ML20045D846
| ML20045D846 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/22/1993 |
| From: | Burdick T, Hansen J, Lennartz J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20045D845 | List: |
| References | |
| 50-282-OL-93-01, 50-282-OL-93-1, NUDOCS 9306300127 | |
| Download: ML20045D846 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-282/0L-93-01 Docket Nos.
50-282; 50-306 Licenses No. DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name:
Prairie Island Nuclear Generating Pl' ant Examination Administered At:
Prairie Island Training Center 1660 Wakonade Drive West Welch, MN 55089 Examination Conducted: May 24 - 26, 1993 Examiners:
Keith Parkinson, Sonalysts RIII Examiner: kn ju M,7 l,/R/93 Jay ' Mlartz Date/
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l Chief Examiner:
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.w, 2 M.12/G J y e p. Hansen-Date' Approved By:
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f Inotnas~ M. Burdick, Chief Dat~e Operator Licensing Section 2 Examination Summary Examination Administered on May 24 - May 26. 1993 (Recort No. 50-282/0L-93/01(DRS))
Three licensed Reactor Operators were given Senior Reactor Operator Upgrade
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examinations.
1 Results: All individuals passed the examination.
The following is a summary of the strengths and weaknesses noted during the performance of this examination.
(NOTE: The ability to identify generic or common strengths and weaknesses was limited due to the small sample size.)
9306300127 930623 PDR ADOCK 05000282 PDR:
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Examination Summary 2
t Strenaths:
o The training department provided good support during preparation and administration of the examinations. (For details see Sections #3a, 3d, l
and 4) o The plant's radiological cleanliness was good. (For details see Section #4a)
Weaknesses:
o There were no major weaknesses noted.
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2 REPORT DETAILS 1.
Examiners
- +J. L. Hansen, Chief Examiner, NRC, Region III J. Lennartz, Region RIII
- +K. L. Parkinson, Sonalysts 2.
Persons Contacted Facility
+M. Wadley, Plant Manager
+T. Amundson, Training Manager
+J. Sorensen, General Superintendent Operations
+W. Bell, Shift Supervisor j
+M. Hall, Operations Training
- +M. Lawrence, Operations Training
- +D. Reynolds, Operations Training
- +D. Smith, Operations Training
- +D. Westphal, Operations Training U. S. Nuclear Reaulatory Commission (NRC)
M. Dapas, Senior Resident Inspector R. Bywater, Resident Inspector
- Denotes those present at the Training Staff exit meeting on May 26, 1993.
+ Denotes those present at the Management exit meeting on-May 26, 1993.
3.
Initial License Trainina Proaram Observations The following information is provided for evaluation' by the licensee via l
their SAT based training program. No response is required.
a.
Written Examination l
Strenaths:
o The pre exam review was good as evidenced by the few post exam comments.
Weaknesses:
o The post examination review of the written examination by the NRC identified the following deficiencies in the candidates' knowledge. A majority of the candidates failed 3
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to provide the' correct response for each particular knowledge area identified.
e The NSP Lifetime Accumulated Dose-(LAD) limits.
(Question 007) e The position responsible for maintaining the Daily i
Order Book.
(Question 013) e The position responsible for assuring Shift Emergency Communications coverage.
(Question 014) e The final positions of valves following a loss of instrument air.
(Question 23)
The basis for not discharging the radioactive gas holdup tanks during unfavorable wind conditions.
(Question 36) e The reason for the location of the RHR pump suction piping connection to the RCS.
(Question 39) e The condition initiating a pressurizer low temperature, (Question 42) i e
The actions that must occur to restore availability of a 4160 volt source following breaker closure during an undervoltage condition. (Question 49) e The reason why immediate manual actions are~ directed during an uncontrolled withdrawal of control rods.
(Question 61) e The reason why operators are directed to check.
l containment fan cooling units running in safeguards l
mode during a response to high containment pressure.
(Question 81)
The primary reason natural circulation flow may stop
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e during a LOCA.
(Question 88) b.
Job Performance Measures (JPMs)
Strenaths/ Weaknesses-
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No strengths or weaknesses were observed in this category during this examination.
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c.
Administrative l
Strenoths/ Weaknesses:
o No strengths or weaknesses were observed in this category during this examination.
d.
Dynamic Simulator Scenarios Strenoths:
o Scenario validation went smoothly and input by the facility was helpful in final scenario development.
Weaknesses:
O The facility was given a set of data to trend during each of-three scenarios..The requested trends were only available on one of the scenarios due to equipment problems.
4.
Trainina. Operations. Security. Rad Protection Strenaths:
o The licensee's training.and operations staff-provided the NRC with good support and cooperation during the examination materials i
validation and examination administration. An adequate number of licensee representatives were available to support the examination i
process.
