ML20006B775
| ML20006B775 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/24/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20006B713 | List: |
| References | |
| NUDOCS 9002050344 | |
| Download: ML20006B775 (3) | |
Text
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4 JAFNPP LIST OF TABLES (Cont'd)
Table Title Pace 4.2 8 Minimum Test and Calibration Frequency for Accident Monitoring 86a instrumentation 4.6 1 Comparison of the James A. FitzPatrick Nuclear Power Plant inservice 157 Inspection Program to ASME Inservice Inspection Code Requirements 4.6 2 Minimum Test and Calibration Frequency for Drywell Continuous 162a Atmosphere Radioactivity Monitoring System 3.7 1 Process Pipeline Penetrating Primary Containment 198 4.7 1 Minimum Test and Calibration Frequency for Containment Monitoring.
210 Systems 4.7 2 Exception to Type C Tests 211 3.12-1 Water Spray / Sprinkler Protected Areas 244j 3.12 2 Carbon Dioxide Protected Areas 244k 3.12 3 Manual Fire Hose Stations 244l i
4.12-1 Water Spray / Sprinkler System Tests 244q 4.12 2 Carbon Dioxide System Tests 244r 4.12 3 Manual Fire Hose Station Tests 244s i
l-6.2 1 Minimum Shift Manning Requirements 260a e
6.10 1 Component Cyclic or Transient Umits 261 l
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Amendment No. %)f, %3pi,p,134 iSE*E88848886gg3 l
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3.5 (cont'd) 4.5 (cont'd) condition, that pump shall be considered inoperable for 2.
Following any period where the LPCI subsystems or core purposes of satisfying Specifications 3.5.A,3.5.C, and spray subsystems have not been maintained in a filled 3.5.E.
condition; the discharge piping of the affected subsystem i
shall be vented from the high point of the system and
_ H.
Average Planar Uncar Heat Generation Rate (APLHGH) water flow observed.
During power operation, the APLHGR for each type of fuel as a 3.
Whenever the HPCI or RCIC System is lined up to take function of axiallocation and average planar exposure shall be within limits based on applicable APLHGR limit values which suction from the condensate storage tank, the discharge piping of the HPCI or RCIC shall be vented from the high have been approved for the respective fuel and lattice types.
point of the system, and water flow observed on a monthly When hand calculations are required, the APLHGR for each type basis.
of fuel as a function of average planar exposure shall not exceed 4.
The level switches located on the Core Spray and RHR the limiting value for the most limiting lattice (excluding natural uranium) shown in Figures 3511 through 3.5-14 during two System discharge piping high points which monitor these recirculation loop operation. Dunng single loop operation, the lines to insure they are full shall be functionally tested each APLHGR for each fuel type shall not exceed the above values h'
l multiplied by 0.84 (see Bases 3.5.K, Reference 1). If anytime H.
during reactor power operation greater than 25% of rated power Average Planar Unear Heat Generation Rate (APLHGR)
)
it is determined that the limiting value for APLHGR is being The APLHGR for each type of fuel as a function of average exceeded, action shall then be initiated within 15 minutes to planar exposure shall be determined daily during reactor restore operation to within the prescribed limits. If the APLHGR operation at >25% rated thermal power.
is not returned to within the prescribed limits within two (2) hours, an orderly reactor power reduction shall be commenced immediately. The reactor power shall be reduced to less than 25% of rated power within the next four hours, or until the AFLHGH is returned to within the prescribed limits.
Amendment No. 96,95,J4, A6,95,199,1#7, tal,134 i
123 p.
..c
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3.6 (cont'd) 4.6 (cont'd) 2.
2.
At least one safety / relief valve shal: be disassembled and inspected once/ operating cycle.
a.
From and after the date that the safety valve function of one safety / relief valve is made or found to be inoperable, continued operation is permissible only during the succeeding 30 days unless such valve is made operable sooner.
b.
From and after the time that the safety valve function on two safety / relief valves is made or found to be moperable,. continued reactor operation is
. permissible 'only during the succeeding 7 days unless such valves are sooner made operable.
l 3.
If Specification 3.6.E.1 and 3.6.E.2 are not met, the reactor 3.
The integrity of the nitrogen system and coiswas shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
wtuch provde manual and ADS actuation of the 4.
Low power physics testing and reactor operator training safety / relief valves shall be deiTiorstrated at least once i
shall be permitted ; with inoperable components as every 3 e specified in item B2 above, ptovded that reactor coolant 4.
An ' annual report of safety /refief vave failures and temperature is <212*F and the reactor vessel is vented or.
challenges will be sent to the NRC in accordance with the reactor vessel head is removed.
Section 6.9.A.2.b.
Amendment No.yf,76,1)d 134 143
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