Text

Forwards Comments Concerning Written Exams for Reactor Operators & Senior Reactor Operators Given at Plant on 870824.Questions Appearing on Both Exams Have Been Addressed by Reactor Operator Exam Comments Only
	ML20236M893
Person / Time
Site:	Farley
Issue date:	09/01/1987
From:	Woodard J; ALABAMA POWER CO.
To:	Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20236M550	List: ML20236M548; ML20236M847; ML20236M893;
References
	FNP-87-0403-TRN, FNP-87-403-TRN, NUDOCS 8711130320
	Download: ML20236M893 (54)
	v • d • e

_- - - - .

3

' I 4 Alabama Power Company 1 J. M. Far!ey Nac;enr Plant .i e o orawer 470 _ ENCLOSURE 3 l A.,htord. Alabarna 36312 Teieanone 205 oms 15e u

Alabama Power i

FNP-87-0403-TRN September 1, 1987 i

The Regional Administrator., Region II l Nuclear Regulatory Commission 101 Marietta St., N.W.

Atlanta, GA 30323 ATTN: Mr. John F. Muriro, Chief Operator Licensing 53 ranch Enc'losed are Alabama Power Company's comments concerning the written examinations for reactor operator and senior reactor operator given at Farley Nuclear Plant on August 24, 1987.

Questions appearing or, both examinations have been addressed on the reactor operator exam ccmments only.

The courteous and professional manner which your staff displayed in preparing and administering this exam is appreciated.

For further clarification or discussion of these comments, pleaSe contact Mr. Lee Williams at (205) 899-5156, extension 6106.

Sincerely,

_ ($ ')%w'

d. D. Woodard //

General Manager -/Sarley Nuclear Plant JDW/LSW/RBW:mjk Enclosures 8711130320 871103 PDR t. DOCK 05000348 V PUR

.1

[~~~ 11.04/5.01 (1.00)

                   -QUESTION A reactor is shutdown with'a boron concentration-cf 1100 ppm'and a SDM of 2 percent delta K per'K. The. source range r.hannel indicates 10 cps.

The boron concentration is then reduced by 100 ppm. . Assuming a 0BW of'

                    -10 pcm/ ppm, choose the one answer that is' CLOSEST to the final Keff.

I a.) Keff = .980 L b.) Keff = .985 c.) Keff'= .990 ; d.) Keff = .995 ANSWER c.) REFERENCE ( ( NUS Nuclear Energy Training, Module 3, Reactor Operation y Unit 12.1 Learning Objective #1 . j 192003K102 192002K111 192002K114 192002K110 ..(KA's) 1 1 COMMENT J Key _ answer c.) assumes SDM is shutdown reactivity. SDM is'also an-abbreviation used to refer to " shutdown margin." Shutdown margin,.as defined by S.T.S., assumes the most reactive rod is stuck out. In this I l case, you must add the most reactive rod reactivity to the SDM.to l l determine actual shutdown reactivity. Using this value, answer a.).is l the correct response. RECOMMENDATION Accept either a.) or c.) as a correct response.

                                                                                               ;l I

i i Qi___--_____ - - - - .

f: ,. .

DE~$ NIT!0!is 1 1 l RkACTORTRI?SYSTEMRESPONSETIM~ l'.25 -The REACTOR TRI? SYSTEM RESPONSE TIME shall be the time interval' f rom when-the monitored parameter exceeds its trip setpoint at the.channbl-sensor until a loss of stationary gripper coil. voltage . l

                                                                                                                       'l j
           .REPORTAELE EVENT                                                                                1 ,

q l'.27 A REPORTABLE. EVENT shall be' any of those conditi,ons specifiedfin'Section j

S0.73 to 10CFR Part 50. SHUT 00WN MARGIN 1.28 SHUTDOWN MARGIN'shall be the instantaneous amountLof' reactivity by which? the .reac tor is subtritical or would be'subcritical- f rom :its present condition' assening.a11. fu11Liength rod cluster assemolies (shutdown:and; control) are fully inserted 1 except .for the single. rodL cluster.? assembly of . highest reactiv.ity. worth which is assumed to be fully withdrawn. SOLIDIFICATION 1.29 SOLIDIFICATION shall be the conversion of. radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immooili:ed solid with definite volune and shape, bounded by a stable surface of ~ distinct ' outline on all sides (free-standing) . , i 1 SOURCE CHECK i 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response- ( when the channel sensor i s exposed to a radioactive source.- 1 STAGGERED TEST BASIS 1.31 A STAGGERED TEST. BASIE shall consist of: 3

a. A test schedule for. n systems , sub systens ,. trains or. other design'ated components obtained by dividing :the scecified ' test interval into n. '

equal subinterval s,

b. The testing of one systen, subsystem, train or other designated q component at the oe; inning of eacn'subintervai . ;

I

              ~ ARLE'f-UN 7 1                           'l-6:                           ;At'ENDMENT WO. 57!

i

                                                                                                                          'f
                                                                                                                         't l_ _____z                                                                                                         j

