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{{#Wiki_filter:FACILITY POST-EXAMINATION COMMENTS FOR THE QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION JUNE 2007 June 25,2007 SVP-07-040 Regional Administrator, Region 111 US. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265  
{{#Wiki_filter:FACILITY POST-EXAMINATION COMMENTS FOR THE QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION JUNE 2007
 
June 25,2007 SVP-07-040 Regional Administrator, Region 111 U S . Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265


==Subject:==
==Subject:==
Initial License Training NRC Written Examination From June 11, 2007, to June 18, 2007, Initial License Training (ILT)
Initial License Training NRC Written Examination From June 11, 2007, to June 18, 2007, Initial License Training (ILT) NRC examinations were administered to six (6) Senior Reactor Operator (SRO) candidates and one (1) Reactor Operator (RO) candidate at Quad Cities Nuclear Power Station. We are requesting a revision of the written examination answer key for one question (#IO). Attached, you will find the requested change and the justification supporting the change.
NRC examinations were administered to six (6) Senior Reactor Operator (SRO) candidates and one (1) Reactor Operator (RO) candidate at Quad Cities Nuclear Power Station.
Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.
We are requesting a revision of the written examination answer key for one question  
(#IO). Attached, you will find the requested change and the justification supporting the change. Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.
Respectfully, Timothy J. Tulon Site Vice President Quad Cities Nuclear Power Station Attachments:
Respectfully, Timothy J. Tulon Site Vice President Quad Cities Nuclear Power Station Attachments:
cc: NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Raymond K. Walton -Region 111 JUN 2 8 2007 Attachment I The answer to question 40 (below) should be different than what is listed in the written examination answer key. QUESTION: 040 (1 .OO) With Unit 2 in Mode 1 on the 60% rod line, Operators raise recirculation flow with both pumps to 80% of rated drive flow. Assume that the APRM Flow Biased scram signal is set to the analytical value The APRM Flow Biased scram set point is now . . . A. 108.0%.
cc:     NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Raymond K. Walton -Region 111 JUN 2 8 2007
B. 112.2% C. 115.9%. D. 125.0% The key provided with the examination lists the answer as "B, but the correct answer should be "C". Quad Cities Lesson Plan LIC-0703 LPRM/APRM, provided to your office with the original reference material submittal, lists the APRM Flow Biased scram setpoint Analytical Limit:
 
APRM HIGH-HIGH Trip Unit Setpoint: Analytical Limit 20% (Not in Run) Analytical Limit 56 WD+71.1% and 125% WD is the percentage of recirculation loop flow, which provides a rated core flow of 98 million Ibs/hr. 0.56(80) + 71.1% = 115.9%. Therefore, the answer to the question should be "C", 115.9%. A facility requested revision to question might have prompted the error on the key. As originally provided for validation, the question was based on the Tech Spec allowable value for the APRM Flow Biased scram setpoint  
Attachment I The answer to question 40 (below) should be different than what is listed in the written examination answer key.
(.56 WD+67.4% and 122%) and the correct answer was "8". Following validation, the facility requested revision of the question to base it on the Analytical Limit instead of the Tech Spec allowable value. The Lead Examiner and Facility Representative agreed on the revision prior to approval, but it appears that the key was not revised accordingly.
QUESTION: 040 (1.OO)
SENIOR REACTOR OPERATOR Page 101 001 b 002 b 003 b 004 a 005 d 006 c 007 a 008 d 009 a 010 a 011 c 012 a 013 d 014 a 015 d 016 b 017 c 018 c 019 b 020 a 021 b 022 c 023 b 024 d 025 c 026 c 027 c 028 d 029 c 030 b 031 d 032 a 033 b 034 b 035 c 036 a 037 d 038 a 039 a ANSWER KEY MULTIPLE CHOICE 041 c 061 a 042 c 062 c 043 c 063 a 044 b 064 d 045 c 065 c 046 b 066 c 047 b 067 d 048 a 068 b 049 b 069 b 050 b 070 a 051 c 071 b 052 b 072 b 053 a 073 b 054 a 074 c 055 d 075 b 056 d 076 b 057 b 077 b 058 c 078 c 059 a 079 a 060 c 080 c 081 a 082 d 083 b 084 a 085 d 086 c 087 d 088 d 089 d 090 c 091 b 092 d 093 a 094 b 095 a 096 b 097 d 098 d 099 c 100 a ('***"'***
With Unit 2 in Mode 1 on the 60% rod line, Operators raise recirculation flow with both pumps to 80% of rated drive flow.
END OF EXAMINATION  
Assume that the APRM Flow Biased scram signal is set to the analytical value The APRM Flow Biased scram set point is now . . .
********** )}}
A. 108.0%.
B. 112.2%
C. 115.9%.
D. 125.0%
The key provided with the examination lists the answer as " B , but the correct answer should be "C".
Quad Cities Lesson Plan LIC-0703 LPRM/APRM, provided to your office with the original reference material submittal, lists the APRM Flow Biased scram setpoint Analytical Limit:
APRM HIGH-HIGH Trip Unit Setpoint:
Analytical Limit 20%
(Not in Run)
Analytical Limit 5 6 WD+71.1%and 125%
WD is the percentage of recirculation loop flow, which provides a rated core flow of 98 million Ibs/hr.
0.56(80) + 71.1% = 115.9%. Therefore, the answer to the question should be "C", 115.9%.
A facility requested revision to question might have prompted the error on the key. As originally provided for validation, the question was based on the Tech Spec allowable value for the APRM Flow Biased scram setpoint (.56 WD+67.4%and 122%) and the correct answer was "8". Following validation, the facility requested revision of the question to base it on the Analytical Limit instead of the Tech Spec allowable value. The Lead Examiner and Facility Representative agreed on the revision prior to approval, but it appears that the key was not revised accordingly.
 
