ML082680203
| ML082680203 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/24/2008 |
| From: | Duston S Florida Power & Light Co |
| To: | NRC/RGN-III |
| References | |
| 50-335/08-301, 50-389/08-301 | |
| Download: ML082680203 (8) | |
Text
POST-EXAM COMMENTS (Green Paper) s~ T L L-i <2 I I:::.
02-otJ8-- caD(
Licensee Submitted Post-Exam Comments
[vi Letter Attached With Comments
[
]
Comments Only - No Letter
[
]
Letter Stating "No Comments"
[
]
None
- I=PL August 6, 2008 Florida Power & Light Company, 6505 S. Ocean Dr., Jensen Beach, FL 34957 772-465-3550 Mr. Richard Baldwin USNRC Chief Examiner, Region II U. S. Nuclear Regulatory Commission 61 Forsyth Street, SW Suite 23T85 Atlanta, GA 30303-3415
Subject:
Operator Licensing Examinations Docket No. 50-335 & 50-389 License No. DPR-67 & NPF-16 St. Lucie Nuclear Station In accordance with Operator Licensing Examination Standards for Power Reactors, NUREG-I02l Rev. 9, Supplement 1, ES-402, ES-403 and ES-501, Florida Power & Light St. Lucie Nuclear Plant is submitting the HLC-18 NRC written examination package for grading.
As required by ES-501, enclosed in this package are the following items:
The Master SRO written examination (100 questions) and answer key (3 pages).
The applicant signed examination cover sheet and the applicants original answer sheet (9 total).
A clean copy of each applicant's answer sheet (9 total).
Five (5) pages of questions asked by applicants with proctor responses during the administration of the written examination.
The written examination seating chart.
Three (3) ES-501 Attachment I,-Facility Comments and NRC Resolution sheets, each signed by an authorized facility representative, and supporting reference material.
Written examination performance analysis.
If you have any questions concerning this examination package, please contact Mr. Joseph Milligan, Supervisor, Initial License Operator Training, at 772-467-7106 for resolution.
Sincerely,
")
-P..,----
uston J--
Tra ing Manager St. Lucie Nuclear Power Station an FPL Group company
ES-501 Question #65 St. Lucie Comments and NRC Resolution CO/lIllIe/II: The question asks for the actions to be performed wIlen 1B2 Circulating Water Pump (CWP) trips with IB1 CWP out of service The submitted answer is '~B" is based on Unit 1 Procedure 1-0620030, HCirculating Water System)" Subsequent Operator Actions, page 7, step 7~2. This question is recommended for acceptance oftwo answers as correct Tllis off-normal procedure also addresses maintaining differential temperature across the condenser < 32° F. Conditions provided in the question state Li T across the condenser is 31 0 F and discharge canal temperature is 1020 F.
Applicant 55-23238 submitted the following:
There lvere no trends providedfor this question. I assu111ed that the values given in the stenz o.fthe question )vere steady state values after the plant stabilizedJr0111 the transient induced b)J the Cf'T'ptanp trip. Anslver A is incorrect because the plant lvas above 30%
pOlver so the trip requireJnentfor backpressure is 5.5" Hg.
frfJ1en I looked at Ql1SlVer B, 1 read it as stating that a dOlvnpolver )-vas required in order 10 restore a CfVpUll1p. I salV no reason "Yvh)! ))OZllVOuld need to d01VnpOyVer in order 10 restart a efT!pli1np in this situatio111 so I ruled this anSlver out.
AnSll'er C is incorrect because the plant lvas less than the 2.5" Hg differential trip require111ent. That left lne selecting al1S1ver D - start a d01VnpO}Ver in order to reduce the load across the renlaining condenser and reduce DT less than 30 degrees. I ll'ould expect to have lnainlenQnCe inspect the tripped 1B2 CfV pU1J1p prior to restarting it or have the 1Bl CT'f'pll111p returned to service as soon as possible.
St.Lllcie positioll:
- 81. Lucie supports the following position:
In accordance witll Unit 1 ProCedtlre 1...0620030, HCirculating Water Systen1," page 5, the off normal entry conditions are:
e One or n10re Circulating Water Pumps Trips o
High differential ten1perattlre (>30° F ) as obtained from the Environmental System Panel (MET Panel) or conlputed on the RCO logs sheet Question #65 provides conditions that exceed the expected differential tenlperature across a condenser (31 0 F)" This is a valid entry condition into this off-normal operating procedure.. Operators at St. Lucie are trained to take actions to reduce tllrbine load when condenser differential telnperature exceeds 30° F.
Per Unit 1 Procedure 1-0620030, ~'CirCldating Water Systeln," page 13, the note for Step 9 states that the linlits for condenser differential tenlperature and canal discllarge ten1perature are not allowed to be exceeded UNLESS the following conditions exist:
o Condenser and/or Circulating Water Pump Inaintenance 8
Fouling of the Circulating Water Systen1 1
ES-501 St. Lucie Comments and NRC Resolution These two conditions do NOT apply for Question # 65. Therefore, the actions listed below for high condenser differential temperature are required to be performed.
Unit 1 Procedure 1-0620030, '~Circulating Water System," Subsequent Operator Actions, page 15, step 7.2.9.H states: "Control turbine power so that differential temperatures limits or discharge callal temperature limits are NOT exceeded". For this question, choice "D" is: "Begin a turbine/reactor shutdown until fj, T across the condenser is less than 30°F." Therefore, based on the above infonnation, it is recolnmended that BOTH "B" and "D" are accepted as correct answers.
