ML17289A470
| ML17289A470 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/10/1992 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17289A469 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9204200091 | |
| Download: ML17289A470 (14) | |
Text
The following pages will be affected by this Technical Specification amendment.
REMOVE 3/4 4-8 3/4 4-9 3/4 4-10 B 3/4 4-la B 3/4 4-2 INSERT 3/4 4-8 3/4 4-9 3/4 4-10 B 3/4 4-la B 3/4 4-2 920gZ00091 PDR ADOCY 0 R
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REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:
a.
The primary containment atmosphere gaseous radioactivity monitoring
- system, b.
The primary containment sump flow monitoring system, and c.
The primary containment atmosphere particulate radioactivity monitoring system.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
O..
With only two of the above required leakage detection systems
- OPERABLE, operation may continue for up to 30 days provided grab samples of the con-tainment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT SHUTDOWN 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 COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
gnSec0 H SURVEILLANCE RE UIREMENTS R
4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:
a.
Primary containment atmosphere particulate and gaseous monitoring systems-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a
CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATIOH at least once per 18 months.
b.
Primary containment sump flow monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.
WASHIHGTON NUCLEAR - UNIT 2 3/4 4-8
INSERT A With the primary containment sump flow monitoring system INOPERABLE, operation may continue for up to 30 days provided an alternate manual leak rate measurement method is applied to obtain the required sump monitoring until the drain sump monitoring system is restored; otherwise, be in at least HOT SHUTDOWN 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 COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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, REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING'CONDITION FOR OPERATION 3'.3.2 Reactor coolant system leakage shall be limited to:
a.
b.
5 gpm UNIDENTIFIED LEAKAGE.
c.
2 gpm increase in UNIDENTIFIED LEAKAGE within any P'-hour period.
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:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With any reactor coolant syst IVekaga greater than the limits in b.
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 UTDOMN 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 COLD SHUTDOWN within t~ llowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With 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 SHUTDOWN 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.
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
Mith 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 SHUTDOWN 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 SHUTOOMN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e.
Mith an reactor coolant system UNIDENTIFIED LEAKAGE increase greater
~j ~an 2 gpm with>a an +hour period, identity tha 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 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 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 3/4 4"9
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0 REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREHENTS 4.4.3.2. 1 The reactor coolant system leakage sha'll be demonstrated to be within each of the above limits by:
a.
tlonitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
tlonitoring the primary containment sump flow rate at least once per ~ezra, SHIFT. 407 TD FxQ.6c'D l.Z. AGER.R c.
Honitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4. 0. 5 and verifying the leakage of each valve to be within the specified limit:
b',
At least once per 18 ponths.
Prior to returning t
, valve to service following maintenance, repai'r or replacement
'n the valve which could affect,its leakage rate.
The provisions of Specificati'on POP/ are not app'licable for entry into OPERATI'ONAL CONDITION3.'p
'@y
- 4. 4. 3. 2. 3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4. 3. 2-2 by performance of a:
a.
CHANNEL FUNCTIONAL'TEST at least once per 31 days, and b.
CHANNEL CALIBRATIOH at least once per 18 months.
MASHINGTOH NUCLEAR " UNIT 2
.3/4 4-10 Amendment No.
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REACTOR COOLANT SYSTEM BASES 3/4.4.2 SAFETY/RELIEF VALVES (Continued) the dual purpose safety/relief valves in their ASME 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 MSIV 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 110K 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 MSIV closure without direct scram was performed at 25K of RATED THERMAL POMER 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 110K of design pressure.
Demonstration 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 DETECTION 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,"
May l973.,
insert 8
MASHINGTON NUCLEAR - UNIT 2 8 3/4 4-la Amendment No. 8"
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 are capable of detecting a change in UNIDENTIFIED LEAKAGE of 1 gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> may be used, for up to 30 days, when the installed system is INOPERABLE.
I 4
CONTROLLED COPY REACTOR COOLANT SYSTEM BASES 3/4. 4. 3. 2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based
'n the predicted and experimentally observed behavior of cracks in pipes~The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system leakage was also con-sidered.
The evidence obtained from experiments suggests that for leakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability CEWkl< L<TIB is small that the imperfection or crack associated with such leakage would grow rapidly.
However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shut down to allow further investigation and corrective action.
Service sensitive reactor coolant system Type 304 and 316 austenitic stainless steel piping; i.e., those that are subject to high stress or that certain relatively
- stagnant, intermittent, or low flow fluids, requires additional surveillance and leakage limits.
The surveillance requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4. 4 CHEMISTRY The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant.
Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION.
During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0,5 ppm concentration of chlorides is not considered harmful during these periods.
Conductivity measurements are required on a continuous basis since changes.
in this parameter are an indication of abnormal conditions.
When the conductivity is within limits, the pH, chlorides and other impurities affecting conductivity must also be within their acceptable limits'ith the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.
The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
WASHINGTON NUCLEAR - UNIT 2 B 3/4 4-2
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