ML17289A577
| ML17289A577 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/20/1992 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17289A576 | List: |
| References | |
| NUDOCS 9205290193 | |
| Download: ML17289A577 (8) | |
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ATTACHMENT I
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. REACTOR COOLAN7 SYSTEM OPERATIONAL LEAKAGE LIMITING CONOITION FOR OPERATION 3.4.3.2 a.
b.
C.
Reactor coolant system leakage shall be limited to:
AmG.Z EY THl5 No PRESSURE BOUNOARY LEAKAGE.
- LGlTER, 5
gpm UNIOENTIFIED LEAKAGE.
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OR. L.E.SS 2 gpm increase in UNIDENTIFIED LEAKAGE within an P'.o r eriod.
d.
25 gpm total leakage averaged over any 24-hour period.
e.
1 gpm leakage at a reactor coolant system pressure of 950 + 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.
APPLICABILITY:
OPFRATIONAL CONOITIONS 1, 2, and 3.
ACTION:
~ r' F mom c,aa-nz-om With any PRESSURE BOUNOARY LEAKAGE in at least HOT SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUT within the nex 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Mith any reactor coolant syst
~kage greater than the limits in h.
and/or d.
- above, reduce the ge rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least UTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTOOWN within t~ llowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Mith any reactor coolan tern pressure isolation valve leakage greater than the above it, isolate the high pressure portion of the affected system ~om the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least on~~er closed (manual or deactivated automatic)
(or check") valve ~ be in at least HOT SHUTOOMN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in.
SHUTOOMN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With one or more f the high/low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; restore the inoperable monitor(s) to OPERABLE status within 30 days or be in at least HOT SHUTOOWN wi i e xt 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTOOWN within the followin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
QHKD HY 'THLt LGTKP With an reactor coolant sy te.
UNIOENTIF 9
LEAKAGE increase greater an 2 gpm with>n an g-hour eriod ntiiy the source of leakage increase as not service sensitive Type 304 or 316 austenitic stainless steel within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least HOT SHUTDOWN within the nex 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
sr "Which has been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
WASHINGTON NUCL'EAR - UNIT 2
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9205290193 920520 PDR ADOCK 05000397 P
PDR 3/4 4"9
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REACTOR COOLANT SYSTEM BASES 3/4.4.2 SAFETY/RELIEF VALVES (Continued) the dual purpose safety/relief valves in their ASHE Code qualified mode (spring lift) of safety operation.
The overpressure protection system must accommodate the most severe pres-surization transient.
There are two major transients that represent, the most severe abnormal operational transient resulting in a nuclear system pressure rise.
The evaluation of these events with the final plant configuration has shown that, the HSIV closure. is slightly more severe when credit is taken only.
for indirect derived scrams; i.e.,
a flux scram.
Utilizing this worse case transient as the design basis
- event, a minimum of 12 safety/'relief valves are required to assure peak reactor pressure remains within the Code limit of 110 of design pressure.
Testing of safety/relief valves is normally performed at lower power.
It is desirable to allow an increased number of valves to be out of service during testing.
Therefore, an evaluation of the HSIV closure without direct scram was performed at 25K of RATED THERMAL POWER assuming only 4 safety/relief valves were operable.
The results of this evaluation demonstrate that any 4 safety/relief valves have sufficient flow capacity to assure that the peak reactor pressure remains well below the code limit of 110M of design pressure.
Oemonstration of the safety/relief valve lift settings will be performed in accordance with the provisions of Specification 4.0.5.
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3. 1 LEAKAGE OETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary.
These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"
Hay 1973..
censer&
8 WASHINGTON NUCLEAR - UNIT 2 8 3/4 4-la Amendment No. 8"
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FKM G 02-'t2-OZS INSERT B
The primary containment sump flow monitoring system monitors the UNIDENTIFIED LEAKAGE collected in the floor drain sump with a sensitivity such that 1
gpm change within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> can be measured.
Alternatively, other methods for measuring flow to the sump which a capable of detecting a change in UNIDENTIFIED LEAKAGE of 1 gpm within 1
may e used, for up to 30 days, when the installed system is INOPERABLE
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PROPOSED WCHNICAL SPECIFICATION INSERT CHANGE TO BASES SECTION 2.0 PARAGRAPH 8 for scram discharge volume 'A'525' 1/2" elevation) provides
- 87. 1 gallons of margin above the required 617.9 gallons of free volume required for a reactor scram.
The scram discharge volume high level alarm setpoint for scram discharge volume 'B'524'" elevation) provides 91.3 gallons of margin above the required 617.9 gallons of free volume required for a reactor scram.
The rod block setpoint for'scram discharge volume 'A'nd 'B'527'3" elevation) provides~
gallons of margin above the required 617.9 gallons of free volume required for a reactor scram.
The scram setpoint for scram discharge volume 'A'nd
'B'529'"
elevation) provides 64.9 gallons of margin above the required 617.9 gallons of free volume for a reactor scram.
- LHKNbE, KE,GLMETED Tlirt LETt'BR
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ATTACHMENT 3 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1 SERVICE WATER SYSTEMS Standby Service Water System..
High Pressure Core Spray Service Water System.
Ultimate Heat Sink..........
3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM......
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.
3/4. 7. 4 SNUBBERS.... ~..............
3/4 7 5 SEALED SOURCE CONTAMINATION 3/4. 7. 8 AREA TEMPERATURE MONITORING.
3.4.7.9 MAIN TURBINE BYPASS SYSTEM.
3/4,8 ELECTRICAL POWER SYSTEMS 3/4. 8; 1 '. C.
SOURCES A, C.
Sources
- Operating.
A. C.
Sources
- Shutdown.....
3/4.8.2 D.C.
SOURCES 0, C.
Sources
- Operating.
D.C.
Sources - Shutdown.
PAGE 3/4 7-1 3/4 7"3 3/4 7-4 3/4 7"5 3/4 7-8 3/4 7-10 3/4 7-16 3/4 7-~ I E 3/4 7-8F'cgQ 3/4 8-1 3/4 8-10 3/4 8"11 3/4 8-15 WASHINGTON NUCLEAR - UNIT 2 1X Amendment No. 67