I 1.15/5.16 (2.0/1.5). QUESTION State whether each of the following parameters would INCREASE, DECREASE, or REMAIN THE SAME if one main steam isolation valve closed with the plant at 50 percent load. Assume that control rods are.in manual and no reactor trip occurs, a) Affected loop cold' leg temperature , b) Affected loop's steam generator pressure c) Unaffected loop cold leg temperature d) Unaffected loop's hot leg temperature ANSWER ' 1 a) INCREASE (0.5) ; b) REMAIN THE SAME (0.5) -' c) DECREASES (0.5) d) REMAINS THE SAME (0.5) REFERENCE NUS, Nuclear Energy Training, Modules 2 and.3, Reactor Operation l l License Retraining Learning Objective #8 002020K508 ..(KA's) l l COMMENT For part b) of this question, since the affected loop cold leg temperature increases, and the main steam isolation valve is shut; the affected steam generator pressure must also increase. For part d) (on RO exam only), the assumption could be made that since t the unaffected loop cold leg temperature decretses, then steam generator pressure will also decrease. This would cause steam flow to decrease, which, in turn, would cause reactor power to decrease. This would cause the unaffected loop hot leg temperature to decrease also. RECOMMENDATION For part b) of this question, change the answer key to increase. l For part d) of this question, accept either remains the same or decrease as a correct response. l l l

                                                ~2'.14 (1.00) l~

QUESTION l Indicate whether'each of the following statements regarding RCP seals is TRUE or FALSE. a.) The floating seal ring, located between the ~ pump radial. bearing and the #1 seal, will limit RCS leakage to 50 gpm on a #1 seal-failure. 1 b.) If the #1 seal leakoff bypass valve is opened at normal operating pressure, the #1 seal will shut causing damage to the #2 seal because of a high dP across the seal. ANSWER I a.) TRUE (0.50) b.) FALSE (0.50) REFERENCE FNP.RCS - I 003000K602 ..(KA's) I COMMENT For part a.) of this question, the floating seal ring is located above I the runner in the #1 seal package itself, not between the lower radial-bearing and the number i seal as stated. RECOMMENDATION l Change answer key to false.

l l l l i-I*

1 REACTOR C0OLANT PUMP - MODEL 93AS l l A'

 !                                       UPPER GUIDE                                                                                    l d                                         BEARING                                                                                     4 FLYWNEEL ANTI REVERSE                      '\                                                  CCW SUPPLY                    l ROTATION DEVICE               -Q OIL LIFT PUMP UPPER BEARING            Y_ - -                 :.

CIL COOLER ^ ' 00 00 __ l KINGSB R HRUST # '

                                                    "00           00 ll                                                            S     ON
                                         @'h               ! l i

(@H-SERVICE WATER SUPPLY j j l: 8 AIR COOLER =- 8

                                                                                     ,    @_*SERVIC               AR
                                         @ ,1              . '                    .I s-CCW SUPPLY LOWER GUl0E BEARING
                                                       ={

NCCW RETURN

                                                          /L                          ___________________

V

                                                         %        r O                 SPOOL PIECE NO. 3 SEAL          g
                                                      =-

O O WASTE DISPOSAL SYSTEM MO. 2 SEAL

                                                    .q=-]O        C
                                                                          /

SEAL SECTION

- CVCS. SEAL RETURN NO. 1 SEAL ' (

                                                       -~                                 CVCS SEAL INJECTION                V RADIAL BEARING-             g                                       _,

g g p CCW SUPPLY A

THERMAL BARRIER / HEAT EXCHANGER 8 / 8n! o 6 [>c o c; - CCW RETURN REACTOR COOLANT 00T HYDRAUllC SECTION - i IMPELLER l l : 4 M y flEACTOR C00UNT IN A V J FIGURE 1

g 2.19 (1.00) QUESTION State the design feature of CVCS'for each of the following situations. a.) Prevents uncovery of the pressurizer heaters. b.) Allows for velocity reduction of-letdown flow and N-16 decay. c.) Provides for continuous degassing of RCS fluid.

d.) Allows for direction of excess letdown flow to the VCT when normal-letdown is not available. ANSWER ALL of the following at (0.25) each: a.) Auto closure of LTDN (and orifice) isolation valves, b.) LTON delay tanks (pipes) c.) Spraying of LTDN flow into VCT vapor space. d.) Excess LTDN divert valve REFERENCE FNP CVCS II-G Learning Objective #8 l 004000K407 004000K404 004000K401 ..(KA's) COMMENT For part d.) of this question, in order for excess letdown flow to be directed, a manual valve lineup must be performed if excess letdown is to be used for extended periods. Normally, excess intdown would be lined up to charging pump suction for short durations. RECOMMENDATION Accept either answer as a proper response. l i _m_______.. _ _ . _ _ . _ .__-- - - - - - - - ---

5

                                                                                                              !                              8
                                                                                                                                                          !                  h                    !

a 1- .; t a .. g d' dI d U M is! > i , a l_i _ _ M ini b X =! k-hN-r-- . s-i<*E -

                                                                                       !                   t

j % ; -

                               !L                    !i_              d               .

!r * - 2 i

                                                                          -*- 1
     !'                                           l           l_       X                   =      ~.      I                         afsi_f.~5 !_UX~

l,: ! = ' -

                                                  ,,          si' Q                                       j'+ M ~4 4
                                                  !             !                          o X*a             is ='T              aX i

ll' = l : 5 ! s e aoi l l

     '- 4u.._
          - _- - _ -.-q)---                       s, o                   g                   " @e                          g a p.
                                                                                                                         .-                                                                           1, ni do                               >4y         i                 , ce-h         _
                                                          =

g tj k y-c{

                                                                                                                                   !!!                                                           i)                       !
                 +1

1 ,

                                                                                               ..g_
                 *!                                                                                                  g!

p ' s!I/.

