ML032590862
| ML032590862 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/09/2003 |
| From: | Roush K Susquehanna |
| To: | Caruso J NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-387/OL-03-301, 50-388/OL-03-301, PLA 005673 | |
| Download: ML032590862 (7) | |
Text
Susquehanna Learning Center 769 Salem Boulevard Berwick, PA 18603-0467 570-542-3353 September 9, 2003 Mr. John Caruso USNRC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-141 5 Susquehanna Learning Center Follow-up Post-Examination Comments PLA 005673 File A14-13D
Dear Mr. Caruso:
In our Post-Examination Materials letter to you, dated August 20,2003, (PLA 005667; File A14-13D), we requested a modification to the Written Examination Answer Key for Question Number 82, and supplied documentation for the requested modification in Attachment 1 to the letter.
After additional review of this question, we respectfully retract our request to modify the Written Examination Answer Key for Question Number 82. During the additional review, we concluded that the stem of the question is flawed. In that question, the given value for Wide range level is -146 inches, and that of the Fuel Zone is -93 inches. At the given reactor pressure of 50 psig, these two values should be nearly the same. Therefore, the stem of the question poses conditions that are not realistic.
Additionally, under the conditions stated in the stem of the question, two of the distractors are not plausible.
Based on the information provided by the additional review, we request Question Number 82 be deleted from the Written Examination.
If you have any questions or require more information, please contact me at 570-542-3326 or Rich Brooks at 570-542-1 891.
K. M. Roush Manager - Nuclear Training Response: No cc:
Ops Letter File Nuc Records - NUCPT rb post exam follow-up memo 1 KM R/RB/va h
Susquehanna Learning Center 769 Salem Boulevard Berwick, PA 18603-0467 570-542-3353 August 20, 2003 Mr. John Caruso U SN RC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Susq uehan na Learning Center Post Examination Materials PLA 005667 File A14-13D
Dear Mr. Caruso:
In accordance with the guidance provided in NUREG 1021, "Operating Licensing Examination Standards for Power Reactors" (Draft Revision 9) ES-501 "initial Post-Examination Activities", the following materials are submitted in support of the Susquehanna Initial Licensing Examination that concluded on August 15,2003.
- 1. The graded, ORIGINAL, written examinations.
- 2. Two clean copies of each Applicant's answer sheet.
- 3. The MASTER examination and answer key. (One change to the MASTER was necessary during the administration of the examination. See Question #82 typographical correction.)
- 4. All questions asked by the Applicants during the administration of the examination and the Proctor's responses to those questions.
- 5. The written examination seating chart.
- 6. Form ES-403-1 "Written Examination Grading Quality Checklist"
- 7. Requested modification to the Written Examination answer key (Question #82), with supporting documentation. (Attachment 1)
After the written examination was completed, an exam analysis was performed, and the Applicants participated in a review session to determine if enhancements to the questions were necessary.
Results of this analysis/review indicate several questions (Questions 28, 70,72, 81, 82, and 88) that should be enhanced prior to reuse. Additionally, four generic weaknesses (Questions missed by 50 percent or more of the Candidates) in the Training Program were identified with Questions 16,70, 71, and 91. Correction of the generic weaknesses and enhancement of these questions will be tracked by the Corrective Action Program.
August 20,2003 Page 2 PLA File A I 4-1 3D All individuals signed on to Form ES-201-3, 'I Examination Security Agreement", have not yet completed the post-examination signature. When Form ES-201-3, 'I Examination Security Agreement", has been completed, it will be forwarded to you, thus completing the necessary documentation for this Susquehanna Initial Licensing Examination.
If you have any questions, or require more information, please contact me at 570-542-3326 or Rich Brooks at 570-542-1891.
&k&&*
K. M. Roush Manager - Nuclear Training Response: No Enclosures cc:
Ops Letter File Nuc Records - NUCPT rb post exam memo RB/KMR/vah
Attachment I Facility Comments for Question #82 Comment:
The question presents a LOCA with RPV slowly trending downward and various additional plant conditions and then asks, Using ON-145-004 which Reactor level instrument would you instruct the operators to use as water level lowers. The answer key answer was D.
Wide Range. This was an open-book question, the students were given ON-145-004 RPV Water Level Anomaly to use for this question.
The given value, in the question, of -146 inches for the wide range can be extended to -147 inches using ON-145-004 RPV Water Level Anomaly Attachment C (Attachment 2 page 2). This would leave only 1 inch of useable level indication as water level continued to drop.
The question provided a value of -93 inches for the Fuel Zone. For the given RPV pressure of 50 PSlG (use the 100 psig graph for conservative level indication) and using Attachment D of ON-145-004 RPV Water Level Anomaly (Attachment 2 page 3) the Fuel Zone would be on scale at -93 inches and would extend down to -307 inches. This would leave 214 inches of useable level indication as water level continued to drop.
Based on this information, we consider the only correct answer to question #82 is B. Fuel Zone.