St Lucie supports the recomnlendation to accept two answers, botll "B" and "D."
cf/13/0r Date #
NRC Reso[lltioJl:
2
ES-501 Question #70 St. Lucie Comments and NRC Resolution C0111111el1t: The question asks for a condition that could result in an inaccurate or invalid calculation ofRCS leakage wl1ile perfonning 2-0PS...01903, "ReS Inventory Balance."
This question is reconunended for acceptance oftwo answers as correct. The submitted answer is "C"*. However, choice "A" (50 gallons ofprimary water added to Charging pump suction) would result in a dilution of the ReS, changing Res tenlperature. As stated in Unit 2 procedure 2-0PS~.Ol.03, ~'Reactor Coolant System Inventory Balance,"
Section 2..2 Limitations, deviations fronl steady state conditions s110uld be avoided to ensure accuracy of the leak rate calculation.. Any of the following could result in inaccurate or invalid calculations:
Cllanges in ReS temperature Adjustments to Quencll Tank parameters Applicant 55-23238 subluitted tIle following:
I anslveredA for this question as I lvas certain thaI adding 50 gallons ofpriJnal)/ lvater to the reactor lvould invalidate an)) inventoJy balance that lvas being done at the ti111e and lVOllld cover up an)! potentia/leakage that nlG)J have been occurring. Ansyver B lvas incorrect because the charging pUJ11p seal tank level is accouJ1tedfor in the inventor)}
balance. AnSlver C see/ned like a potential correct anSlyer as a changing quench tank level could invalidate the calculation, but Iftlt that A lvas a Jnore correct anS1ver as it lJ10re directl)) qffected actual ReS inventolY. AnSlver D depicts a situation lvhere 110 inventoly is being lost - only recirced back to the T/CT.
St.Lllcie positioll:
St. Lucie supports the following position:
Vmu =Vrcs* In[(Concmu-ConcRCS~/(COnC111u-ConcRCSj)]
Vmu/Vrcs =In[(Concmu-COnCRCSl)/(COnC111U-ConcRCSj)]
e(VIJIIII fires) =[(COnC111U-COnCRCSl)/(COnC111,U-ConcRCSfJJ e(VlIIuIVres) = (ConcRCS~/ConcRCSfJ e(50/66,891) = (ConcRCS~/ConcRCSf) 1.000747764= (ConcRCS~/CO}1CRCSf)
C011CRCSj=ConcRCSi/I.000747764 The initial equation above is [roin the addendum to the Nomograpll whicll is attached. A siInilar equation is in the U2 Initial criticality following Refuelillg procedure 2-3200088, whicl1 is also attacl1ed..
3
ES-501 St. Lucie Comments and NRC Resolution Using the derived equation and the data from the Physic curve books supplied to the simulator, also attaclled, the following ReS temperature changes can be derived for BGe, at 200 EFPH and MOC, at 5000 EFPH.
DOC HFP Critical Boron Concentration from Figure C2 of the Physics curve 1134 ppm Cb ConcRCSf= 1134/ 1.000747764 = 1133.1527 = 1133.153 Delta Cb = 1134 -1133.153 =.847 Reactivity wOlih ofdelta Cb =.847 ppm
- 7.86 PCmJPPlll (fronl figure C.l for 200 EFPH) = 6.657 peln. This is a positive reactivity addition which must be offset by an equal negative reactivity addition to maintain the reactor critical.
Temperature worth ofpcm (assuming only telnperature and not power is changed) is as follows: to get a negative 6.657 pem tllen -6.657 pcm / (-8.8 pcm/op) (fron1 figure C.4 for 200 EFPH) =.756°F Moe HFP Critical Boron Concentration fron1 Figure C2 of the Physics curve for 5000 EFPH 678 ppm Cb ConcRCSf= 678 / 1.000747764 =677.493 Delta Cb = 678-677.493 =.507 Reactivity worth of delta Cb =.507 ppnl
- 8.33 pcnl/ppm (from figure C.l for 5000 EFPH) = 4.223 pern.. This is a positive reactivity addition which' must be offset by an equal negative reactivity addition to maintain the reactor critical.
Telnperature worth of pcm (assuming only tenlperature and 110t power is changed) is as follows: to get a negative 4.223 pcm~ tllen -4~223pcm / (-15.8 pcnll°F) (from figure C.4 for 5000 EFPH) =.267°F Per 2-0SP-O1.03, page 6, operators are required to record initial and final readings of Teold ina F, with a note tllat requires Tcold be maintained constant (+/- 0° F). At St.
Lucie, Tcold indications are n1easured and displayed in tenths of degrees..
Therefore, based on tIle above infoflnation, it is recommended that BOTH "A" and "C" are accepted as correct answers.
4
ES-SOl St. Lucie Comments and NRC Resolution St.Lucie supports the recommendation to accept two answers, both "A" and He."
NRC Resoilitioll:
5
ES-501 Question #95 St.. Lucie Comments and NRC Resolution COlllllle/ll: Tllis question aslcs for actions required to be taken once a*Secondary Chemistry Action Level 2 excursion occurs. Although no applicant submitted comnlents on this question~ the exanlination analysis determined that this question had a 44 %
success rate, with 4 of 5 applicants who n1issed this question selecting HA" as the correct answer.
St.Lllcie positioll:
- 81. Lucie supports the following:
Unit 1. procedure 1-0610030, "Secondary Cllenlistry - OffNormal," Section 5.3.6 Subsequent Actions, states that following a Level 2 excursion, excluding dissolved oxygen, consideration should be given to furtller reductions in power and a low power or hot soak to promote removal ofthe specific contanlinant from the 8/0. Tllerefore, based on the above infonnation, it is recomn1ended that BOTH "A" and "C'~ are accepted as con*ect answers.
f 1/3/rf Date NRC Resoilitioll:
6