                                                                                                                          =         --

wS i

           -                 X                                                                                                                                                     .-

1 s . . n l l ws. !$-2

     .        !_                                i a

hj! 18' !~ ' j '6

                                                                                         !        e%                                         '
                                                                                                                                                              =,>M-                                !
                   =
                                                  ;u.y

w. w- - i. :.

i 3, T, d!%I%! ! !!'_. U i !

     ' -I T Y 4

I iit i

                                                                               -                  !f n k 8"            h 4

_. i _ l

                                                                                             .       t i

g [ _, _ si sil mil j ! si CHEMICAL AND VOLUME CONTROL SYSTEM FIGURE 3 '

                     - . . . - . . . . _ .              -                  -                                _          -                 ._-.----__..--...-_--.--.__.--_.-_.-.-__.a

2.20 (1.75) QUESTION EXPLAIN how the "RPI ROD AT BOTTOM" alarm operates (when it clears and alarms) during a reactor start-up to provide early detection of dropped or unmoving control rods. INCLUDE ALL APPLICABLE SETPOINTS. a ANSWER Alarm WILL annunciate (0.25) if any S/D bank rod is < 211 steps (0.25)' l or any CBA rod is < 6 steps (0.25). Alarm will NOT annunciate (0.25) unless any CBB control rod is >-12' steps'(0.25) or any CBC or CBD control rod is -> 6 steps (0.25) and a control rod remains at rod bottom (0.25). , REFERENCE l l FNP DRPI XF PG 13 Learning Objective #5 014000K406 ..(KA's) COMMENT l Answer key only reflects rod at bottom annunciator prevention only for bank B. Does not mention how bank C_or D rods are prevented from causing a rod at bottom annunciator. Key is incomLl ete. Refer to DRPI lesson plan X F, Fig.-7. RECOMMENDATION Change key to reflect how all rods are prevented from causing alarm. l 1 L____.____.____________________.__.___ . _ _ _ _ _ _

                                                                                                                         - J ANY I   ANy I   ANy )      ANY l    ANY l    ANW L   ANY I  ANY l      ANY l     ANY I  ANY I         ANY l               j SOA R00 108 R00 CB A R00   CBB R00 CBB R00   CBC R00 CB0R0D C B C 20'J CBC R00  C80 ROC CBD ROD    CBD R00                 l
  < 211   < 211    <s        s     <6        2 12       26     <6               2 12            ;