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The status of contamination control and' cleanup in the auxiliary i
building was good as evidenced by additional areas being l
accessible since the last exam.
l Weaknesses:
0 No weaknesses were observed in this category during this l
i examination.
5.
Simulator Observations l
Simulator discrepancies were identified. These discrepancies are noted in Enclosure 4.
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6.
Exit Meetina A preliminary exit meeting with the facil.ity training department was held at the Prairie Island Training Center on May 26, 1993,:'at 2:30 pm.
A final exit meeting with Prairie Island Nuclear Plant management was held at the same location at 3:00 pm on the same day.
Those attending the meetings are listed in Section 2 of this report. The. following items were discussed during the exit meeting:
o Strengths and weaknesses noted in this report.
o The general observations relating to the plant noted in Section 4.
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t FACILITY COMMENTS AND NRC RESOLUTION OF COMMENTS NOTE: The NRC independently made minor changes to the SRO written examination after facility pre-examination review. -These changes were made to ensure consistency in grammar, distractor length and development, and usage of terms and notations. The following questions were affected: 1, 48, 60, 66, 85, 95, 98.
00ESTION 60 ON THE SR0 EXAMINATION:
i While at 100% power steady state, a loss of offsite power occurred.
Which ONE [1]- of the following sets of parameters indicate that natural circulation exists:
- 1. RCS subcooling based on core exit T/Cs - GREATER THAN 20 degrees F.
- 2. RCS subcooling based on core exit T/Cs - GREATER THAN t
40 degrees F.
- 3. SG pressure - STABLE.
- 4. SG pressure - INCREASING.
- 5. RCS hot leg temperature - DECREASING.
- 6. RCS hot leg temperature - INCREASING.
- 7. Core exit T/Cs - STABLE.
- 8. Core exit T/Cs - DECREASING.
a.1,4,6,8.
b.2,3,5,8.
c.2,5,6,7.
d.1,3,5,7.
ANSWER:
d.
REFERENCE:
IES-0.1, Rev. 10 [10-3-91], Attachment A KA 000056K101
[3.7/4.2]
FACILITY COMMENT: The question asks which of the following indicates that natural circulation exists. Attachment A specifies greater than 20 degrees F subcooling.
Item 2. which is contained in answer b. is greater than 20 degrees F, making b. also v.
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correct. The question does not ask for a minimum subcooling value and if greater than 40 degrees, natural circulation could exist. Answer b. also meets the criteria for natural circulasion and should also be a correct answer.
(See Attachment A)
NRC RESOLUTION:
Concur with the facility comment and recomaendation.
The answer key for Question 60 was changed to b. or d. and credit was given for either b. or d. when grading Question 60.
OVESTION 95 ON THE SR0 EXAMINATION:
Which ONE [1] of the following statements describes the PURPOSE for an automatic transfer to standby sources in the event of a loss of power to D C busses 11 and 127
- a. To maintain control power to the generator output
- breaker,
- b. To maintain control power to the M to R transfer.
- c. To maintain control power for the RCP breaker trip.
- d. To prevent motoring the Unit I generator.
ANSWER:
c.
REFERENCE:
1 P8186L-005, Rev. 1, Page 16 KA 000058A201
[3.7/4.1)
FACILITY COMMENT: The question seeks the reason for an automatic transfer of D C control power on 4160 volt Susses 11 and 12, but is worded unclearly asking about loss of power to D C busses.
t The question stem should be reworded for future use as i
l follows:
D C control power for 4160 volt busses 11 and 12 has l
an automatic transfer to a standby source to:
This change was recommended during the pre-exam review.
i NRC RESOLUTION:
Concur with the facility comment as to the unclear wording of the question as used. The question stem will be reworded following the format guidance of NUREG/BR-0122, Rev. 5, Examiners' Handbook for Developino Operator Licensino Written Examinations prior to any future usage.
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SIMULATION FACILITY REPORT Facility:
Prairie Island Nuclear Generating Plant Docket Nos.
50-282; 50-306 Ogeratina Tests Administered On: May 25 and 26, 1993 The following documents observations made by the NRC examination team during the May, 1993, replacement examination. These observations do not constitute audit or inspection findings and are not, without further verification and-review, indicative of non-compliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION CV-31622, CNTMT Vacuum BKR During a LOCA with a loss of D C bus #11, Containment Vacuum Breaker Isolation Train B, CV-31622, indicated OPEN but the closed indication cycled off and on at about a one second interval. This continued until the termination of the scenario.
l CV-31089, 8 Atmos. Stm Relf During a steam line break in #11 SG steamline upstream the MSIV with #12 SG power operated relief valve (CV-31089) stuck open and indicating OPEN,-the closed indication cycled off and on at about a one second interval. This continued until the termination of the scenario.
DG/ Electrical Modeling The diesel generator and electrical modeling on the simulator panels does not currently match the main control room panels.
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