPERABLE air lock door, considering the OPERABLE door of the affected air lock is being maintained closed.
Required Action A.3 verifies that an air lock with an inoperable door has been isolated by the use of a locked and closed OPERABLE air lock door. This ensures that an acceptable containment leakage boundary is maintained.
The Completion Time of once per 31 days is based on engineering judgment and is considered adequate in view of the low likelihood of a locked door being mispositioned and other administrative controls.
The Required Actions have been modified by two Notes.
Nate 1 clarifies that only the Required Actions and nsociated Completion Times of Condition C are required if both doors in the same air lock are inoperable. With both doors in the same air lock inoperable, an OPERABLE door is not available to be closed.
Required Actions C.1 and C.2 are the appropriate remedial actions. Note 2 allows use of the air lock for entry and exit for 7 days under administrative controls.
Containment entry may be required to perform Technical Specifications (TS) Surveillances and Required Actions, as well as other activities on equipment inside containment that are required by TS or activities on equipment that support TS-required equipment.
This Note is not intended to preclude performing other activities (i.e.,
non-TS-required activities) if the containment was entered, using the inoperable air lock, to perform an allowed activity listed above. This allowance is acceptable due to the low probability of an event that could pressurize the containment during the short time that the OPERABLE door is expected to be open.
l (continued)
Crystal River Unit 3 B 3.6-10 Amendment No.
Containment Air Locks B 3.6.2 i
BASES ACTIONS B.1. B.2. and B.3 (continued)
With' an air lock interlock mechanism inoperable in one or i
more air locks, the Required Actions and associated i
Completion Times are consistent with those specified for Condition A.
The Required Actions have been modified by two Notes.
' Note 1 clarifies that only the Required Actions and associated Completion Times of Condition C are required'if both doors in the same air lock are inoperable. With both doors in the same air lock inoperable, an OPERABLE door is not available to be closed. Required Actions C.1 and C.2 are the appropriate remedial actions.
Note 2 allows entry into and exit from the containment under the control of a dedicated individual stationed at the air lock to ensure that only one door is opened at a time (i.e., the individual 1
performs the function of the interlock).
C.I. C.2. and C.3 With one or more air locks inoperable for reasons other than those described in Condition A or B, Required Action C.1 requires action to be immediately initiated to evaluate previous combined leakage rates using current air lock test results. An evaluation is acceptable since it is overly conservative to immediately declare the containment inoperable if both doors in an air lock have failed a seal test or if the overall air lock leakage is not within I
limits.
In many instances-(e.g., only one seal per door has failed), containment remains OPERABLE, yet only I hour (per LCO 3.6.1) would be provided to restore the air lock door to OPERABLE status prior to requiring a plant shutdown.
In i
j addition, even with both doors failing the seal test, the q
overall containment leakage rate can still be within limits.
This Condition is entered whenever the air lock fails to meet either leakage rate acceptance criteria specified in SR l
3.6.2.1 (the individual air lock door or the overall). The reason this condition is initially applicable to the failed air lock door SR is due to the design of the CR-3 air lock door leakage test configuration. Common piping is used to l
simultaneously leak rate test both air lock doors. When there is excessive leakage indicated during performance of l
1 (continued) a Crystai River Unit 3 B 3.6-11 Amendment No.
Containment Air Locks B 3.6.2 l
BASES-1 ACTIONS C.I. C.2. and C.3 (continued) the SR, it is not initially possible to identify which door (or both) is leaking in excess of the allowable limit.
Therefore, the conservative action is to consider both doors inoperable and enter Condition C until the air lock, or at a minimum one door, can be determined to be OPERABLE. Once this has been done, Condition C may be exited and plant operation continue in accordance with the LC0 or the l
Required Actions of Condition A, as applicable. Completion Times for Condition A begin when the determination has been made that Condition A can be entered.
Required Action C.2 requires that one door in the affected containment air lock must be verified to be closed. This action must be completed within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time.