~~STEPS STEPS STEPS STEPS STEPS STEPS STEPS STEPS STEP $ STEPS STEPS STEPS i l n I k I I~~
~~~ \~~
RPI R00 AT BCTTOM AL ARM i R00 AT BOTTOM ALARM LOGIC FIGURE 7 __ _. __..___.m.m_ _ _ _ _
i 3.10 (1.50) QUESTION Answer TRUE or FALSE to each of the following statements concerning the AFW system. l l a.) The discharge valves may be completely shut after an autostart ONLY . after placing BOTH NORM / RESET handswitches in the RESET position. j i b.) The air operated isolation valves that admit steam to the TDAFWP ! must be LOCALLY operated if instrument air is lost. I c.) When the CST level decreases below the LO-LO level setpoint, the Service Water Intake valves will automatically open to provide a ; continuous water supply to the AFW pumps. { ANSWER a.) FALSE b.) FALSE l c.) FALSE j l REFERENCE FNP AWF PG 23,12,05 l 061000K404 061000A202 ..(KA's) l COMMENT For part a.) of the question, the discharge valves for the MDAFW and TDAFW can be completely shut in the mod position by the flow controllers following an autostart after placing both norm / reset handswitches to the i reset position. RECOMMENDATION Change answer key to true, i
3.12 (2.00) QUESTION Complete the following statement regarding the RHR System. (NOTE: Appropriate units should be included as part of the answer as necessary.) a.) The Loop "C" Inlet isolation valva can be opened when RCS pressure is g)_ as sensed by pressure transmitter 403 ano will autoclose if RCS pressere increases to (2) as sensed by pressure transmitter (3) . The Loop "A" Inlet isolation valve can be opened when RCS pressure is (4) as sensed by pressure transmitter 403 and will autoclose if RCS pressure increases to _ (E) _ as sensed by prescure transmitter _ (6) . b.) What is the purpose of this arrangement? ANSWER a.) ALL of the following: 1.) <402 psig (0.20); (0.05) 2.) 700 psig (0.20); (0.05) 3.) 402 (0.25) 4.) <402 psig (0.20); (0.05) 5.) 700 psig (0.20); (0.05) 6.) 403 b.) Prevents complete loss of overpressure protection (0.25) due to instrument failure. (0.25) REFERENCE FNP RHR II L Learning Objective #7 005000K407 ..(KA's) COMMENT Answer a.1) & a.4) is <402 psig. Actual setpoint is <402.5 psig. RECOMMENDATION Change answer key for a.1) & a.4) to 1402.5 psig on the examination key. l l l l u_ _ _ _ _ _ _ _ _ _ _ _ _ -
1 j of the RHRS and CVCS, depressurization of the RCS, or overflow and dilu-tion of the RWST. j (')i L 1 The interlocks operate as follows:
~~1. RHR suction valve 8701A (train A) cannot be opened unless . ;~~
A. RWST suction valve 8809A (train A) is shut. . B. Charging pump suction valve 8706A (train A) is shut. C. RCS pressure is less than 402.5 psig (PY-402 off RCS loop C). C. Pressurizer vapor space temperature less than 475*F (TE-454). l 2, RHR suction valve 8701B (train B) cannot be opened unless A. RWST suction valve 8809A (train A) is shut. B. Charging pump suction valve 8706A (train A) is shut. C. RCS pressure is less than 402.5 psig (PY-403 off RCS loop A).
~~3. RHR suction valve 8702A cannot be opened unless~~
( ) l C' A. RW9T suction valve 88098 (train B) is shut. B. Charging pump suction valve 8706B (train B) is shut. C. RCS pressure is less than 402.5 psig (PY-402 off RCS loop C). i l D. Pressurizer vapor space temperature less than 475'F (TE-454).
~~4. RHR suction valve 8702B cannot be opened unless A. RWST suction valve 88098 (train B) is shut.~~
B. Charging pump suction valve 8706B (train B) is shut. C. RCS pressure is less than 402.5 psig (PY-403 off RCS loop A). l RHR inlet isolation valves will automatically close if RCS pressure 1 exceeds 700 psig as indicated by PT-402(3). However, the same pressure transmitter that allowed the valve to open is not necessarily the same
~~; one used to shut it. If the pressure transmitters were cross-connected v~~
8 W.
d 1 3.18 (1.25) : QUESTION
]
~~Assuming the appropriate control switch is in AUTO, list ALL the signals that automatically reposition / shut each of the following valves l associated with the CVCS.~~
~~a. Orifice Isolation. valves l~~
~~) \~~
b.) VCT Outlet Isolation valves ANSWER ALL of the following at:(0.25) each: a.) Letdown Line Containment Isolation valves not fully open: LO Pressurizer level (< 15%) Containment Isolation Phase "A" signal present ("T" signal) b.) LO-LO VCT level (<57.) { Safety Injection cignal ("S" signal) { a REFERENCE { FNP CVCS 11 G Learning Objective #8 004010K403 004000K403 ..(KA's)
~~] .J COMMENT J~~
For the answer key for part b.) of this question,'the _RVST suctions to l the charging pumps must be fully open before the VCT outlet' suctions 1 will shut following either of the two signals stated in the key.
]
RECOMMENDATION 1 Change answer key for part b.) to reflect the RWST suctions required l being full oped prior to the VCT outlet suctions shutting on either of .l i the two signals stated in the answer. i N._._l-_--- .,_-------_l._--____-.-_ _ _ . - - . - - - . _ - . - - . ~ . . _
1 to-AUIO. In AUIO,.the valve will automatically. divert flow to the VCr-if either a high letdown temperature. occurs or high. inlet temperature to'- 'l the BTRS demineralizers cccurs. , I I
-)
VCr Level Control Valve (IOV-115A) (Figure 10) _ [ The MCB handswitch is a. three--position switch (V.C. TK/AUIO/H.U. i TK, raintain in each position). There are valve position ini1 cation. lights above the switch (red-to VCT, red-to. recycle holdup tank)
~~. . l I~~
With the switch in the V.C. TK position, the valve will direct all-flow to the VCr. In the H.U. TK position, . all flow will te directed to I j l . the recycle holdup tanks. In AUIO, the valve position will be determin- ) I ei by the VCr level controller and will acdulate acconiingly. In AUIO, ] d the valve will fully divert to the recycle holdup tanks when the VCT high level (81 percent) is reached, i l l VCr Outlet Isolation Valves (LCV-1150 and ILV-115E) (Figure 11) Each valve has a three-position handswitch (CIOSE/AUIO/OPEN, spring t return to AUIO) with associated valve position iniication lights.
