ML20091M201
| ML20091M201 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/05/1984 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20091M196 | List: |
| References | |
| NUDOCS 8406110129 | |
| Download: ML20091M201 (4) | |
Text
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3.6.8-If INOPERABILITY was due to excessive combined leakage (See TS 4.4.1.7.1) demonstrate that one of the valves has no detectable leakage (by using soap solution at equal to or greater than 5 psig interspace pressure) and that this valve is maintained closed by approved administrative controls. This shall oe sufficient verification that the one valve is OPERABLE.
Plant operation may then continue provided that the OPERABLE valve is verified to be closed at least once per 31 days and is maintained closed by approved administrative controls.
If neither purge valve in the penetration can be declared OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be in HOT SHUlDOWN 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 SHJTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.6.9 Except as specified in 3.6.10 Delow the Reactor Building purge isolation valves shall be limited to less than 318 AH-V-1A & D) and less than 33 o AH-V-18 & C) open, by positive means, while purging is conducted.
a.
Containment purging shall not be performed for temperature or humidity control, b.
Containment purging is permitted tu reduce airborne activity in order to facilitate containment entry for the following reasons:
(1) Non-routine safety-related corrective maintenance.
(2) Non-routine safety-related surveillance.
(3) Performance of Technical Specification required surveillances.
(4) Radiation Surveys.
(5) Engineering stpport of safety-related modifications for pre-outage planning.
(6) Purging prior to shutdown to prevent delaying of outage commencement (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to shutdown).
c.
Containment purging is permitted for Reactor Building pressure control.
d.
To the extent practicable the above containment entries shall be scheduled to coincide, in order to minimize instances of purging.
3.6.10 When the reactor is in cold shutdown continuous purging is permitted with the Reactor Building purge isolation valves opened fully.
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- Bases
' The Reactor Coolant System conditions of cold shutdown assure tnat no steam
- will be formed and.hence no pressure will build up in the containment if the
' Reactor Coolant system ruptures.
-The-selected shutdown conu.
ns are based on the type of activities that are being. carried out and will preclude criticality in 'any occurrence.
( A condition requiring integrity of containment exists whenever tne reactor coolant system is open to the atmosphere and there is insufficient soluole poison-in the reactor coolant to maintain the core one percent subcritical in
.the event all control rods are withdrawn.
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The rAactor building is designed for an internal pressure of 55 psig, and an external pressure 2.5 psi greater than the internal pressure.
Due to reports of unsatisfactory performance of resilient seats of containment purge is01ation valves throughout the nuclear industry, a leakage test program has' been inplemented for these valves. This program assures a higher degree of assurance of purge valve operability.
An analysis.of the impact of purging on ECCS' performance and an evaluation of e
the radiological-consequences of a design basis accident while purging have been conpleted and accepted by the NRC staff. The purge isolation valves have been been demonstrated. capable of closing against the dynamic forces i
associated with a loss-of-coolant accident when limited to 30' open.
Allowing p' rge operations during hot shutdown and operation (TS. 3.6.9) is u
more beneficial than Iaquiring a coaldown tu cold shutdown from the _ standpoint
.of (a) avoiding unnecessary thermal stress cycles on the reactor coolant systens and its components and (b) reducing the potential for' causing unnecessary challenges to. the reactor. trip and safeguards systems.
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References -
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. FSAR Section 5.2.2.4.3-l i
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14.4.1.2.4 ~
Corrective A-tion eno Retest
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a.
If at.any time it'is determined that the criterion of 4.4.1.2.3
. sLl above is exceeded, repairs shall os initiated immediately.
A b.
If conformance to the criterion of 4.4.1.2.3 is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following detection of excessive local leakage, w-.
the reactor shall be shutdown and depressurized until repairs (
are effected and the local leakage meets the acceptance criterion.as demonstrated by retest.
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.4i4.1.2.5 Test Frequency Local leak detection tests shall be perf t med at a frequency of at
'least each refueling period, except that; a.
The equipment hatch and fuel transfer tube seals shall be testes every other refueling period but in no case at intervals greater
. than 3 years.. If they are opened they will be tested after being closed.
b.