Attachment C Revision 8 Page 16 of 25 ON-145-004 TEMPERATURE AFFECT ON THE USABILITY OF RPV WATER LEVEL INSTRUMENTS RPV water level indication is affected by RPV pressure and instrument run temperatures. Figures 1 - 7 provide pressure and temperature limitations to be considered in determining whether level indication is "usable." Per EOP Caution #I, an RPV water level instrument may be usable when determined usable in accordance with ON-145-004, or it reads within the prescribed band.
Figure 1 is a saturation temperature curve. When temperatures near instrument runs are above Figure 1, flashing of water in the instrument runs will cause unreliable water level indication.
Figures 2 - 7 are graphs of indicated RPV water level vs temperature near the reference leg vertical runs. Below the curves, indicated level could be caused by off-calibration Drywell and Reactor Building temperatures which may result in on-scale indication even when water level is below the instrument tap.
The "prescribed band" of Caution # I is a result of simplifying information from Figures 2 - 7. The upper end of the "prescribed band" is the upper limit of the instrument indicator range. The lower end of the "prescribed band" is the "Minimum Indicated Level (MIL)." MIL is derived from Figures 2 - 7 assuming a maximum Drywell temperature of 350°F near the reference leg vertical runs (except for Fuel Zone which is assumed to be 100°F). 350°F is assumed because EO-100-103, Primary Containment Control, requires Rapid Depressurization before exceeding 340°F.
Instrument Narrow Range A (B) (C)
Wide Range A(B)-FIRE ON 749' Extended Range A Extended Range B Fuel Zone A Fuel Zone B Shutdown Range Upset Range
-NO FIRE ON 749' MIL 2.1
-126.8
-1 47
-88
-87.7
-304.3
-293.8 46.5 42.1 Caution I 2
-1 25
-1 45
-a5
-290*
50 45 Assumed DW temp 350 350 350 350 350 100 100 350 350 Limiting RB temp 350 350 21 2 350 350 350 350 350 350 Fuel Zone is calibrated for drywell temp of 212" F and is effected inversely by elevated Drywell temperatures.
Fuel Zone Indicated I
N C
,H E
S 0
F W
A T
E R
Attachment D Revision 8 Page 25 of 25 ON-145-004 ACTUAL RPV WATER LEVEL (INCHES) 0
-1lC
-12C
-13C
-14C
-is[
-16C
-17C
-18C
-19c
-zoo
-2 10
-220
-230
-240
-250
-260
-270
-280
-290
-300
-310 100
-93
- 189
-200
-211
-222
-232
-243
-254
-265 5
-284
-297
-307 200
-83
-95
-106
-117
-12e
-139
-150
-161
-173
-184
-195
-206
-217
-228
-239
-25 1
-262
-273
-284
-295
-306 300
-7 6
-88
-99
-111
-122
-134
-145
-157
-168
-180
-19 1
-203
-214
-226
-237
-249
-260
-272
-283
-295
-306 400
-70
-82
-93
-105
-117
-129
-141
-153
-164
-176
-188
-200
-212
-224
-235
-247
-259 a 2 7 1
-283 a295 a306 r e s 500
-64
-76
-88
-101
-113
-125
-137
-149
-161
-173
-186
-198
-210
-222
-234
-246
-258
-27 1
-282
-295
-307 re 60C -
-58
-7 1
-83
-96
-101
-12(
-13:
-14!
-15t
-17(
-18:
-19f
-20
-22C
-233
-245
-257
-270
-283
-295
-307 s5g) 700
-53
-66
-79
-9 1
-104
-117
-13C
-142
-155
-168
-181
-193
-206
-219
-232
-244
-257
-270
-283
-295
-3 08 800
-48
-61
-74
-87 7
-io0
-113
-126
-139
-152
-165
-178
-191
-204
-218
-23 1
-244
-257
-270
.283
-296
-309 900
-43
-56
-69
-83
-9 6
-1Q9
-123
-136
-150
-163
-176
-190
-203
-217
-230
-243
-257
.270
.284
.297
,310 I -
100C
.-37
-51
-64
-7%
-92
-106
-119
-133
-147
-160
-174
-188
-201
-215
-229
-243
-257
-270
-286
-297~
-311 LlOl
-32
-4f
-6C
-7'4
-8E
-10:
-ll
-13t
-144
-15
,172 I86
- 200 215 229 243 257 27 1 285 299 313 FORM ON-145-004-1, Rev. 2, Page 1 of 1 (File R16)
A W ~ c ~ n l l e ~ v t 1
p4j.e 3
ON-145-004 Revision 8 Page 8 of 2525 I
The below table lists calibration data.
NAME CALIBRATED Wide Range Narrow Range Upset Range Shutdown Range Extended Wide Range Fuel Zone 1035 psig in vessel, 135°F in Drywell Saturated, 1035 psig in vessel, 135°F in Drywell Saturated, 1035 psig in vessel, 135°F in Drywell 120°F water at 0 psig, 80°F in Drywell 1035 psig in vessel, 135°F in Drywell 0 psig in vessel, 212°F in Drywell, no jet pump flow