This specified time period is cons', stent with the ACTIONS of LC0 3.6.1, which requires that containment be restored to OPERABLE status within I hour.
Additionally, the affected air lock (s) must be restored to OPERABLE status within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time. The specified time period is considered reasonable for restoring an inoperable air lock to OPERABLE status aseming that at least one door is maintained closed in each aftbcted air lock.
The Required Actions have been modified by a note indicating performance of an overall air lock leakage test may be used to satisfy Required Actions C.1 and C.3 when Condition C is entered as a result of failure of the individual door seal test. The overall leakage test is performed at a test pressure of P., allowing direct evaluation of air lock leakage results against the overall containment leakage rate limit.
Direct application of individual door seal leakage results to the overall limit is not technically justified since the individual test is performed at significantly less than P. and the results cannot be extrapolated.
Additionally, the test pressure applied to the outer door is in the non-accident direction.
Reliance on a successful performance of the overall leakage rate test for the purposes of declaring the air lock OPERABLE, even with one door not meeting its acceptance (continued)
Crystal River Unit 3 B 3.6-12 Amendment No.
3 Containment Air Locks J
B 3.6.2 BASES 4
l ACTIONS C.l. C.2, and C.3 (continued) criteria, is acceptable when considering the historical.
l intent of the overall/ individual door seal, air lock leakage rate tests. The overall test has historically been the true 1
measure of an air lock's ability to perform its DBA function.
Periodic containment airlock tests should be performed at not less than P, at a Frequency of at least i
i once per 30 months. Containment airlock test methods should be performed in accordance with the Containment Leakage Rate
)
Testing Program. Containment airlock door seals should be
[
tested within 7 days of opening. For periods of multiple containment entries where the airlock doors are routinely used for access more frequently than once every 7 days 1
(e.g., shift or daily inspection tours of the containment),
door seals may be tested once per 30 days during this time period. Door seals are not required to be tested when containment integrity is not required, however they must be 4
tested prior to reestablishing containment integrity.
Door seals shall be tssted at a pressure stated in the plant 4
Technical Specifications.
i D.1 and 0.2 If the inoperable containment air lock cannot be restored to OPERABLE status within the required Completion Time, the plant must be placed in a MODE in which the LC0 does not 4
apply.
To achieve this status, the plant must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner j
and without challenging plant systems.
SURVEILLANCE SR 3.6.2.1 1
REQUIREMENTS Maintaining containment air locks OPERABLE requires
{
compliance with the leakage rate test requirements of 10 CFR 50, Appendix J, Option B (Ref. 1), as modified by l
approved exemptions. This SR reflects the leakage rate testing requirements with regard to air lock leakage (Type B leakage tests). The acceptance criteria were established during ii.itial air lock and containment testing.
The (continued)
Crystal River Unit 3 B 3.6-13 Amendment No.
w Containment Air Locks B 3.6.2 l
BASES l
SURVEILLANCE SR 3.6.2.1 (continued) l REQUIREMENTS periodic testing requirements verify that the air lock leakage does not exceed the allowed fraction of the overall containment leakage rate. The Frequency is as required by the Containment Lcakage Rate Testing Program. Thus, I
l SR 3.0.2 (which allows Frequency extensions) does not apply.
The SR has been modified by two Notes. Note 1 states that an inoperable air lock door does not invalidate the previous l
successful performance of the overall air lock leakage test.
This is considered reasonable, since either air lock door is capable of providing a fission product barrier in the event of a DBA. Note 2 has been added to this SR requiring the
{
results to be evaluated against the acceptance criteria of i
This ensures that air lock leakage is properly i
accounted for in determining the overall containment' leakage rate.
l l
Sj 3.6.2.2 l
The air lock interlock is designed to prevent simultaneous opening of both doors in a single air lock.
Since the inner l
and outer doors of an air lock are both designed to withstand the maximum expected post accident containment pressure, closure of either door will support centainment OPERABILITY.
Thus, the door interlock feature supports 1
containment OPERABILITY while the air lock is being used for personnel transit in and out of the containment.
