ML20214J588
| ML20214J588 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/16/1986 |
| From: | Perks W ARKANSAS POWER & LIGHT CO. |
| To: | Mccrory S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20214J575 | List: |
| References | |
| ANO-86-2-00693, ANO-86-2-693, NUDOCS 8608150087 | |
| Download: ML20214J588 (4) | |
Text
Attachment 1 ARKANSAS POWER & LIGHT COMPANY Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 ANO-86-2-00693 Mr. Steve McCrory U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Comments on NRC SR0 Exam of July 15, 1986
Dear Mr. McCrory:
I have attached my comments on the SR0 examination for your review and consideration.
I thought that the test was well written and the key was for the most part accurate.
l The only general comment I have is that although I felt the questions included in section 5 were very good, the section took too long to complete!
I would like to express my appreciation for your efforts in providing us I
with a good wrftten examination.
If you have any comments, please contact me.
Very truly yours, i
Walt Perks l
Unit 2 Operations Supervisor l
WP: rab Attachment cc:
ANO-DCC Dan R. Howard 8608150087 860008 PDR ADOCK 05000368 V
PDR MEMBEA MIDOLE SOUTH UTILITIES SYSTEM l
ERC860484 07/16/86 5.01 Axial and Radial flux redistributions will also cause changes in CEA worth. Similar to key response 5 and 6.
5.02 a)
New rod position 75" i 10"
[75 i 10]" - 10"
_l 65 i 10" l Rod motion
=
b)
Assume BOL p =.0062 Assume EOLS =.0052 p=
S p
S
=
1 + AT 1 + AT
.0062
=.0052
=
1 +.08(26) 1 +.08(26) p=
.2%
.03%
p =.169% i.03 final insertion final insertion worth
.03
.15%p worth
.05
.17%p final rod position 110-145" final rod position 105 - 140" additional rod motion 25 - 80" additional rod motion 20-75" c)
SDBCS will maintain Tavg ~ 545*F, so no moderator temperature increase. With only a fuel temperature increase Doppler defect must be used.
BOL/MOL Doppler defect EOL Doppler defect 1.02 1.12 i
Doppler coefficient l
1.02%p/100% Power or 1.12%p/100% Power
.0102%p/% Power or
.0112%p/% Power
=
j Therefore, 545 Final temperature
=
2250 Final pressure
=
l i
l
[
ATTACanZNT TO ANO-86-2-00693
ERC860484 07/16/86 BOL/MOL DOPPLER EOL DOPPLER
.2 % p calculated in (S) for
.169%p calcuated in (S)
.0102% p/% Power BOL
.0112%p/% Power for EOL 15.1% power
= 19.6% power
=
range 17 to 22% power range of 13 to 18% power This was an excellent questions, but working was difficult using given data:
1)
A BOL Boron concentration 2)
An EOL EFPD 3)
A MOL Rod Worth Curve 5.04 Should accept 185 i 10.
5.06 Should accept top region of core (2/3 to top)
Reason - should accept because this is the region of minimum CHF and MAX AHF.
5.09
- 3) If " Normal" operating temperature is 545'F to 580*F, "C" is correct.
Reference 2103.05 Att. C-5 and A-8.
i If " Normal" Operating temperature is 80*F to 580*F, "B" is correct.
5.12
[Since it is a function of B-T/B + T]
(ANO terminology) 5.13 d.
False Reference SAR 6.3.3.3.1.3F included in safety analysis calculations if clad temperature No H2 is < 1800*F.
4 Question 6.08 Part a.
TM/LP should be changed to DNBR or Low Pressurizer Pressure.
Keason: ANO-2 does not have a TM/LP Trip.
ATTACHMENT TO ANO-86-2-00693 re-
.-n-e
..,._--.-,-r._
ERC860484 07/16/86 Question 6.08 Part b.
High Steam Generator water level results in a Reactor Trip, not a turbine trip.
If it is assumed that the feedwater level control system level switch is in its normal position (both),
failure of a single channel will not affect system operation due to the high select feature of the feedwater control system. Failure of one channel would result in a level deviation alarm on panel 2C-12 at a setpoint of 10% level deviation.
Level transmitter for ANO-2 are 2 LT 1033, 2LT 1034, 2LT 1133 and 2LT 1134.
Reference:
STM-2-69 Question 8.01 Answer should be at > 40 gpm of 1731 ppa boric acid solution.
Question 8.11 ANO OP2502.01 previously listed Operations Superintendent and Nuclear Engineering. Latest Rev. lists Operations Superintendent and Reactor Engineering.
ANO has never had a group called Nuclear Operations.
Should accept Nuclear Engineering or Reactor Engineering.
l l
l ATTACHMENT TO ANO-86-2-00693
.