BSEP 12-0141, Initial Exam 2012-301 Post Exam Comments
| ML13008A517 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/20/2012 |
| From: | Pope A Duke Energy Corp |
| To: | Mccree V Division of Nuclear Materials Safety II |
| References | |
| IR-12-301, BSEP 12-0141 | |
| Download: ML13008A517 (5) | |
Text
Duke 0Energy December 20, 2012 Serial: BSEP 12-0141 U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325, 50-324 NRC Operator License Written Examination Facility Comments
Reference:
1.
Letter from Mark E. Franke (NRC) to Michael J. Annacone (CP&L), Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 0500032512012301 and 05000324/2012301), dated March 8, 2012, ADAMS Accession Number ML120690257 On December 18, 2012, NRC operator license written examinations were administered at the Brunswick Steam Electric Plant (BSEP).
In accordance with ES-402, Administering Initial Written Examinations, of Supplement 1 to Revision 1, of NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, Carolina Power & Light Company (CP&L) has performed a post-examination review and is submitting comments for consideration in the grading process. contains comments, recommendations, and references for a question from the written license exam.
Please refer any questions regarding this submittal to Mr. Bob Bolin, Senior Nuclear Operations Instructor, at (910) 457-3078, or Mr. Tony Pearson, Superintendent Operations Training, at (910) 457-2057.
Sincerely, Annette H. Pope Manager Organizational Effectiveness Brunswick Steam Electric Plant LJG/ljg flEC 282012
U.S. Nuclear Regulatory Commission Page 2
Enclosure:
1.
NRC Operator License Written Examination Facility Comments cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN:
Mr. Bruno Caballero 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Mark E. Franke Chief, Operations Branch 2 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mr. Christopher Gratton (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 cc (without enclosure):
Chair
- North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
BSEP 12-0141 ENCLOSURE 1 RO/SRO Exam Question #3:
3.
205000 1 RHR Loop A is operating in the Shutdown Cooling mode of operation with the following parameters:
RHRSW Pump 2A Operating RHRSW Flow 2000 gprn RHR Pump 2A Operating RHR Loop A Flow 6000 gpm Which one of the following choices completes the statements below?
The required operator action to lower the cooldown rate lAW 2OPl7, Residual Heat Removal System Operating Procedure, is to (1)
The effect of this action is that heat exchanger shell to tube differential pressure will (2)
A. (1) throttle open El l-F048A, HX ZR Bypass Valve (2) rise B. (1) throttle open El l-FO4SA, HX 2A Bypass Valve (2) lower C. (I) throttle closed Eli -PDV-F068A, HX 2A SW Disch Vlv (2) rise D. (1) throttle closed Eli -PDV-FO6SA. HX 2A SW Disch Vlv (2) lower Answer: B K/A: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
Al.10
- Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Throttle valve position (Cm: 41.5 / 45.5)
RO/SRO Rating: 3.0 / 2.9 Page 1 of 3
Comment:
BSEP 12-0141 ENCLOSURE 1 The question asks for the valve that must be operated which under these conditions is the E11-F048, because the E11-PDV-F068 cannot be closed any further due to RHR SW flow limitations. The question also asks the response of the Shell to Tube dip. lAW the pump curves the discharge pressure of the RHR Pumps would lower as flow is increased. The RHR SW side is unchanged (it is at a higher pressure than the RHR side). Therefore the lowering of the RHR side pressure would cause the d/p to rise, not lower.
Recommendation:
The correct answer for this question should be A.
UPDATED FSAR CP&L REACTnR COOLAPTSYS TEM 5-0 AJD CoNNE(TErSvsrEMs
°age.
I CHAP TEf 5 FIGUPES RESIDUAL HEAT REMOVAL PUMP CHARACTERISTiC CURVE (TYPICAL)
Li. L
.ALL.oa.c Pen. 41I.J4yrE Page 2 of 3
BSEP 12-0141 ENCLOSURE 1 The first gauge shown below is the RHR SW pressure which will not change with the opening of the F048 valve.
The second gauge is the RHR pressure with the F048 valve closed with the conditions established in the question.
The third picture is the RHR pressure with the F048 valve full open with a flow increase. The RHR pressure has slightly lowered thereby causing the RHR Heat Exchanger d/p to rise.
5DD 40 300 S
20 100 RHR SW PUMP A DISCH PRESS
-F1-1 141
-f HX 2A MSiSF1ESS El 1Fl6O Fc1-F HX 2A STS AE El 1F96O Page 3 of 3