~~'In .]~~
the AUIO position, the valves will' automatically close 'if '(1) a lo-lo . l level in the VCr occurs or a safety injection (S-signal) occurs, ani (2) ' L ILV-B ani D are fully open, ani (3) the valve is not fally open. 1 i RWST to Charging Pumo Valves (IOV-115B ani ICV-11SD) (Figure 12) Each isolation valve has .an associated .three-position switch. l (CIOSE/AUIO/OPEN, spring return to AUIO). - Valve position iniication lights are above the handsvitch. In AUIO, the valves will automatically l 48 ~! i l I i 1- .
a i i open if either (1) toth LT-112 and 115 sense a lo-lo level in the VLT or (2) a safety injection (S-signal) is present. Charging Suctlon Header Isolation Valves (8130A and B: 8131A ani B) ( Each of the four valves bas an associated three-position hardswitch (CLOSE/ Neutral /OPEN, spring return to Neutral). - Valve position l ini1 cation lights are above each switch. l , I Charging Punms A and C (Figure 13) j The' charging pumps ray be contro11ei remotely from .the MCB. or j i
~~- The remote control switch is ' a ' three-position locally at the ESP. 1 i~~
switch (SIOP/AUIO/STARI', sprirg return to' AUIO). The remote control' ] q switch is only operable when the selector switch on tba ESP is.-in the j PHK7IE position. Placing the switch momentarily in tra STARP position' vill start the pump if the lockout relay (86) is in the reset coniition. 1 In the AUIO position, the pump will automatically be started by (1) ' the ESF sequencer, if the B chargirg pump breaker associated with the delicatei pump is open, (2) the IDSP sequencer, or: (3) as a result of B chargirg pump trippdrg due to a fault. This arrangement precludes the-automatic startirg of all three charging pumps on a safety injection ani-yet provides an autoratic backup feature which v111 automatically' start the swirg pump in the operating train- on faults of tra .rtuming pump. Again, the 86 relay must be in the reset position. 'Thet pump . will automatically trip if either the sequencer load shMMng circuit or the 1 49 L
3.22 (1.25) QUESTION a.) State the consequence (s) that could be expected in the Rod Control l System DC Hold Cabinet if two (2) or more GROUPS of rod drive mechanisms, except for control bank "D", were placed on HOLD. b.) State the two (2) different DC voltages used in the DC Hold Cabinet and the usage of each. i ANSWER j a.) Overload (overheat) the cabinet. (0.25) b.) 125 VDC (0.25) - 1.atching rods (0.25) 4 70 VDC (0.25) - Holding rods (0.25) 1 REFERENCE FNP Rod Control System X E 001050G01 ..(KA's) j COMMENT l l For part a.) of this question, an_ overheating condition, could ultimately cause a dropped rod. RECOMMENDATION j l Accept the possibility of dropping a control rod as an acceptable answer for part a.) of this question. ] l l i 1
+
3.24 (1.50) QUESTION Explain why a Tcold failing HIGH would result in a greater rod speed signal than a Thot failing HIGH. l ANSWER A Tcold failed high would produce an Auctioneered High Tavg equal to Thot. (0.50) A That failed high would cause only a small increase in Auctioneered High Tavg. (0.50) The temperature error (generated by the Rod Control System) would be larger for a Tcold failure high than for a Thot failure high. (0.5) REFERENCE FNP R00 CONTROL SYSTEM X E Learning Objective #10 001000K403 ..(KA's) COMMENT While the temperature error for Tcold instrument failing high would be greater than a Thot failing high, both failures would produce a rod control temperature mismatch >5*F., which would demand maximum rod speed. RECOMMENDATION Since the assumption of the question is incorrect, delete this question from the exam.
.i : ~*
~~4.05 - (1.50) -- 1~~
~~- QUESTION Answer each of the following . situations. if temporary. revisions.to 2 operating procedures SHOULD or SHOULD.NOT be issued according to !~~
FNP-0-AP-16, Conduct of.0perations - Operations Group. -i a.) 'While performing-a. valve.line-up,.the procedure requires that the _ pump be running-prior to opening the associated:suctionLisolation valve. b.) During a. reactor St. art-up, it 'is necessary for the accumualtors 'to I
-remain isolated until'RCS pressure exceeds 2100 psig to allow for- .1 the completion of post inaintenance testing.. -j c.) Prior to beginning a plant cooldown using RHR. it is necessary ~to cross-connect both CCW trains with a temporary connection in: order ] "
~~to perform of surveillance testing on the'CCW pumps.~~
~~- ANSWER 4~~
~~a.) COULO b.) COULD N0T c.)' COULD~~
']
REFERENCE FNP-0-AP-16 pg 47 1 194001A01 . . (KA's) l i COMMENT The question asked if the operator.SHOULO or SHOULD NOT make a temporary -l revision to procedures. The plant conditions stated in item c.).would ! violate Technical Specifications by cross-connecting both CCW trains while in mode 4. RECOMMENDATION Answer key changed to could not . i r , __,_.___.__.m_m._ _ _ _ _ - - --m---
~~'i 4.9/7.14 (1.50)/1.50)~~
QUESTION List six (6) indications, other than radiation monitoring, that are ; symptoms of excessive RCS leakage according to FNP-1-A0P-1.0, Excessive ,l RCS Leakage, ANSWER ; ANY r,ix (6) of the following at.(0.25) each: 1.) Increase in charging flow requirements 2.) Pressurizer safety _ta11 pipe temperature high 3.) PORY tailpipe temperature high i 4.) Containment cooler drain level high l 5.) _PRT level high ; 6.) PRT Pressure high l 7.) PRT temperature high ' 8.) Containment humidity high REFERENCE FNP-1-A0P-1.0 i 000028A106 ..(KA's) COMMENT The largest revision to A0P-1.0 changed the symptoms as follows:
~~1. Increasing charging flow.~~
1
2. Decreasing VCT levei. 1 RECOMMENDATION Change answer key for this question to reflect the latest revision of- 1 AOP-1.0.
~~I l l~~
.j + l FNPal-AOP-lVOL FARLEY NUCLEAR PLANT * , UNIT 41 , {
~~ABNOR!iAL OPERATIN~~
~~G. PROCEDURE~~
~~AOP-l'.0, ~ ~~~
