ML16166A106
| ML16166A106 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/13/2016 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| Download: ML16166A106 (21) | |
Text
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Catawba Nuclear Station would like to offer comments on the following 2016 NRC Written exam questions for review:
Question 17 Recommendation: Facility recommends that two correct answers (A and B) be accepted for this this question as both answers are correct based on conflicting information contained within a procedure note and the Operations governing document for EP/AP implementation.
Discussion:
1.
EPI1IA/5000IECA-1.1 (Loss of Emergency Coolant Recirculation) contains a note which states An invalid SPDS orange path may briefly exist between opening NS suction valve from sump and starting NS pump. FR-Z.1 should not be entered unless NS pump fails to start
- 2. The purpose of this note is to prevent a crew from needlessly transitioning to a CSF procedure while attempting to restore the ability to align for Cold Leg Recircu lation.
- 3. The signal generated is actually valid as the logic for this condition is met due to the alignment specified by this procedure (see attached logic diagram).
4.
OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) states that an SPDS signal is only invalid if caused by an instrument malfunction or computer related failure (see attached note). Since this document governs all Emergency and Abnormal Procedures, this guidance would apply to ECA-1.1.
- 5. Operations Department management has determined that the orange SPDS signal that is generated is technically VALID, however current wording of the note in ECA-1.1 states to consider it invalid. Ultimately the reason for the note is to ensure that an unnecessary transition to FR-Z.1 is not made. A procedure change request has been generated to modify this note (in ECA-1.1), to remove the term invalid, in order to eliminate the conflict discovered during this exam.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 17 as administered (A identified as correct answer)
Catabwa Nuclear Station ILTJo cS RO NRC fxa,,,inathi,,
Question:
17 it pointi Given the following conditions on Unit I:
The crew has entered EP/1/N5000)ECA-1 I (Loss of Emergency Coolant Recircutation) and is prepanng to initiate an NC system cooldown Pnmary chemistry has been instructed to sample the NC system for boron concentration The BOP is performing Enctosure 2 (Aligning NS for Recirculation)
NS suction valves from the containment sump are opened c
Containment CSF status turns ORANGE Per ECA-I 1.
The Containment CSF status (1) valid Boron sample results J2L required prior to beginning the cooldown Which ONE (I) of the following complete the statements above A
lisNOT 2
are NOT B
t.is 2
are NOT C
lisNOT
- 2. are D
iIS
- 2. are ir
Post Exam Comments 2016 CNS NRC WRITTEN EXAM ECA-1.1 Guidance CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO EPI1/A150001ECA-1.1 6of84 Revision 41 ACIION/IXP[CItU RESPONS[
[I]N[
NOt Verify criteria to align NS for recirc as follows:
a Verify both NS pumps
- orr b
Verify containment pressure
GREATER THAN 3 PSIG c
Verify at least one of the following annunciators
- LIT.
>33W OR
>3.3 ft a.
IF all the following conditons met
_* NS in service
. NS suction aligned to Containment Sump
. RN established to associated NS Hx.
- THEN GO TO Stop 8 b
Perform the following.
1) if AT,ffIiMcontainment pressure goes above 3 PSIG.
14 perform Step 1.
_2) iQStep8.
c.
Perform the following 1)
WHENatleastoneCONT SUMPLEVEL>33ft annunoator is LIT.
perform Step 7 2)
GOTOStep8.
NOTE An invalid SPDS orange path may briefly exist between opening NS suction valve frem sump and starting NS pump, FR-Z 1 should not be entered unless N$ pump fails to start d.
Align NS for wcirc REFER TO Enclosie 2 (Aligning NS fer Recirculation)
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Containment SPDS Orange Path Logic Flowpath L.
