L-2011-535, 05000250/251-2011-302 Turkey Point Post Exam Comments
| ML120090369 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/20/2011 |
| From: | Kiley M Florida Power & Light Co |
| To: | Mccree V Region 2 Administrator |
| References | |
| L-2011-535 | |
| Download: ML120090369 (9) | |
Text
L-201 1-535 Victor McCree Regional Administrator, Region II Attn: Bruno Caballero U. S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Re:
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 FPL Comments for the 2011 Written NRC License Examination The provisions of NUREG-1 021, Operator Licensing Examiner Standards, Examiner Standards ES-402, Administering Initial Written Examinations, allow the opportunity for submittal of comments on the written portion of the License Examination to the NRC. This letter documents that Florida Power and Light (FPL) Company has no challenges related to the site-specific written examination administered at Turkey Point on December 14, 2011.
FPL has two comments regarding the 2011 NRC License Examination Answer Key. First, Question 61 used indicated S/G level. The initial effects of S/G level response to a MSIV closure on the Simulator are opposite for narrow and wide range S/G levels. The answer key was updated to accept both A (WR) and D (NR). Also, Question 80 response was incorrectly marked during review. The correct response to Question 80 is A, instead of the presently marked response C. This also has been update. The corrected Answer Key is attached.
Should there be any questions, please contact Mark Wilson at (305) 246-6900.
Sincerely, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment SM cc:
Chief, Operations Branch, Division of Reactor Safety, Region II, USNRC Chief Examiner, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Document Control Desk, USNRC, Washington, D.C.
4j NRC LICENSE EXAM COMMENT SHEET 2011-302 TURKEY POINT INITIAL LICENSE OPERATOR EXAM Proposed Changes Test Item (Question #1 Issue Recommendation Reference Comments ScenarioIJPM)
Recommend accepting two answers (A and D).
The initial 3A SIG This question did not Narrow and Wide specify whether A
based on Wide Question # 61 indicated SIG Level Plant Simulator Range Level Range SIG Level, response was plotted was Narrow or Wide after 3A SIG MSIV Range SIG Level.
D based on Narrow was closed.
Range_SIG_Level.
The stem of the question asked for the The procedural required transition Recommend changing flowpath at Step 21 based on Subcooling the answer key to match where RCS Question # 80 3-EOP-E-3
< 50°F. The answer the stem and only accept Subcooling is checked key is marked with distractor A.
has the RNO transiton loss of Pressurizer to 3-EOP-ECA-3.1.
Pressure Control.
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Turkey Point Nuclear Plant 2011 Reactor Operator License Examination
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61.
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Unit 4 is at 25% power with all systems in normal alignments.
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Turkey Point Nuclear Plant 2011 Senior Reactor Operator License Examination 80.
Given the following:
Unit 4 experienced a Steam Generator Tube Rupture (SGTR) from 100% power.
Containment temperature on TE-4-6700, TE-4-6701, and TE-4-6702 is 135°F and rising.
The operating crew is implementing 4-EOP-E-3, Steam Generator Tube Rupture.
The crew stopped the RCS cooldown and verified the ruptured S/G pressure is increasing slowly.
QSPDS CET Subcooling is 70° F.
Instrument Air to Containment has been lost, and CANNOT be established.
Which ONE of the choices below completes the following statements?
In order to remain in 4-EOP-E-3, Steam Generator Tube Rupture, RCS subcooling is required to be greater than 1
If below the required RCS Subcooling for 4-EOP-E-3, en transition to (2)
A.
(1) 50°F Only A is correct (2) 4-EOP-ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery Desire B.
(1) 100°F (2) 4-EOP-ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery Desired C.
(1) 50°F (2) 4-EOP-ECA-3.3, SGTR without Pressurizer Pressure Control D.
(1) 100°F (2) 4-EOP-ECA-3.3, SGTR without Pressurizer Pressure Control 80
Procedure No.
Procedure
Title:
Page:
Approval Date:
4-EOP-E-3 Steam Generator Tube Rupture 1/10/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I
1 8 Establish Charging Flow a.
Charging pumps
- AT LEAST ONE a.
Perform the following:
RUNNING 1)
IF CCW flow to RCP thermal barrier is lost, THEN go to Step 19.
2)
Go to Step 1 8b.
b.
Check offsite power available b.
offsite power is NOT available, THEN check if diesel capacity is adequate to run one charging pump.
- 1) E adequate diesel capacity is !+/-QI available, THEN shed nonessential loads. Refer to ATTACHMENT 3 for component KW load rating.
c.
Start one charging pump.
d.
Place RCS Makeup Control Switch in STOP e.
Adjust speed controller as necessary to establish maximum charging flow from the running charging pump(s) f.