Periodic testing of this interlock demonstrates that the interlock will function as designed and that simultaneous opening of the inner and outer doors will not inadvertently occur.
Due to the purely mechanical nature of this interlock, and given i
that the interlock mechanism is only challenged when containment is entered, this test is only required to be performed upon entering containment but is not required more frequently than every 184 days. The 184 day frequency is based on engineering judgment and is considered adequate in view of other indications of door and interlock mechanism status available to operations personnel.
l t
k-4 (continued) i Crystal River Unit 3 B 3.6-14 Amendment No.
t w
Containment Air Locks B 3.6.2 BASES REFERENCES 1.
10 CFR 50, Appendix J, Option B l
2.
FSAR, Sections 14.2.2 3.
FSAR, 5.2.1.1 l
4.
10 CFR 100 5.
FSAR Section 5.2.5.2.3.1 6.
ANSI /ANS 56.8-1994 l
Crystal River Unit 3 9 3.6-14A Amendment No.
J
.m.._-_
Containment Isolation Valves B 3.6.3 l
l 8 3.6 CONTAINMENT SYSTEMS 4
}-
~
Containment Isol'ation Valves l
B 3.6.3 o'
[
VASES 1
BACKGROUND The general ' design basis governing isolation valve j
L requirements is' leakage through fluid penetrations not i
serving accident-consequence-limiting systems is minimized j
-by a double barrier so that no single, credible failure or i
malfunction of an' active component can result in loss of l
2 isolation or intolerable leakage. The installed double i
barriers take the form of closed piping systems, both inside l
J and outside the reactor building, and various types of l
l isolation valves (Ref.1).
i Containment isolation occurs upon receipt of a high i
containment pressure or diverse containment isolation signal. The containment isolation signal closes automatic containment isolation valves in fluid penetrations not i
required for operation of engineered safeguard systems to prevent leakage of radioactive material.
Upon actuation of high pressure injection, automatic containment valves also isolate systems not required for containment or Reactor Coolant System (RCS) heat removal. Other penetrations are isolated by the use of valves in the closed position or blind flanges. As a result, the containment isolation valves (and blind flanges) help ensure that the containment atmosphere will be isolated in the event of a release of i
radioactive material to containment atmosphere from the RCS following a Design Basis Accident (DBA).
OPERABILITY of the containment isolation valves (and blind i
flanges) supports containment OPERABILITY during accident conditions.
The OPERABILITY reghirements for containment isolation valves help ensure that containment is isolated within the time limits assumed in the safety analysis. Therefore, the OPERABILITY requirements provide assurance that containment leakage rates assumed in the safety analysis will not be exceeded.
The Reactor Building Purge System is part of the Reactor Building Ventilation System. The Purge System was designed for intermittent operation, providing a means of removing l
I (continued) 1 Crystal River Unit 3 B 3.6-15 Amendment No.
-- =
Containment Isolation Valves B 3.6.3 BASES BACKGROUND airborne radioactivity caused by minor leakage from the RCS i
(continued) prior to personnel entry into containment. The Containment Purge System consists of one 48 inch line for exhaust and i
one 48 inch line for supply, with supply and exhaust fans capable of purging the p/ min.
ontainment atmosphere at a rate of approximately 50,000 ft The containment purge supply and exhaust lines each contain two isolation valves that receive an isolation signal on a unit vent high radiation condition.
Each of the purge lines is provided with two 48 inch diameter butterfly valves, one inside and one outside of containment.
The valves inside containment are electric i
motor operated, designed to close within five seconds, while the outboard isolation valves are pneumatically opened-spring closed, casigned to close within two seconds of demand (Ref. 5).
Each of these valves was intended to be capable of closing against a differential pressure of 55 psig (the containment design pressure), such that closure i
would be assured in the event a loss of coolant accident (LOCA) occurred while containment purging was in progress.
Failure of the purge valves to close following a design basis event would cause a significant increase in the radioactive release because of the large containment leakage path introduced by these 48 inch purge lines.