Is JITAjNUttfl
.iW. LEVEL LL T11At
\\ES CNS EPI 1 IN5tJOOIF-O CRITICAL SAFETY FUNCTION STATUS TREES CONTAINMENT-Page 1 of 1 (C)I()
FR Li 1I.3 FL.O j-5 1lICIHEL GOlD FR 7.1 a ii IAFJF
- Ht-
- u; LJ T.-aMFrr LE3 THAN H PIJ LS ZL rnMNtJT PRESSIJFE LE THAN 3 PRIG
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FR L2
- *J GO ID FR 13 NO OcoDcE) coIITAHIMEr RAEIATIORI HAlt I
3$PJKK ks (IMP (3A OR 13tH HVEROGCII NO LEECTHAjI
Post Exam Comments 2016 CNS NRC WRITTEN EXAM OMP 1-7 SPDS Guidance Opeiauous Management Procedure 1-7 Page 12 of 30 E.
Afier the CSF Status Trees have been ;mplerueuted the following rules of usage apply Use of EPs to restore a critical safety function is based on a two facto; puonty svsteui The fist facto; considers the relative unportance of the safety function in an accident scenailo On the OAC alasm video the otder of priority is established by position along the bottøm of the screen. SUBCRITICALITY at the left side of the screen has the highest pnorltv The others in decreasing pi*iority axe C ORE COOUNG HEAT SDK NC INTEGRITY.
C ONTAINMENT tinteeniv and NC INVENTORY on the right side of the scicen The second factoi considers the deetee of severity to which the critical safety function is being challenged The order ofptiontv is designated by color in decreasing ordet. as follows 1.
Red
- Extreme Challenge 2
Orange
- Sevete Challenge 3
Yellow
- OtT-Normal 4.
Green
- Satisfied NOTE:
An insmimem or computer related failine that causes an erroneous SPDS indication is the only example of an invalid CSF Status Tiee condition.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 28 Recommendation: Facility recommends that this question be removed from the exam as no correct answer to part 1 is listed.
Discussion:
1.
Part 1 of this question is technically correct concerning the loss of a Reactor Coolant Pump with no other plant transient in progress.
2.
With the given conditions, a Reactor trip will occur based on P-8 (Single Loop Loss of Flow Reactor Trip > 48%) resulting in a fluctuation of all SIG levels.
3.
Post exam simulator analysis revealed that the identified S/G level (1 C) would actually begin to shrink first and at a faster rate but not to a lower level when compared with other S/Gs (see attached SIG level trend).
4.
The question did not specify a detailed time frame for analysis. Initially is open to interpretation as the applicable SIG level varies considerably within a relatively short period of time (as compared to other SIG levels).
- 5. The listed answer is technically incorrect. The other available answer is also technically incorrect as SIG swell will not occur.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 28 as administered (A identified as correct answer)
Catabwa Nuclear Station IL T16 CNS RO ?sRC Exambwtio,t Question:
28 (1 pout)
Given the following conditions on Unit 1:
Unit is at 100% RTP Subsequently:
1C NC pump trips due to an operator error on the Main Control 8oani The crew verifies the reactor trips 1C Sf0 N!R level will initially (1) than the otherS/Os afterthe JC NC pump trips.
NC loop 1 C delta T would initially be (2) than the other NC loops delta Ts.
Which ONE (f)ot the following completes The statements above?
A.
- 1. shrink lower
- 2. lower
- 1. swell higher
- 2. lower C.
- 1. swell higher
- 2. higher D.
- 7. shrink lower
- 2. higher za of 75
Post Exam Comments 2016 CNS NRC WRITTEN EXAM S/G level trend following trip of 1 C NCP and resulting Reactor Trip Insight Trend 1I.p[ TI#..-
- nmn, Time Span (02:00)
Simulation time (07:20) a)
C 70 65 60 55 50 45 40 35 30 25 20 1A &1D S)G LEVEL lBS/C LEVEL 70 65 60 55 50 45
- 40 35 30
- 25 20 00:00 00:20 00:40 01:00 01:20 u,
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 50 Recommendation: Facility recommends that question 50 be deleted from the exam due to not having enough information in the stem of the question in order to answer it correctly.