~~, EXCESSIVE'RCS. LEAKAGE e~~
~~L ) 1. 0 - . Purpose - 1~~
'J This procedure.previdestsymptoms, Automatic:Actibns, 1 Immediate-Operator Actions, and-Subsequent. operator Actions- , for a' reactor coolant system leakJsithin the capability;of .the charging 1 pumps toimain.tain pressurizer level. ,- 2.0 Symotems ! 1 l
2.1 Increasing charging flow, 1 J 2.2 Decreasing VCT level 3.0 Automatic Actions 3.1 Reactor makeup system. auto starts at 20% VCTclevel.--- 4.0 Immediate coerator Actions None. > 5.0 subsequent Ocerator Actions' () 5.1 verify.pressuriserblevel'is being-maintained:at programmed value, and adjust' rCV-122 as ;necessary to' stabilize pressurizer level. 'i 5.2 verify reactor makeup;in' automatic. Ir makeup ~to VCT. is not sufficient, THEN verify-charging pump suction
~
shifts-to the'RWST. ' 1 ;
~~' 5.3 Ir required to maintain pressurizer-levelnatjprogram value, THEN reduce letdown flow asinecessary.~~
5.4 Start additional' charging: pumps as-necessary to: maintain pressurizer level at program'value. ; 5.5 Using a CVCS flow. balance:with charging' flow, letdown flow,'and seal injection ~ determine.approximateLRCS leak rate. IT leak rateican not be1 determined-using-the CVCS fl'ow~ balance, THEN-performDRCSJ1eak test TNP-1-STP-9.0. 5.6 Ir-leakace rate is1creater than.that scecifiediin
-Yechnical Specifications, THEN begin;rampingJpoweri down to. minimum load per FNP-1-UCP-3.1Ein{preparati~cn for shutdown. -Refer to IIP's'for: appropriate: i y
~~emergency classification, .~~
"~
I G e n . 'R'e v .1-_ 3 1 L __ _-__=____-____ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ <. _ - -.
4.10/7.15 (1.25/1.5) QUESTION List FIVE (5) possible Main Control Board alarms that would indicate an inadvertent dillution while operating at 100% power. (Setpoints are NOT required.) ANSWER Any FIVE (5) at (0.25) each: 1.) Tavg/ Tref deviation alarm 2.) Overpower Rod Stop 3.) RCS High Delta-T 4.) OpdT Rod Stop 5.) RCS HIgh/ Low Tavg 6.) RIL low limit alarm 7.) RIL lo-lo limit alarm REFERENCE FNP-1-A0P-27.0 FNP-1-ARP-1.6 004020G08 ..(KA's) COMMENT Per ARP, the OTdT rod stop alarm could also be an annunciator that may be received with an inadvertent dilution at power due to increasing Tavg. RECOMMENDATION Accept OTdT rod stop alarm as an acceptable response to this question.
~~.m..~~
~~__ __ .. , . . . , . . . , u.~.~~
-~ u-= .....a.___.... . ..._.,........_.___;__. -mm + .-= "_m 2 _. 4.,. _ u. ._ ._. ,.
rNP-l e l.s I4X2TICN F34 SEDDINE: Variable at 3W 1asar thart Reactor Trip Setpoint,, (C-3) 119% nr=4nal _ - OVERTDIP. AT 1/3_for alacar < AITIO/ MANUAL 2/3: foe =*r==+4e actiotr "
~~. RCD STOP . . AND.~~
CEIGIN:1 W11==y Relar1-Tr412Cractuated WRBINE RUNBACK .. by overt ==parahire Ar Channel. . . 2 *14= y Relar 1-Tr422CK. actuated
~~. by overtamquerature AT. channel .T. H1i= y Relay 1-Tr432CX actuated . .~~
~~by Overtumparahtre AT Channel .~~
. e4 q \ . Pennanrr CAUSE ,
~~t i~~
~~.j 1 Overtumperature at condition resulting -~~
from: l a) --ine pressure. in Reactor Coolant System. - l ..
~~' c) b)itsemasive Incesasing FlSIt 7 ' Tilt. . ,~~
~~2; Instrument channal malfunction. ' 8 i~~
'~
~~AIFIanATIC ACTION - ('~~
~~\ - 1; As a single Channel. Alert,:None .~~
~~2. With 2/3 coincidence Automatic and. Manual- Rod Withdrawal l~~
1 Os is inhlhited.. 0 i IDIT. .
' i Automatic and Manual Rod Insertion - ==M14 ties still exist.
~~IMMEDIATE ACTICH e, -~~
1. PKNIIM ICOP OVERTEMPERAWRE AT SETPOINI AND TSLB-1 Cti -9 M MAIN CCNIBOL BOAltD. * '

2. IF 2/3 OVERTEMPERATURE AT CHAtWELS INDICATE HIE, THEN EBCREASE 'IURBINE IDAD UNTIL THE OVERTEMPERAWRE.
~~CENDITIM IS Cul:ARED.~~
~~'IHEN -~~
3. IF A 'IERPERAERE INSTRUMENT CHANNEL FAILURE EXIST h THE SNITCEES. DEFECTIVE CHA!WEL USING THE T* AND AT D
~~' 4. CIRRECT THE AXIAL FLUX TILT, IF IT IS EXCESSIVE.'~~
a) REFER 'IO THE TECHNICAL SPECIFICATI(ES CN PONER DISTRIBUTION LIMITS. (Continued on Page 2) Page 1 of 2 Revision 15 I ( d a g E_ ____L._._____.____________.________.._______ _ _ _ _
x_ ,. ,,. _ _ . ._ ,..,_ ,,,,,. _ ._. - . , , FNP-1-ARP-1. 6
~~-. i g (GMfruchge.1); IDCATICN F34 C '~~
( .s. t. snpPfMMPRmr ACTE}f - . [ r.,
. ~, , l 1 Etitifrm - ! ate personnel. to inilestigate . . - mut.carrect that cause; of: the- alarm. ,
2._Ir a failed:Rttris: indicated, THEN insure that T"- ani , lE==r4=c Imvel. Control returns to Normal when l~ ' Amenantic RetCentrol is. reinstated. - L andsets thatW cal Specifications.for LCQ r
..= . ) '. \
~~li i~~
\ + .,- , l i .\ . , ~ .. ..? I f~ .
J
~~) \~~
~~l 1 1~~
*\ l 1
~~l c,. .1 1 p~~
~~. 4 -~~
Befemnoas: A-177100, st. 289; U-260610; U-198768; D-177178; D-177398; D-177177; U-260387; U-260388; U-260389; PLS Document; Techn4em1 Specifications p ( Ptige 2.'of 2 Revision 14
~~\ _~~
~~h a g'~~
~~~w ,. s- , , . , . . , .~~
h_
~ 4
\
~~t 4.14/8.'09'(1.50/2.00): QUESTION !~~
~
State'the definition of the following terms per FNP-0-AP-14, Safety. Clearance and Tagging: a.) Tagging Official l 1 b.) Designated Operator 1 J l c.) Clearance 1 ANSWER a.) (SS, SF, P0, or) any individual authorized'by the Plant Manager- l , (0.25) to implement the tagging procedure and with whom.the final I responsibility of insuring the adequary of-lagging Oprations i Orders rests. (0.25) .) b.) Any individual authorized'by the Plant Manager to execute.. Tagging - Operations Orders. (0.50) ; c.) The formal authorization (0.25) to an individu'al or'a . j classification which.provides the individual'or persons working l under his supervision assurance that the' system or portion of a ._ system that he is working on has been isolated'to prevent personnel injury or equipment damage. (0.25) REFERENCE j FNP-0-AP-14 pg 2,3 Learning Objective #4 J 109001K102 ..(KA's) COMMENT For part b.) of this question,-a knowledgeable candidate may define designated oprator by position as delineated in AP-14. RECOMMENDATION Acceptthefollowingpositionsasanacceptableresponse[forpartb.):
1. Plant Operator.