Failure of the purge valves to close would result in leakage considerably in excess of the containment design leakage rate of 0.25% of containment air weight per day (L.)
(Ref. 2).
Because of their large size, the 48 inch purge valves are not qualified for automatic closure from their open position under DBA conditions. Therefore, the 48 inch purge valves are maintained sealed closed (SR 3.6.3.1) in MODES 1, 2, 3, and 4.
The 6 inch post accident hydrogen purge valves operate to:
l a.
Reduce the concentration of noble gases within containment prior to and during personnel access; and b.
Equalize internal and external pressures.
Since the post accident hydrogen purge valves are designed l
to meet the requirements for automatic containment isolation valves, these valves may be opened as needed in MODES 1, 2, 3,
and 4.
(continued)
Crystal River Unit 3 B 3.6-16 Amendment No.
Containment Isolation Valves B 3.6.3 BASES (continued)
APPLICABLE The containment isolation valve LCO was derived from the SAFETY ANALYSES requirements related to the control of leakage from containment during major accidents. This LC0 is intended to ensure the containment leakage rates do not exceed the values assumed in the safety analysis. As part of the containment. boundary, containment isolation valve OPERABILITY supports leak tightness of the containment.
Therefore, the safety analysis of any event requiring containment isolation is applicable to this LCO.
The DBAs that result in a release of radioactive material within containment are a loss of coolant accident (LOCA), a main steam line break, and a rod ejection accident (Ref. 3).
In the analysis for each of these accidents, it is assumed that containment isolation valves are either closed or function to close within the required isolation time following event initiation.
This ensures that potential leakage paths to the environment through containment isolation valves (including containment purge valves) are minimized.
The acceptance criteria applied to accidental releases of radioactive material to the environment are given in terms of total radiation dose received by a member of the general public who remains at the exclusion area boundary for two hours following the onset of the postulated fission product rel ease.
The limits established in 10 CFR 100 (Ref 8) are a whole body dose of 25 Rem or a 300 Rem dose to the thyroid from iodine exposure.
The DBA analysis assumes that, within 60 seconds after the accident, isolation of the containment is complete and leakage terminated except for the design leakage rate, L..
The containment isolation total response time of 60 seconds includes signal delay, diesel generator startup (for loss of offsite power), and containment isolation valve stroke times.
SR 3.3.5.4 addresses the response time testing requirements.
The single-failure criterion required in the safety analyses was considered in the criginal design of the containment purge valves. Two valves in a series on each purge line provide assurance that both the supply and exhaust lines could be isolated'even if a single failure occurred.
The (continued)
Crystal River Unit 3 B 3.6-17 Amendment No.
k
l o
l Containment Isolation Valves B 3.6.3 I
BASES l
APPLICABLE' inboard and outboard isolation valves on each line are SAFETY ANALYSES provided with diverse power sources, motor operated and (continuefi pneumatically operated spring closed, respectively.
This arrangement was designed to preclude common mode failures from disabling both valves on a purge line.
The containment purge valves may be unable to close in the environment following a LOCA.
Therefore, each of the 48 inch purge valves is required to remain sealed closed during MODES 1, 2, 3, and 4.
In this case, the single-failure criterion remains applicable to the containment purge valves because of failure in the control circuit associated with each valve. Again, the 48 inch l
purge system valve design prevents a single failure from compromising containment OPERABILITY as long as the system is operated in accordance with the subject LCO.
The containment isolation valves satisfy Criterion 3 of the NRC Policy Statement.
LC0 Containment isolation valves form a part of the containment bcundary. The containment isolation valve safety function is related to control of containment leakage' rates during a DBA.
The automatic power operated isolation valves are required to have isolation times within limits and to actuate on an l
automatic isolation signal. The 48 inch purge valves must l
be maintained sealed closed in MODES 1, 2, 3 and 4.
The l
valves covered by this LC0 are listed along with their j
associated stroke times in the FSAR (Ref. 4).