Discussion:
- 1. The stem of the question states that battery 1 EBA is supplying AC vital bus 1 ERPA through inverter 1 EIA without a battery charger connected. Even though this would be the lineup if a battery charger were to fail, it does not provide a complete load profile for this battery.
I EBA would be supplying 1 EDA and Panelboard 1 EPA as well as other loads (see system drawing).
- 2. The question stem also states that only the voltage range of 125 VDC to 120 VDC is taken into account. Battery discharge tests in the plant suggest that the battery would only be in this voltage range for mere seconds (see I EBA discharge test data sheet).
3.
Due to the short duration of being in the specified voltage range and the unknown load profile for the specific battery listed, it is the opinion of CNS that there is not enough information to answer this question correctly and it should be deleted from the exam.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 50 as administered (D identified as correct answer)
Catabwa Nuclear Station IL fib NS RO NRC Examination Question:
50 (1 point)
Vital battery 1EBA is supplying IERPA through inverter 1EIA without a battery charger on line As battery terminal voltage decreases from 125 VDC to 120 VDC, battery current flow I) and battery discharge rate (2)
Which ONE (1) of the following correctly completes the statement above7 A
- 1. increases
- 2. decreases B
- 1. decreases
- 2. decreases C
1 decreases
- 2. increases D
I. increases
- 2. increases Page 50 of
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Battery 1EBA Discharge Test Data Sheet trnV=lOAmps Engineering Limits, Refer to SecUon 9.1 for Tech Spec Limits.
During ] 10 59 seconds of test, record lowest battery voltage observed. It isI necessary to record the actual time when the Iowet batLery voltage occurcd.
For Actual Discharge Current, a tolerance of ÷1.0 mV (or + 10.0 Amps) with rcspect to Required Discharge Current is allowed, However, tolerance should he kep to minimum if possible.
BAT[FRY _j.C34_____
EnclQsi.re 11.3 Battery Disch e Data Sheet WORK ORDER oa-.5B /
TEST START TIME Ip/O/A137 101010 Page 1 of 6 TECH SPEC/SLC BATFERY VOLTAGE. VDC ACTUAL I)AIL
. 2.I 5secocids Rf1QUlRI*D*
ACTUAI.**
DISCHARGE CIJRRFNT, rnV REQUIREDt 53.12-I Miiuii,
(
I, lb 9Mm 59 Sec.
lOMinulci, U6.c 9Mm 59 Sec.
It 20 Minuic (7.
fiflMinrites
)tl.
ID 90 Minutes ii a I I 115 Minutes
//
- j5. S 52.70 mV F 10.70 121) Miiure TEST END
,, 5a 2.71k
>2726nrV z3.ot 3$.3 38.IOmV 3Rga.
2.g 28.6%mV 1!.
28.68mV Z.
28.68 mV as.1i lt.
C, 4 28.66 mV
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Vital Instrumentation and Control System Drawinci EDS EBC DGBA
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 75 Recommendation: Facility recommends that the Exam Key be changed to list the correct answer as 0 (approved exam listed D as correct answer).
Discussion:
- 1. Several CNS procedures list the sound powered phone circuit power supply for each unit, but omit information concerning a permanent cross-tie installed per NSM 50307.
2.
Post exam review identified conflicting information concerning split versus cross-tied power supplies.
3.
CNS Engineering staff has verified that a previously installed modification tied sound powered phone circuits together ensuring availability from the opposite unit following a loss of one units essential B train power (see attached email and NSM).
4.