2. System Operator.

3. Electrician. ,

4. Chemistry and Health Physics Technician.

5. Asst. C&HP Technician.

6. Instrument: Serviceman or any other individual authorized by the Plant Manager to ,
execute Tagging Operations Orders. ___,_m___..-_ _ _m.mm.m.m__mm.m__<_,__--_-m- mmm m
4 1 '
. . . .. I 4 j . .. FNP-0-AP-14" -
L-
~~/"C . ~3.5 All Tagging operations Orders /in effect.willibe !~~
T' ' maintained.in theLTagging. operations Notebook :( j except as required 'for placement .and removal j operations cn audit activities. - The Tagging 1 Operations Notebook will be maintained'in-the Control. Room.: s 3.6 Separate Tagging Operations order; notebooks will"- l U be maintained for . Unit 1 and Unit 2. ~ Tagging. operations orders that interface with both units. J
~~! .will be maintained in the Unit 1 notebook. m L~~
~~L 1~~
-3.7 . Each individual . (journeyman or above) .in charge j of:a task requiring clearance for safe execution V of work is responsible for obtaining such clearance priorito allowing work 1to commence. ' ,
a
-3.8 The switchyard shall be considered to include the unit power and .startup auxiliary transformers ] 'q and their.high side disconnect-switches. ;{
3.9 The-inplant. area shall be considered-to/ extend. to. but not include the unit power and startup: to auxiliary transformers. 3.10 Designation of Tagging Officials > and1 Designated. Operators will-be in writing.and will'be approved O by the~ Plant Manager. by. employee classification or by individuals. Copies of the designation will1be distributed to Designation may be made, holders of' controlled copies of this procedure 'l for attachment to their copies of this procedure. * ~
~~-3.11 When an activity requires"the t'agging of multiple - '~~
devices some of which are under the cognizance of the operations Superintendent and -the remainder , are under the cognizance of either the' Technicial . - Superintendent or Training Superintendent, only one Tagging Operations order will be prepared-by-the operations Group. ' 7
, 4.0 Definitions 4.1 Clearance - The formal authorization'to'an U ' individual (journeyman or above) or a classification' (foreman or. above) which provides ' the -individual or persons working under his supervision assurance j that the system or portion of a: system that he l is working on has.been isolated to prevent -
personnel injury or equipment damage. J 1 4.2 Tagging Operations Order - A form' used to 'specify-the sequence of tag placement and removal and to e document the -granting of clearance. (Figures'1 () & 2) _,d 2 Rev. 5 t _ _ _ __. _. _ . _ ._ _ _ _ __ _ _.- _-._ _ _ -.-.a _ _ _ _ - _ - _ _ _ _ - _ _ _ - _ _ _ - _ _ _ _ _ _ _ . . _ - _ _ _ _ _ _ _ _ - _. _= _ ____ =_ : _a
1 1
~~. .4 FNP-0-AP-14 .~~
i (\' i( ) 4.3 Tagging' Operations Notebook - A loose leaf notebook'of all outstanding: Tagging' Operations a ' l Orders ard Index Sheets. I 4.4 Hold Tags - safety tags which are placed on control points or devices to ensure personnel safety and equipment ' protection. l j Tags may'be- ; 1, placed on mechanical devices, such as a valve j to prohibit the operation of'the valve or - 4 placed.on electrical' control points, such as ; j circuit breakers, switches.600 Volt load center j I and 4160. Volt breaker cubicle' doors, etc., to 1
~~! ' prohibit the energizing of electrical circuits )~~
~~or the operation of other components.~~
J (Figure 3, 4, & 5) - j i j 4.5 Requestor - Individual requesting clearance.
, only those personnel in a journeyman or higher ; ; classification are authorized to request inplant j ! clearances. '
4.6 Designated Operator - The following~ employee classifications are designated as Designated i Operators: { a Plant Operator l
~~' Systems Operator.~~
~~(']/~~
~~\_ Electrician Chemistry and Health Physics Technician '~~
l Assistant C&HP Technician. I Instrument Serviceman or any individual authorized by the Plant Manager ~ to execute Tagging Operations Orders. Authorization may be for all inplant clearances or may be limited to the execution of Tagging Operations Orders on particular systems or in particular areas of the plant. 4.7 Tagging Official - The following employee classif-ications are designated as Tagging Officials: Shift Supervisor I Shift Foreman ' Plant Operator i or any individual authorized by the~ Plant Manager to implement the tagging procedure and with whom. the final responsibility for insuring _the adequacy of Tagging Operations Orders rests. 5.0 Switchyard clearances O' i All switchyard clearances will be made in accordance with the APCo Electric System Operating Procedure e -t Rev. 7 - '! 3
~~. _ _ _ . . __.-_.________m__~~
q
~~. l 4~~
4.19 (2.00) QUESTION l FNP-1-EEP-3, Steam Generator Tube Rupture, has the operator. verify that the atmospheric relief-valves are set at ^1035 psig and in AUTO.- Explain i why the atmospheric relief valves lift setpoint is INCREASED to 1035 psig. ANSWER l Less than the lift setpoint for the first S/G safety (0.50) to minimize challenges to the S/G safties (0.50). l Greater than no-load pressure (0.50) to minimize rad release from the' faulted S/G (0.50). REFERENCE Westinghouse ERG Background for SGTR 000038G12 ..(KA's) COMMENT This question could confuse a knowledgeable-individual for the following reasons:
1. Our relief valve setpoint is ns INCREASED to 1035, but is normally set to that value.