I The normally closed isolation valves are considered OPERABLE when manual valves are closed, check valves have flow through the valve secured, blind flanges are in place, and closed systems are intact.
Purge valves with resilient seals must meet additional leakage rate requirements addressed as part of this l
Specification. All.other containment isolation valve I
leakage rate testing is addressed by LCO 3.6.1,
" Containment," as part of Type C testing.
(continued) o Crystal River Unit 3 B 3.6-18 Amendment No.
Containment Isolation Valves B 3.6.3 BASES LC0 This LC0 provides assurance that the containment isolation (continued) valves and purge valves will perform their designated safety functions to control leakage from the containment during accidents.
4 APPLICABILITY In MODES 1, 2, 3, and 4, a DBA could cause a release of radioactive material to containment.
In MODES 5 and 6, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES.
Therefore, the containment isolation valves are not required to be OPERABLE in MODE 5.
The requirements for containment isolation valves during MODE 6 are addressed in LCO 3.9.3,
" Containment Penetrations."
ACTIONS The following terms are defined for the purpose of implementing this Specification:
penetration flowpath: The piping which passes through the RB liner such that a portion of the system inside the RB can communicate with the portion outside the RB. A penetration passes through the imaginary plane established by the RB liner.
unisolated: The state of a penetration flowpath whereby the operating fluid (liquid or gas) of the system is capable of passing freely through the imaginary plane established by the RB liner.
The ACTIONS are modified by a Note allowing penetration flow paths, except for 48 inch purge valve penetration flow paths, to be unis01ated intermittently under administrative control s.
These administrative controls consist of stationing a dedicated operator at the valve controls, who is in centinuous communication with the control room.
In this way, the penetration can be rapidly isolated when a need for containment isolation is indicated.
Due to the size of the containment purge line penetration and the fact that those penetrations exhaust directly from the containment atmosphere to the environment the penetration flow paths conta.ining these valves may not be opened under (continued)
Crystal River Unit 3 B 3.6-19 Amendment No.
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Containment Isolation Valves B 3.6.3 BASES ACTIONS administrative controls. A single purge valve in a (continued) penetration flow path may be opened to effect repairs to an inoperable valve, as allowed by SR 3.6.3.1.
A second Note has been added to provide clarification that, for this LCO, separate Condition entry is allowed for each penetration flow path.
The ACTIONS are further modified by a third Note, which ensures appropriate remedial actions are taken, if necessary, if the affected systems are rendered inoperable by an inoperable containment isolation valve.
In the event purge valve leakage results in exceeding the overall containment leakage rate, Note 4 directs entry into the applicable Conditions and F.equired Actions of LC0 3.6.1.
A.1 and A.2 a
In the event one containment isolation valve in one or more penetration flow paths is inoperable (except for purge valve leakage not within limit), the affected penetration flow path must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be 4
adversely affected by a single active failure.
Isolation barriers that meet this criterion are a closed and de-activated automatic containment isolation valve, a closed tranual valve, a blind flange, and a check valve with flow througn the valve secured.
For a penetration isolated in accordance with Required Action A.1, the valve used to l
isolate the penetration should be the closest available one to containment.
Required Action A.1 must be completed within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time. The specified time period is reasonable, considering the time required to isolate the penetration and the relative importance of supporting containment OPERABILITY during MODES 1, 2, 3, l
and 4.
For affected penetration flow paths that cannot be restored to OPERABLE status within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time and that have been isolated in accordance with Required 1
Action A.1, the affected penetration flow paths must be i
verified to be isolated on a periodic basis. This periodic j
l (continued)
Crystal River l'... t B 3.6-20 Amendment No.
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i Containment Isolation Values B 3.6.3 BASES ACTIONS A.1 and A.2 (continued) verification is necessary-to ensure that containment penetrations required to be isolated following an accident and no longer capable of being automatically isolated will be in the isolation position should an event occur.
This Required Action does not require any testing or valve manipulation.