Per the listed conditions, the emergency sound power phone circuit will be available, via Unit 2 power supply. Answer D is technically incorrect. Answer C is technically correct.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 75 as administered (D identified as correct answer)
Catabwa Nuclear Station IL T16 CNS RO ?sRC fxa,nbwtion Question:
75 (1 point]
Given the following condthonson Unit 1:
16 DIG is tagged out The control room has been evacuated per API1IN55001O17 (Loss of Control Room) due to a tire lithe Auxiliary Building Following control room evacuation. a loss of offsite power occurred API17 requires a reactor operator to be dispatched to the (1)_to maintain Hot Standby conditions on Unit 1 The emergency sound powered phone circuit ___(2)___ be available for communications.
Which ONE (1) of the following completes the statements above?
A.
- 1. Auxiliary Shutdown Panels
- 2. will B.
- 1. Auxiliary Shutdown Panels
- 2. will NOT C.
- 1. Standby Shutdown Facility
- 2. will D.
I. Standby Shutdown Facility
- 2. wilt NOT Pe75of7
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 75
- CNS Engineering Response Miller, Rusty E From:
CobleIll. James Vt Sent:
Thursday, May 26: 2016 6:15 PM To:
ByrunoshO Cc:
Rudisill. Rudy Miller, Rusty E Subject RE: NRC 1LT2016 Question Aftathmenb:
NSM CN-50307.pdf The Unit 1 and Umt2 emergency sound-powered systems are cross tsed together.
The cross tie is depicted on CN-132 1-01 Rev. 3 reference drawtng Coordinates 5-St. The cross tie wes added as port ofbyNSM-5030 (Pertinent documents of the modification are anached). WO 003Sl73-01 documents the installation of the cross tie. WR604009 (associated WO is 00590S5 performed the tesn ofthe ne and2newlvinstalled soundpoweredjacksinthe OSCandTSC.
Per CNSD-l343-04M1 the emereencysouodccwered system is weredas follows:
Unit 1 Breaker Normal 2LA6 Breaker 25 Alternate 2ELBBrealri9 Unit 2 Breaker Normal 2LA6 Breaker 25 Alternate 2ELBBrealzrl9 The breakerpower ttes were further validated byreviewthe CN-13l9-02 and CN-l8l 9-03.
Questson 5 states the following conditions of the Station:
iBDGistaeeedout The control room has been evacuated per AP I A 5500 01 (Loss of Control Room) due to a fire us the AsniliasyBuildaig Following control room evscuauots. a loss of rffsste power occurred Since the Umt land Untt2 EmereencySound powered systems are tied together, power to the system renuins available as the system can get power from Untt 2 sources.
Additional Notes:
From. NSM-50507 theresa memo to flle dated Jima 26th, 1939 which states the need for this change on having a loss of offsite power event occurring and causing insufficient communications systems to be available between the ASP SSF and the TSC OSC dunne emergencses.
Thss 2Luso ts attached.
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Question 75 Reference (NSM 50307)
NUCLEAR STA11ON MODIFICATiON REQUEST Sf1 121F1 1446 lfl NSU &
IIJ+/-
lbwU (2)D.*crioIPITzi17 Th. th1tt 1.jd 1h1L 2
tK1OV iQWd pow.r.4 OhOna circidt.
_J.c1J1.ctvut. nct aHowina D.ool. it Unit 2 ph. 2acki to talk to i.onl.
ii tha Unlt 1
ObO?. Jack or th. 53!.
flip no *imid Dowr.d ihoni lack. ail.t 1n th., ThC!OC.
Iii fbi Ibilt I d Thttt 2 rt.ncv nod oow.r.d pln. rirno1t toi.Lhir and adA iound owerad thon. lack In thi TYC and OSt.
- 14) DøaW Fis**ty U S0.4 DOM (1..kgit MocDi? C] s No)
(4a)
Au(5(2M
- rdy) PItM By NIL Ds t4)i*w a*y)pp U/A (5) hi,.&it. Riipxscty-C NPDcr 2CI.
