ML20094C412
| ML20094C412 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 10/26/1995 |
| From: | VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | |
| Shared Package | |
| ML20094C410 | List: |
| References | |
| NUDOCS 9511020204 | |
| Download: ML20094C412 (2) | |
Text
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UVAR Tech. Specs.
TABLE OF CONTENTS Page i
1.0.
DEFINITIONS...................
...................3 2.0.
SAFETY LIMIT AND LIMITING SAFETY SYSTEMS SE'ITINGS....
10 2.1.
Safety Limit 10 2.2.
Limiting Safety System Settings..........................
14 1
3.0.
LIMITING CONDITIONS FOR OPERATION...................
15 3.1.
R e a c tivi ty..........................................
15 3.2.
Reactor Safety System.......
17 3.3.
Reactor Instrumentation...............................
19 3.4.
Radioactive Effluents
.................................21 3.5.
Co n fi n e m e n t...................................
22 3.6.
Limitations on Experiments..............
23
)
3.7.
Operation with Fueled Experiments.......
...............25 3.8.
Height of Water Above the Core in Natural Convection Mode of Operation..................................
26 3.9.
Rod-Drop Times.............
...............27 3.10.
Emergency Removal of Decay Heat.......................
28 3.11.
Primary Coolant Condition
...........................29 1
4.0.
SURVEILLANCE REQUIREMENTS 30 4.1.
Sh i m R od s...................................
30 4.2.
Reactor Safety System.
...............................31 4.3.
Emergency Core Spray System.................
.........32
)
1 4.4.
Area Radiation Monitoring Equipment.......
33 l
4.5.
M ain t e n a nce........................................
34 4.6.
Co n fi n e m e n t.......................................
35 4.7.
Airborne Effluents
...................................36 4.8.
Primary Coolant Conditions.............................
37 4.9.
Surveillance of Activity in Secondary Cooling System (Amendment No. 22).....................
37a l
5.0.
D ES IO N FEATU R ES......................................
3 8 5.1.
Reactor Fuel Specifications....
38 5.2.
Reactor Building.........
40 5.3.
Fuel Use and Storage............
....................41
- 6. 0.
ADMINISTRATIVE CONTROLS............................
42 6.1, O rga n iza t ion.........................
..............42 6.2.
Reactor Safety Committee.............
..........44 6.3.
Standard Operating Procedures......................
. 47 6.4.
Review and Approval of Experiments 49 6.5.
Plant Operating Records 52 6.6.
Required Acticns..
54 6.7.
Reporting Requiremem..
56 9511o202o4 951026 2
Amendment No. 22 PDR ADOCK 05000062 p
UVAR Tech. Specs.
4.9.
Surveillance of Activity in Secondary Cooling System Apolicability: This specification applies to the surveillance frequency of cooling tower (secondary system) water for identification of potential radioisotope concentrations.
Objective:
The objective is to discover incipient 4
primary-to-secondary heat exchanger leaks, either newly-formed or due to secondary tube plug failure (s),
by identification of sodium-24 or other reactor-produced radionuclides in the secondary water.
A second and related objective is to satisfy TS 3.1.4 (Radioactive Effluents; Airborne Effluents), TS 3.4.2 (Radioactive Effluents; Liquid Effluents), and 10 CFR 20 limits.
If sodium-24 or other radionuclide activity is observed in secondary system water, appropriate maintenance on the secondary system will be initiated.
Specification: Cooling tower (secondary system) water shall be sampled and analyzed for radionuclides, at least weekly.
Bases:
The plugging of heat exchanger secondary tubes and the impact of primary-to-secondary heat exchanger leaks are analyzed in UVAR LEU-SAR Section 9.19 and Section 9.20, respectively.
It is reasoned that incipient secondary tube plug failures and new secondary tube pinhole leaks (possibly caused by corrosion and/or erosion) would be associated with initially very small and slowly-increasing leak rates.
This TS 4.9,
" Surveillance of Activity in Secondary Cooling System", specifies a secondary system water sampling and counting interval appropriate to ensure small leak identification long before time-averaged liquid and airborne release concentration limits are challenged.
j This TS 4.9 is not material to the secondary tube double-ended-guillotine-break (DEGTB) analyzed in LEU-SAR Section 9.20.8, which would result in a leak rate sufficiently large for rapid (
<1 day ) discovery (by visible and noticeably rapid falling pool water level).
Mitigation of the consequences of this hypothetically most-severe case would also occur before time-averaged liquid and airborne release concentration limits are i
challenged.
Specification of a very short secondary water sampling interval is not appropriate for large-scale leaks.
37a Amendment No. 22
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