SENIOR REACTOR OPERATOR                                           Page 101 ANSWER KEY MULTIPLE CHOICE 001 b         021 b             041 c         061 a         081 a 002 b         022 c             042 c         062 c         082 d 003 b         023 b             043 c         063 a         083 b 004 a        024 d            044 b         064 d         084 a 005 d        025 c            045 c         065 c         085 d 006 c        026 c            046 b         066 c         086 c 007 a        027 c            047 b         067 d         087 d 008 d        028 d            048 a         068 b         088 d 009 a        029 c            049 b         069 b         089 d 010 a        030 b            050 b         070 a         090 c 011 c        031 d            051 c         071 b         091 b 012 a        032 a            052 b         072 b         092 d 013 d        033 b            053 a         073 b         093 a 014 a        034 b              054 a         074 c         094 b 015 d        035 c              055 d         075 b         095 a 016 b        036 a              056 d         076 b         096 b 017 c        037 d              057 b         077 b         097 d 018 c        038 a              058 c         078 c         098 d 019 b        039 a              059 a         079 a         099 c 020 a                          060 c         080 c         100 a
('***"'*** END OF EXAMINATION ********** )}}

Latest revision as of 01:45, 23 November 2019

Facility Post - Examination Comments for the Quad Cities Nuclear Power Station Initial Examination June 2007
ML073170299
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 11/09/2007
From:
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co, Exelon Nuclear
Shared Package
ML072010156 List:
References
50-254/07-301, 50-265/07-301 50-254/07-301, 50-265/07-301
Download: ML073170299 (4)
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Text

FACILITY POST-EXAMINATION COMMENTS FOR THE QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION JUNE 2007

June 25,2007 SVP-07-040 Regional Administrator, Region 111 U S . Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Initial License Training NRC Written Examination From June 11, 2007, to June 18, 2007, Initial License Training (ILT) NRC examinations were administered to six (6) Senior Reactor Operator (SRO) candidates and one (1) Reactor Operator (RO) candidate at Quad Cities Nuclear Power Station. We are requesting a revision of the written examination answer key for one question (#IO). Attached, you will find the requested change and the justification supporting the change.

Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.

Respectfully, Timothy J. Tulon Site Vice President Quad Cities Nuclear Power Station Attachments:

cc: NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Raymond K. Walton -Region 111 JUN 2 8 2007

Attachment I The answer to question 40 (below) should be different than what is listed in the written examination answer key.

QUESTION: 040 (1.OO)

With Unit 2 in Mode 1 on the 60% rod line, Operators raise recirculation flow with both pumps to 80% of rated drive flow.

Assume that the APRM Flow Biased scram signal is set to the analytical value The APRM Flow Biased scram set point is now . . .

A. 108.0%.

B. 112.2%

C. 115.9%.

D. 125.0%

The key provided with the examination lists the answer as " B , but the correct answer should be "C".

Quad Cities Lesson Plan LIC-0703 LPRM/APRM, provided to your office with the original reference material submittal, lists the APRM Flow Biased scram setpoint Analytical Limit:

APRM HIGH-HIGH Trip Unit Setpoint:

Analytical Limit 20%

(Not in Run)

Analytical Limit 5 6 WD+71.1%and 125%

WD is the percentage of recirculation loop flow, which provides a rated core flow of 98 million Ibs/hr.

0.56(80) + 71.1% = 115.9%. Therefore, the answer to the question should be "C", 115.9%.

A facility requested revision to question might have prompted the error on the key. As originally provided for validation, the question was based on the Tech Spec allowable value for the APRM Flow Biased scram setpoint (.56 WD+67.4%and 122%) and the correct answer was "8". Following validation, the facility requested revision of the question to base it on the Analytical Limit instead of the Tech Spec allowable value. The Lead Examiner and Facility Representative agreed on the revision prior to approval, but it appears that the key was not revised accordingly.

SENIOR REACTOR OPERATOR Page 101 ANSWER KEY MULTIPLE CHOICE 001 b 021 b 041 c 061 a 081 a 002 b 022 c 042 c 062 c 082 d 003 b 023 b 043 c 063 a 083 b 004 a 024 d 044 b 064 d 084 a 005 d 025 c 045 c 065 c 085 d 006 c 026 c 046 b 066 c 086 c 007 a 027 c 047 b 067 d 087 d 008 d 028 d 048 a 068 b 088 d 009 a 029 c 049 b 069 b 089 d 010 a 030 b 050 b 070 a 090 c 011 c 031 d 051 c 071 b 091 b 012 a 032 a 052 b 072 b 092 d 013 d 033 b 053 a 073 b 093 a 014 a 034 b 054 a 074 c 094 b 015 d 035 c 055 d 075 b 095 a 016 b 036 a 056 d 076 b 096 b 017 c 037 d 057 b 077 b 097 d 018 c 038 a 058 c 078 c 098 d 019 b 039 a 059 a 079 a 099 c 020 a 060 c 080 c 100 a

('***"'*** END OF EXAMINATION ********** )

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