The entile personnel and emergency airlocks shall be tested once every six months.
When the airlocks are opened during the interim between six month tests, the.airloc< door resilient seals shall be tested within 72-hours of the first of each of a
. series of openings.
This requirement exists whenever y
containment integrity is required.
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g c.
The reactor building purge isolation valves shall be leak tested cac.h refueling interval per 10 CFR 50 Appendix -J, Item III.D.2.
/.c d.
An interspace pressurization test (See T.S. 4.4.1.7.1) shall be performed for reactor building purge isolation valves every 3
.i month's. Tnis requirenent is not in effect during cold shutdown.
e.
Readings of the rotameters in each manifold of the penetration pressurization system shall be recorded at periodic intervals i2 not to exceed three' months.
.4.4.l.31 Isolation Valve Functional -Tests
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- Every three -months,-remotely operated reactor building _ isolation valves shall be stroked to the position required to fulfill their safety. function'unless.
1such operation is' noti practical during plant operation.
The valves not
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stroked every three months shall be. stroked curing each refueling perios.
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Annual Inspection
'A visualiexaminationlof the: accessible interior and exterior surfaces of the containment ' structure and its ' components shall be performed annually and prior' Lt.o:anyjintegrated leak test to uncover any eviden:e of < deterioration which may
. af fect, either the containment's structural' integrity or leak-tightness. - The:
Ldiscovery_ of any"significant deterioration'shall be> a:Com?anied by :::rective :
- actionstin-accord with acceptable
- procedures, noncestructive -tests, and.
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. inspect' ions,: and local testing. where. practical, ::io:1to tne concutt of any,
{ integrated leak test. -Such repairs shall be~ rep::te: as:part of the test
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l 4.4.1.5 Reacter Builcino Mcdifications Any major modification or. replacement of components affecting the reactor builcing integrity shall be followed by either an integrateo leak rate test or a local leak L._
test, as appropriate, and shall meet the acceptance criteria of 4.4.1.1.5 and.
4.4.1.2.3, respectively..
5 4.4.1.6 Operability of Access Hatch Interlocks 1*
At least once per 6 months the operability of the personnel and emergency hatch door interlocks and the associated control rcom annunciator circuits' shall be determined.
If the interlock permits both doors to be open.at the same time or does not provide accurate status indication in the control room, the interlock shall be declared inoperable.
4 2.
During periods when containment integrity is recuired and an interlock is inoperable, t.ach entry and exit via that airlock shall be locally supervised by a member of the unit operating maintenance or technical staffs, to assure that only one door is open at any time and that both ocors are properly closec following use. A record of supervision ano verification of closure shall be maintained during periods of interlock inoperability in an appropriate station log.
3.
If an interlock is inoperable for more than 14 cays following determinaElon of inoperability, use of the airlock, except for emergency purposes, shall be suspended until the interlock is returned to operable status.
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4.4.1.7E Operability of Purce Valves 1.
A periodic pressurization of the purge valve interspaces to 50.6 psig per T.S.
4.4.1.2.5d shall be performed to help assure timely ostection and resolutien of valve and/or actuator degradation.
Tne acceptance criteria is that total local leakage when updated for the new purge valve leakage shall be less than 0.6L.
See Tech Spec 3.6.8 for further action.
A 2.
Tne rubber seats on purge valves shall be visually examined eacn refueling interval to oetect degracation (e.g. cracking, brittleness, etc.) and to assure timely cleaning, lubrication, and seat reclacement.
As a minimum seats shall be replaced at the first refueling following 5 years of seat service.
Bases (l)
L The reactior building is designed for an internal pressure of 55 psig and'a
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steam-air mixture temperature of 281F. ' Pric; to initial operation,.the containment was strength tested at 115 percent of design pressure and leak rate tested at the design pressure. The containment was also leak tested prior to initial cperation at approximately 50 percent of the design pressure.
Tnese-tests established tne acceptance criteria'of 4.4.1.1.3.
The performance of' periodic intecrated and local leakace rate tests curing the plant life provides;a current assessment of poten:isi leakage from the containment in case of an accident that would pressurize the interior of the containment. -In 1
4-34a
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