ML20117A931
| ML20117A931 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/24/1985 |
| From: | - No Known Affiliation |
| To: | |
| Shared Package | |
| ML20117A934 | List: |
| References | |
| DPR-51-A-094, NPF-06-A-063 NUDOCS 8505080425 | |
| Download: ML20117A931 (3) | |
Text
. -
Ey TARLE'3.5.1-1 (Cont'd)
=
OTHER SAFETY RELATED SYSTENS I
(Cont'd)-
1 2
3 4
5
,?
No. of Operator action in channels Min.
Min.
if conditions of No. of for sys-operable degree of column 3 or 4
,y channels tem trip channels redundancy cannot he met.
2.
Pressurizer level channels 2
N/A 2,
1 Note 10 Pt 3
3.
Emergency Feedwater Flow channels 2/S.G.
N/A 1
0 Note 10 4.
RCS subcooling margin monitors 2
N/A 1
0 Note 10 I
{
5.
F.lectromatic relief valve flow maaltor 2
N/A 1
0 Note 11 6.
Electromatic relief block valve position indicator 1
N/A 1
0 Note 12 7.
Pressurizer code safety valve flow monitors 2/ valve N/A I/ valve 0
Note 10 R.
Degraded Voltage Monitoring a.
4.16KV Emergency Bus Undervoltage 2/ Bus 1/ Bus 2/Rus 0
Note 14 l
b.
460V Emergency Bus Undervoltage
- l/ Bus 1/Rus 1/ Bus 0
Notes 13, 14 i
j 9.
Chlorine Detection Systems 2
1 2
0 Notes 17, 18 l
10.
Containment High Range Radiation Monitoring 2
N/A 2
0 Note 20 i
i 11.
Containment Pressure - High j
Range 2
N/A 2
0 Note 21 12.
Containment water Level -
Wide Range 2
N/A 2
0 Note 21 B505000425 850424 l
PDR ADOCK 05000313 P
PDR i
- Two underv41tage ' relays per bus are userl with a coincident trip logic (2-out-of-2)
m r
of '
Table 4.1-1 '(Cont'd)-
h[
Channel Description Check Test Calibrate Remarks ag. 20.
Reactor fluilding Spray System f4A' M(1)
NA (1) Including R8 spray pump, spray j'
System _togic Channels valve, and cinem. add. valve logic
=
channels.
21.
Reactor Building Spray System Analog Channels 1
a a.
Reactor Building Pressure Channels 11A N
R 22.
Pressurizer Temperature Channels 5
11A R
23.
Control Rod Absolute Position 5(1) flA R
(1) Compare with Relative Position Indicator.
24.
Control Rod Relative Position 5(1)
NA R
(1) Check with Absolute Position Indicator
.~
25.
Core flooding Tanks a.
Pressure Channels 5
tJA R
b.
Level Channels 5
NA R
26.
Pressurizer Level Channels 5
NA R
27.
Makeup Tank Level Channels D
HA R
28.
Radiation Monitoring Systems other u
H(1)
Q(2)
(1) Check functioning of self-checking than containment hi,gh range feature on each detector.
monitors (items 7 )
(2) R for those detectors inaccessible during normal operation.
2 ';.
High.and low Pressure Injection flA flA R
Systems: Flow Channels
,e i.
a s
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
b.
The Safety Limit violation shall be reported to the Comission, the Vice President, Nuclear Operations and to the SRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSC. This report shall describe (1) appli-cable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Comis-sion, the SRC and the Vice-President, Nuclear Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recomended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
t b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
Modification of Core Protection Calculator (CPC) Addressable e
Constants NOTE: Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the Plant Safety Comittee.
h.
New and spent fuel storage.
1.
i j.
Postaccident sampling (includes sampling of reactor coolant, radio-active iodines and particulates in plant gaseous effluent, and the containmentatmosphere).
6.8.2 Each procedure of 6.8.1 above, and changes the'reto, shall be reviewed by the PSC and approved by the ANO General Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
ARKANSAS - UNIT 2 6-13 Amendment No. 24, 25. O, 52, H,63
4 ADMINISTRATIVE CONTROLS 6.8.3. Temporary changes to procedures of 6.8.1 above may be made provided:
l a.
The intent of the original procedure is not altered, b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by the PSC and approved by the c.
ANO General Manager within 14 days of implementation.
l 4
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES l
6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Administrator of the Regional Office unless otherwise noted.
STARTUP REPORT 6.9.1.1 A sunnary report of plant startup and power escalation testing shall be submitted following (1) recei;;t of an operating license (2) amendment to the license involving a planned increase in power level, (3) installation of 4
fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
i 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be i
described. Any additional specific details required in ifcense conditions i
based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or connence-i ment of commercial power operation, or (3) 9 months following initial critical-ity, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup) test program, a shall be submitted at least every tnree months until all three events have been completed.
ARKANSAS - UNIT 2 6-14 Amendment No. 5, p,;,
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