Adjust Charging Flow to Regen Heat Exchanger, HCV-4-121, to maintain proper seal injection flow g.
Verify charging pump suction auto transfers to RWST Check If RCS Cooldown Should Be Stopped Check core exit TCs
- LESS THAN a.
WHEN core exit TCs are less than Y REQUIRED TEMPERATURE FROM required temperature from Step 11, STEP 11 THEN goto Step 19b.
Stop RCS cooldown Maintain core exit TCs LESS THAN
/- REQUIRED TEMPERATURE FROM STEP 11 Check Ruptured S!G(s) Pressure STABLE IF pressure continues to decrease to less OR INCREASING than 250 psig above the pressure of the intact SG(s) used for cooldown, THEN go to 4-EOP-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 1
0 Part 2
- If below the required RCS Subc Check RCS Subcooling Based On Core Exit o to 4-EOP-ECA-3.1, SGTR WITH LO TCs
- GREATER THAN 50°F[230°F]
OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
22 Depressurize RCS To Minimize Break Flow V
And Refill PRZ a.
Normal PRZ spray AVAILABLE
> a.
Observe CAUTIONS and NOTE prior to Step 23 AND go to Step 23.
b.
Spray PRZ with maximum available spray until any of the following conditions satisfied Use ATTACHMENT 6 as reference Both of the following 1)
RCS pressure - LESS THAN RUPTURED S/G(s) PRESSURE 2)
PRZ level
- GREATER THAN 1 7%[50%]
OR PRZ level
- GREATER THAN 71 %[50%]
OR RCS subcooling based on core exit TCs
- LESS THAN 30°F[210°F]
c.
Stop depressurization by closing spray valve(s):
Close normal spray valves OR Close Auxiliary Spray Valve, CV-4-31 1 d.
Observe CAUTION prior to Step 25 AND go to Step 25 Stop RCP(s) as necessary to stop spray flow.
Perform the following:
a)
Reduce charging pump speed to minimum.
b)
Close Charging Flow To Regen Heat Exchanger, HCV-4-121.
c)
Adjust charging pump speed to maintain seal injection flow.
Part 2
Plausib lity
-No air with 70°F S bcooling
Procedure No.:
Procedure
Title:
Page:
Approval Date:
4-EOP-E-3 Steam Generator Tube Rupture 1/10/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I
CAUTIONS If a PRZ PORV is used to depressurize the RCS, the PRT rupture disk may rupture. This may result in abnormal containment conditions.
Cycling of the PRZ PORV shall be minimized.
fOT
a a
a a
I I
/f RCPs are NOT running, the upper head region may void during RCS depressurization.
This will result in a rapidly increasing PRZ level.
23 Depressurize RCS Using PRZ PORV To Minimize Break Flow And Refill PRZ a.
PRZ PORV
- AT LEAST ONE AVAILABLE a.
Establish auxiliary spray using ATTACHM urn to Step 1
jf auxiliary spray can fjQ] be established, THEN go to 4-EOP-ECA-3.3, SGTR WITH UT PRESSURIZER PRESSURE CONTROL, Step 1.
b.
Open one PRZ PORV until any of the following conditions satisfied Use ATTACHMENT 6 as reference Both of the following 1)
RCS pressure
- LESS THAN RUPTURED S/C(s) PRESSURE 2)
PRZ level
- GREATER THAN 1 7%[50%]
OR PRZ level
- GREATER THAN 71%[50%]
OR RCS subcooling based on core exit TCs
- LESS THAN 3OF[21O°F]
c.
Stop depressurization by closing PRZ c.
Close PORV block valve.
PD RV
ATTACHMENT TO L-2011-535 Turkey Point Questions 1-75 RO Questions76-100 SRO only Examination Answer Key December 14, 2011 1
D 26 B
51 D
76 B
2 A
27 A
52 A
77 A
3 B
28 B
53 B
78 A
4 D
29 B
54 A
79 C
5 A
30 D
55 B
80 A
6 A
31 D
56 C
81 B
7 B
32 B
57 C
82 A
8 C
33 C
58 C
83 A
9 C
34 C
59 B
84 B
10 C
35 B
60 A
85 B
11 A
36 C
61 AID 86 D
12 D
37 A
62 C
87 A
13 D
38 B
63 A
88 D
14 D
39 C
64 D
89 D
15 C
40 B
65 C
90 D
16 C
41 B
66 A
91 C
17 B
42 C
67 C
92 A
18 B
43 A
68 C
93 D
19 C
44 C
69 C
94 B
20 A
45 C
70 D
95 C
21 B
46 D
71 C
96 D
22 D
47 D
72 D
97 B
23 D
48 D
73 A
98 C
24 C
49 D
74 D
99 D
25 C
50 A
75 D
100 C