Rather, it involves verification, through a system walkdown, that those isolation devices capable of being mispositioned are in the correct position. 'The Completion Time of "once per 31 days for isolation devices outside containment" is appropriate considering the fact that the valves are operated under administrative controls and the probability'of their misalignment is low.
For the isolation devices inside containment, the time period specified as " prior to entering MODE 4 from MODE 5 if not-performed within the previous 92 days" is based on engineering judgment and is considered reasonable in-view of the inaccessibility of the isolation devices and other administrative controls that will ensure that isolation device misalignment is an unlikely possibility.
I Condition A has been modified by a Note indicating this Condition is only applicable to those penetration flow paths with two containment isolation valves.
For penetration flow paths with only one containment isolation valve and a closed system, Condition C provides appropriate actions.
Required Action A.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and allows the devices to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable since access to these areas is typically restricted. Therefore, the probability of misalignment of these devices, once they have been verified i
to be in the proper position, is small.
B.1 and B.2 With all containment isolation valves in one or more penetration flow paths inoperable (except for 48 inch purge i
valve leakage not within limit), the affected penetration flow path must be isolated within I hour.
The method of isolation must include the use of at least one isolation (continued)
Crystal River Unit 3 B 3.6-21 Amendment No.
!o 1
Containment Isolation Valves B 3.6.3 BASES ACTIONS B.1 and B.2 (continued) barrier that cannot be adversely affected by a single active failure.
Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is consistent with the ACTIONS of LC0 3.6.1.
In the event the affected penetration is isolated in accordance with Required Action B.1, the affected penetration must be verified to be isolated on a periodic basis per Required Action B.2.
This periodic verification is necessary to assure leak tightness of containment and that penetrations requiring isolation following an accident are isolated. The Completion Time of once per 31 days for verifying each affected penetration flow path is isolated is appropriate considering the fact that the valves are operated under administrative controls and the probability of their misalignment is low.
Condition B is modified by a Note indicating this Condition is only applicable to penetration flow paths with two containment isolation valves or those with one containment isolation valve and no closed system.
Condition A of this Specification addresses the condition of one containment isolation valve inoperable in a penetration flow path with two containment isolation valves.
Required Action B.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and allows the devices to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable since access-to these areas is typically restricted. Therefore, the probability of misalignment of these devices, once they have been verified to be in the proper position, is small.
C.1 and C.2 With one or more penetration flow paths with one containment isolation valve inoperable or the closed system breached, the inoperable valve must be restored to OPERABLE status or l
the affected penetration flow path must be isolated.
The method of isolation must include the use of at least one (continued)
Crystal River Unit 3 8 3.6-22 Amendment No.
i Containment Isolation Valves B 3.6.3 l
l BASES l
l ACTIONS C.1 and C.2 (continued) isolation barrier that cannot be adversely affected by a l
single active failure.
Isolation barriers that meet this i
criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. A check valve may l
not be used to isolate the affected penetration.
Required Action C.1 must be completed within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time. The specified time period is reasonable, considering the relative stability of the closed system (hence, reliability) to act as a penetration isolation boundary and the relative importance of supporting containment OPERABILITY during MODES 1, 2, 3, and 4.
In the event the affected penetration is isolated in accordance-with Required Action C.1, the affected penetration flow path must be verified to be isolated on a periodic basis. This periodic verification is necessary to assure leak tightness of containment and that containment penetrations requiring isolation following an accident are isolated. The Completion Time of once per 31 days for verifying that each affected penetration flow path is isolated is appropriate considering the fact that the valves are operated under l
administrative controls and the probability of their misalignment is low.
Condition C is modified by a Note indicating that this Condition is only applicable to those penetration flow paths with only one containment isolation valve and a closed system. This Note is necessary since this Condition is written to specifically address those penetration flow paths utilizing a closed system.
Required Action C.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and
=
allows these devices to be verified by use of administrative l
means. Allowing verification by administrative means is i
considered acceptable since access to these areas is typically restricted. Therefore, the probability of misalignment of these devices, once verified to be in the proper position, is small.