GA (6) AJie Erio..
t Scott HirtTh C
L,atIrs m Cs,y As-.d (I Uvv 16)
Urwy (ct*ck) U C Jn C (8) cavwwtm.ri D.si Cj.Vd To:
IW t9) Das DesaiL t Statai 1iI.n itt. 10-1-90 fj f_7 U. 2 No To.ujport 19 I non-niL&a t.pIntwt
%SUFtA Byfl is (Ii) Esti Cc*t ol Moilralxr $
EllsisB)r Ea1ws Ai1.f1 U U No
jIT) Pft4x.d SdiAM krw Cca 0g.
Sda By:
SdJi Afli.d U 0 No Ds
Post Exam Comments 2016 CNS NRC WRITTEN EXAM CATAWBA t41JCLXAR STAT1C1
)SM cN-S0307 FINAL SP DOCUENT PRO.3CT D!sCRIPT!c1 Tie the aergency Sound Power System !CH of Unit I to the !eergency Sound Power Syetefn (CH) of Unit 2.
and add sound power jacks in the TSC OCS.
PURPOS!
The Unit 1
& Unit 2 emergency sound power phone circuits system !CIfl were separate.
There are no sound power jacks in the TSC or OSC.
Petzonnal in one area cu1d not coefaunlcate with other areas.
The emergency sound power system (!CNI of Unit 1 is to be connected to Unit 2 and to the TSC and OcS.
!LZCTICAL Th. root cause of this NSN is the emergency Sound Power System CECIl) of UnIt 1 is separate frr Unit 2.
There ix not a sound power jack in the TSC or OCS.
The existing emergency sound power ]acks located at column T-U on elevation 568IO of the Service Building have been identified as lASP-3f tot Unit 1 jack L.kSP-JI fc.r Unit 2 jack.
A new Sound Power Jack 1ASP-JJ has been added in the TSC (Service Duilding) on !ievatf on 594+O at column T-26.
A new Sound Power Jack IASP-J4 has been added in the CSC Service Building) on !levatlcn 574+O at column U-)6.
TO connect the emergency sound sytcm of Unit 1 to Unit 2 a jumper tlSFrXl6a.i) has been added between jack L.SP-35 ad ZASP-J3.
Cable tIEII 564 hea been routed frcs jack I 1ASP-J5 to jack I
.1ASP-34 to tie OZC to system.
Cable
The Voltage in the ECH system ii 8.2 Volts DC, care must be taken to tnsre the polarities are properly connected.
This Is po,itlve to positive and negative to negative.
Design input documentation are per P8-101.
Related Modification
- None Assumit ions
- Hcne
çY1 !?WPaNM2iTM No involvement
Post Exam Comments 2016 CNS NRC WRITTEN EXAM Date november 2, L93 T. !. Crawford Superintendent at Integrated $chwdulinq Aftantioni JCU S.t..r D.
1..
Freeze Manager C)W Central Attentioni Jamal C. Blair Subj.ctt Catawba nuclear Station NSM CN 50307 Rev.
0 Tie Unit 1 and Unit 2 sergency Sound Powered Phone Circuit. Together.
File No.i CN-17S.0 it hac been delermflied by the Prolect. Group that no Irplementation Procedur. will be required for the referenced NSM.
Thi. modification tie. the unit I and unit 2 sound powered phone system together and uill add additional Jacks in the TSC and OSC. This work rs not eafety relatad and connecting th. bath unit. together will assist In plant activities.
rhi. modIfication involves no safety related syatea.Casimunjcat.jon Ia dLacussec in the FSAR (9..2 but this mcxliticatlon will not require any changes to the text.. There will not be any Technical Specification changes because of this nodllication.
The work order viii control the work and provide the information necessary for the installation ot thts modification.
There will be a functional teet required far this tn.tallatlon.tt will be don, by CUD end documented on th. work order Pleas. find attached a copy of the Documentation Checklist, the De.ign Completion Notice, and all associated Design Su.m.rle..
The Construction and Maintenance Department should iepi.ment this modification.
A start date may now be developed.
if thin, are any question., pl.ass contact th. IISH Accountable ngIn..r, John Adam., at extension 3026.
