ML20140E944
| ML20140E944 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/11/1986 |
| From: | Hill J BALTIMORE GAS & ELECTRIC CO. |
| To: | Dudley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20140E931 | List: |
| References | |
| NUDOCS 8603280247 | |
| Download: ML20140E944 (3) | |
Text
W// O lNC 9
/
0.
BALTIMORE OAS AND ELECTRIC CHARLES CENTER. P.O. BOX 1475 BALTIMORE. MARYLAND 21203 February 11, 1986 Mr. Noel Dudley U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406
Dear Noel:
First I would like to-thank you for your quick response on Mr. J. R. Denton's test results. Although I realize the results are unof ficial, your ef forts are greatly appreciated.
The following comments are our response to the questions and answers on the February 7, 1986, SRO exam that you administered to our Mr. J. R. Denton.
We are responding to the following answers:
5.02, 5.11a & b, 5.12, 6.01a, b & d, 6.03, 7.02, 8.04, and 8.05b.
5.02 Comment only-I feel that this question should be essay in lieu of multiple choice for the following reason:
If you assume no operator action and that Reactor Power will match steam demand, then I agree.with you that Shut Down Margin will remain the same.
Iloweve r, if you assume that the CEA's are moved outward to compensate for the 100 ppm Boron addition, then the Shut Down Margin will increase, therefore, the candidate should have to explain his answer.
5.11a IAW OP-3 Rev. 23 page 4 CCOM 86-006 dated 1/86:
" Prior to exceeding 207. Rx Power all CEA's must be withdrawn beyond the Long Term Steady State Insertion limit."
Therefore increasing power from 20% to 707,would be done by Boron dilution.
At CCNPP full power RCS AT is 48 F. therefore f rom 07. to 1007. power Th increases f rom 532 F to $96 F or 64 F change. We also program RCS Tc-from 07 to 1007, from 532 F to 548 F or 184T.
In other words, as power is increased it turns out that Th increases 4 F for every F change in Tc (64 F/16 F).
Pa 'Pdu Nd' V
a
,e o
d Mr. Noel Dudley 'F b 11, 1986 e.
o i
Assuming a negative MTC, as the Rx is diluted to power, the upper core section temperature increases more'than the bottom half, therefore the neutron flux increases more in the botton half than the top half of the core. ASI = L-U as power goes to the bottom: ASI goes in the L+U '
positive direction. This is opposite of what you state.
~
5.11b Since power is shifting to the bottom 6f the core, only limiting'the power increase will help the ASI until the swing begins to shift power to the top (pe 14 hrs), then CEA insertion could, control ASI.
s 5.12 Comment only-Different references show a prcapt drop in reactor power following'a Rx' trip to anywhere from 7% down to the 3% you show on the answer key.
Since this power level occurs only momentarily and cannot be seen by our indication, a broader range should be accepr.able.
6.01a Disagree. Automatic closure of SI-651 and SI-652 occurs only whe,n Pzr Pressure exceeds 300 psia as read on PI-103 & PI-103-1 respectiv'ely.
Although procedure directs us not to exceed 300 F, there is no automatic function associated with this.
Sys. Description #62 RCS Instrumentation,page 28 & 2t8 6.Olb Disagree. RAS opens sump valves only.
Sys. Description #63 ESFAS page 13 4
6.01c OK 6.01d Disagree. 2/4 trips for SIAS opens Cont. Spray Valves which will occur on Low Pzr Press. or liigh Cont. Press.
1 Sys. Description #63 page 8 and page 156 table 5-9 t
6.03 Air Operated Normal Valve Action Stat 10n Valves Position On Loss of Air Effect AFW Blocking Open Open Nonc Valves - See System Description #34 page 11 enclosed.
CCIIX SW Outlet Valves - See attached OH-49 circled valves that state "F0" Fall Open 1.--__--,------.--n-a x.-.
a.--
7 o
5 Mr. Noel Dudley Feb. 11, 1986 7.02 Disagree - Admin. limit is 2000 mrem /qtr not 2400 mrem /qtr. (CCI-800B pg 9) 8.04a Question is vague - see enclosed Emergency Plan Procedure:
For an " Unusual Event" (see page 17, 18 and Attachments 1,& 2)
Basically we must notify the following:
(1) Onsite personnel-by sounding the general emergency alarm (2) From Attachment 1 - We must notify the listed offsite agencies (3) From Attachment 2 - page 2 - We must notify the:
SEC - Site Emergency Coordinator M-NO - Manager-Nuclear Operations' EPU - Emergency Planning Unit 8.04b We do not use the term " General Area Emergency".
However, for a
" General Emergency" all of the Attachment 2 page 2 ERP positions listed must be notified.
8.05b See attached Tech Spec for U-2:
Unit 2 Shutdown Margin requirement is now the same as Unit 1 (3.5% ak/k)
If you have any questions concerning my answer key responses or documentation, please don't hesitate to call.
Respectfully, OP M U
/
Hill
{ /. R.
Supervisor Operations-Training JRH/tjg cc:
J. R. Denton Enclosures
(
-