(continued)
Crystal River Unit 3 B 3.6-23 Amendment No.
i
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Containment Isolation Valves B 3.6.3 i
r BASES ACTIONS p_d (continued)
In the event one or more containment 48 inch purge valves in I one or more penetration flow paths are not within the purge valve leakage. limits, purge' valve leakage must be restored to within limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.,The specified time is a reasonable period for restoring the valve leakage to within i
limits, provided overall containment leakage rate remains within limits. With the purge valve seal degraded such that leakage exceeds the limits, there is an increased potential 1
for the same mechanism that caused the initial degradation l
to cause further degradation.
If left unchecked, this coula
)
result in a loss of containment OPERABILITY. Thus, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is necessary to limit the length of i
l time the plant can operate in this condition.
]
L j
E.1 and E.2 i
l' i
l If the Required Actions and associated Completion Times are not met, the plant must be placed in a MODE in which the LCO does not apply.
To achieve this status, the plant must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 l
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are l
reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
L SURVEILLANCE SR 3.6.3.1 l
REQUIREMENTS l
Each 48 inch containment purge valve is required to be verified sealed closed at 31 day intervals. This Surveillance is designed to ensure that a gross breach of containment is not caused by an inadvertent or spurious i
l opening of a containment purge valve. Detailed analysis of the purge valves failed to conclusively demonstrate their ability to close during a LOCA in time to maintain offsite doses to within licensing basis limits. Therefore, these valves are required to be in the sealed closed-position during MODES 1, 2, 3, and 4.
A containment purge valve that is sealed closed must have motive power to the valve operator removed. This can be accomplished by de-energizing 4
l (continued)
Crystal River Unit 3 8 3.6-24 Amendment No.
.m_.
Containment Isolation Valves B 3.6.3 j
BASES SURVEILLANCE S8 3.6.3.1 (continued)
REQUIREMENTS the source of electric power or by removing the air supply to the valve operator.
In this application, the term i
" sealed" has no connotation of leak tightness. The Frequency is a result of an NRC initiative, Generic Issue B-24 (Ref. 6), related to containment purge valve use during unit operations.
In the event purge velve leakage requires entry into Condition D, the Surveillance permits opening one purge valve in a penetration flow path to 4
perform repairs.
i I
This SR ensures that the 6 inch post accident. hydrogen purge 1 valves are closed as required or, if open, open for an 4
allowable reason.
The SR is not required to be met when the post accident hydrogen purge valves are open for pressure control, ALARA or-air quality considerations for personnel entry, or for Surveillances that require tho valves to be i
open.
The post accident hydrogen purge valves are capable I
of closir.g in the environment following a LOCA. Therefore, these valves are allowed to be open for limited periods of time.
The 31 day Frequency for verifying valve position is consistent with other containment isolation valve requirements discussed in SR 3.6.3.3.
SR 3.6.3.3 This SR requires verification that each containment isolation manual valve'and blind flange located outside containment and required to be closed during accident conditions is closed. The SR helps to ensure that post i
accident leakage of radioactive fluids or gases outside the containment boundary is within design limits. This SR does not require any testing or valve manipulation.
Ratner, it involves verification, through a system walkdown, that those i
valves outside containment and capable of being mispositioned are in the correct position.
Since verification of valve position for valves outside containment is relatively easy, a 31 day Frequency, based on engineering judgment was chosen to provide added assurance (continued)
Crystal River Unit 3 B 3.6-25 Amendment No.
4
Containment Isolation Valves B 3.6.3 l
l BASES i
l SURVEILLANCE SR 3.6.3.3 (continued) l REQUIREMENTS g'
of the correct positions.
The SR specifies that valves open l
under administrative controls are not required to meet the SR during the time the valves are open.
A Note modifies this SR and applies to valves and blind l
flanges located in high radiation areas allowing these devices to be verified closed by use of admir.istrative j
means. Allowing verification by administrative means is considered acceptable, since access to these areas is 1
typically restricted during MODES 1, 2, 3, and 4 for ALARA reasons. Therefore, the probability of misalignment of these valves, once they have been verified to be in the proper position, is low.