/3.C.
Adam.
VAccountable rngtn..r Attachments cci N.
1.. Cornwall C.
L. J.ne.n fl.
N.
Kieray C.
L. Th.rni.n J.
N.
Enuti
)5M File U.
1.. Turbyfill 1
Post Exam Comments 2016 CNS NRC WRITTEN EXAM h
Jun. 26 1989 i4 ()3O1 tHTRAsTATIC MEMO IJf H.
B. barron Duperint.ndert of Operations
v f-I
SUBJECT:
Sound PDwered Phone System During several Auxiliary Shutdown Panel/Standby Shutdown Facility Drill. held in 19S.9 for OperaUnna, a r.e.d to put sound powered phona ack.s in the TSC and OSC was identified.
Thu can be ecc1jshe4 in conjunction with your HSN 50307.
This HSII 1. written to cross connect Unit 1 and Unit 2
Mrgency Sound Powered Phone Systems.
This HEN I. to be activated f 99j ncn-oiitaq modificatfous.
Scott Martin of Project. will be sending the package to Design by 7-1-89 and we would like to add an additional SPI to initak; these jack. a. part of you.r NSN 50307.
We base this need on the possibility of having a lose of offilte power event occuxrjng and causing insufficient Ccw.ainjcaUong sy.tams to be available between the ASP/SEt and the TSC/Csc during energencie..
U. hav, seen ividce of this problem during several ASP/sst drills held this year.
We believe having the Sound powered phone system availble at these locations would solve thi.
problem.
We appreciate your consideration of thi. need and will be looking for your reply.
n SPE is attached for your approval and should be sent through the proc... If you agree.
If you have any questions please call me at 3236.
_1t(d.-_
R. Mic!am1 0 over Ccxepliance Manager GLLS\\keb:?t. GLM ttachment xci D. P. Simpson 0.
1.. Mitchell T. S. Martin I
Post Exam Comments 2016 CNS NRC WRITTEN EXAM 1
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Post Exam Comments 2016 CNS NRC OPERATING EXAM JPM F Recommendation: Facility recommends that step 7 be changed to remove the Critical Step designation.
Discussion:
1.
The as submitted JPM F (Shift Operating RC (Condenser Circulating Water)
Pumps by placing 1 D RC Pump in service and securing 1 B RC Pump) step 7 is labeled as a critical step.
2.
The purpose of securing the pump by closing its discharge valve is to prevent exposing the pump suction line from the discharge pressure of the remaining running pumps. In this case that would be RC pumps 1A, 1 C, and 1 D.
3.
If the step for closing the discharge valve were not performed and the 1 B RC pump were secured by just depressing the OFF pushbutton, then the discharge valve would automatically close in approximately 50 seconds. This would allow the discharge pressure of the remaining running pumps to be introduced to the suction of the 1 B RC pump for those 50 seconds.
- 4. According to the engineering department (Mike Classe Manager Nuclear Engineering), the maximum discharge pressure of any running pump would be from the 2C RC pump (-66 PSIG at an operating temperature of 105-110 degrees F).
- 5. The suction piping for this system is Pipe Spec 150.4 seen in the chart below.
For a conservative temperature of 200 degrees F, the maximum design pressure for the suction piping would be 215 PSIG. Therefore, having the suction piping subjected to design discharge pressure for a short duration of time is of no major consequence, and should therefore not be credited as a critical step. The critical part of securing 1 B RC pump is to depress the OFF pushbutton and verify the discharge valve is closed, and therefore step 8 of the JPM should remain the critical step.
SubTable No.:
PS-150..4 Approved for Fire Protection Duke Class:
E,FG.H Related Systems.
See Note 1-5 Generic Material:
Carbon Steel of Table 8.2.2 Maxium Design Conditions:
TEMP
(°F) 100 200 300 400 500 600 650 700 PRESS (psig) 215 215 210 18,0 150 130 120 110