This SR requires verification that each containment l
isolation manual valve and blind flange that is located 4
inside containment and required to be closed during accident conditions is closed. The SR helps to ensure that post accident leakage of radioactive fluids or gases outside the containment boundary is within design limits.
For valves inside containment, the Frequency of " prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days" is appropriate, since these valves and flanges are typically inaccessible during reactor operation, are operated under administrative controls and the probability l
of.their misalignment is low. The SR specifies that valves open under administrative controls are not required to meet the SR during the time they are open.
l The Note allows valves and blind flanges located in high radiation areas to be verified closed by use of l
administrative means. Allowing verification by administrative means is considered acceptable, since the l
access to these areas is typically restricted during MODES 1, 2, 3, and 4 for ALARA reasons. Therefore, the probability of misalignment of these valves, once they have been verified to be in their proper position, is small.
l i
(continued) u i
Crystal River Unit 3 8 3.6-26 Amendment No.
4 e
ex-
o,,
Containment Isolation Valves B 3.6.3 BASES SURVEILLANCE SR 3.6.3.5 REQUIREMENTS (continued)
Verifying that the isolation time of each power operated and automatic containment isolation valve that is not locked, sealed, or otherwise secured in the isolation position is within limits is required to demonstrate OPERABILITY.
The isolation time test ensures the valve will isolate in a time period less than or equal to that assumed in the safety analyses.
The isolation time and Frequency of this SR are in accordance with the Inservice Testing Program.
SR 3.6.3.6 For 48 inch containment purge valves, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J is required to ensure OPERABILITY.
Operating experience has demonstrated that this type of valve seal has the potential to degrade in a shorter time period than do other seal types.
Based on this observation and the importance of maintaining this penetration leak tight (due to the direct path between containment and the environment),
additional purge valve testing was established as part of the NRC resolution of Generic Issue B-20, " Containment Leakage Due to Seal Deterioration" (Ref. 7).
The specified Frequencies are based on plant-specific as-found/as-left leakage rate data for these valves.
The data indicates the CR-3 purge valve resilient seals do not degrade during the operating cycle with the valves in the sealed closed position. The 92 day Frequency after opening the valves recognizes the seals are prone to excessive leakage following use and is consistent with the NRC resolution of B-20.
i A Note to this SR requires the results to be evaluated against the Containment Leakage Rate Testing Program. This l
ensures that excessive containment purge valve leakage is properly accounted for in determining the overall containment leakage rate to verify containment OPERABILITY.
i (continued)
Crystal River Unit 3 8 3.6-27 Amendment No.
l Containment Isolation Valves B 3.6.3 -
i I
l l
BASES SURVEILLANCE SR 3.6.3.7 REQUIREMENTS (continued)
Automatic containment isolation valves close on a i
1 containment isolation signal to prevent leakage of i
i radioactive material from containment following a DBA. This SR ensures each automatic containment isolation valve that is not locked, sealed, or otherwise secured.in the isolation l
position, will actuate to its isolation position on an l-actual or simulated. actuation signal.
The 24 month Frequcncy is based on the need to perform this Surveillance l.
under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance l
were performed with the reactor at power. Operating-l l'
experience has shown that these components.usually pass this Surveillance when performed at the 24 month Frequency.
l Therefore, the Frequency was concluded to be acceptable from j
-a reliability standpoint.
The SR is modified by a note indicating the SR is not applicable in the identified MODE. This is necessary in order to make the requirements for automatic system response l
consistent with those for the actuation instrumentation.~
REFERENCES 1.
FSAR, Section 5.3.1 2.
FSAR, Section 5.2.1.1 l
t l
3.
FSAR, Sections 14.2.2 l
4.
FSAR, Table 5-9.
5.
FSAR, Secticn 5.3.3.1 l
6.
Generic Issue B-24 7.
Generic Issue B-20 8.
+
i I
l Crystal River Unit 3 B 3.6-28 Amendment No.
i i
i j