2. Justification of the setpoint value (1035) was not required by the answer key. However, the question could be read to provide a basis for the setpoint value.
In addition, the purpose of checking the relief valve is to minimize a I challenge to the code safeties. ' q RECOMMENDATION j Change the point value of the question to an amount. proportional to the correct response. Change the answer key response to minimize challenges i to the code safety valve. (See attached ERG Background document, page 1 59.) ' l __ . _ _ . __ _ _ _ - _ _ _ . _ . _- _.___._.__..__..__.__.____-.m_____._. ___m.____ 1____.__m____--.__m
i q
~~.j ,. STEP DESCRIPTION TABLE FOR E-3 (Cont) STEP 3~~
( ) 1 CONTROL /EOUIPMENT: c i o SG PORV and controller. l o Main steamline isolation and bypass valvet. ! o Steam supply valves to turbine-driven AFW pump. o Blowdown line isolation valves. o Plant specific valves between main steamline isolation valves and turbine
~~~ '~~
stop valves. o Isolation valves fq,r turbine-driven AFW pump. J pf p( KNCWLEDGE: ,i Y \ o The PORV on the ruptured steam generator should remain available to limit { steam generator pressure unless it fails open. This will minimize any challenges to the code safety valve. o Means of closing and isolating plant specific valve; between the main steamline isolation valve and turbine stop valve, such as steam dump { valves, Moisture Separator Reheater (MSR) valves, sample line valves, etc. These valves provide a backup means of isolating the ruptured steam generator if the associated main steamline isolation valve should fail. ., /3
~~i Q PLANT-SPECIFIC INFORMATION:~~
o Identify valves between main steamline isolation valve and turbine stop valves. o Actions for isolating the ruptured steam generator should consider any difference in the time delay between closing individual main steamline isolation valves (slow close) and closing all main steamline valves (fast . close). The benefit of steam dump to condenser must be weighed against the possibility of steam generator overfill due to a delay in stopping primary-to-secondary leakage. o (3) Plant specific setpoint for SG PORV controller (typically 25 psi below the lowest safety valve set pressure). This setpoint should be greater than no-load pressure in order to minimize atmospheric . releases from the ruptured steam generator and less than the minimum safety valve setpoint to prevent lifting of the code safety valves. The 25 psi margin is a typical value to allow for opening of the PORV l prior to lifting of the safety valve.
~~; 1~~
~~(. E-3 / ,' HP-Rev.1~~
~~- 0002V:lb ;, 59 N b '~~
j ' L-_ --- . .<
y-
~~<i 4.22'(1.25)~~
~~[f,~~
' QUESTION In GENERAL terms, describe the operator actions that are-taken to remove' failed power -range channel N-44 from service per FNP-1-A0P-18.0,-Nuclear Instrumentation Malfunction,_ including any features that are bypassed or 1
~~defeated.~~
~
I
,:e ANSWER y ALL of:th'e following at [0.25] each; o 1.)' Trip all histables associated with the. failed channel-2.) B' ass the rod stop-for the failed channel' - 3.) Defeat the : upper 'and lower comparator input i 4.) Defeat the'.comparator input l 5.) Defeat the input to the rod control system- j REFERENCF FNP-1-A09-18.0 015000K604 ..(KA's) i COMMENT In accordance with the latest revision of A0P-18.0, the step that i " defeat the input to the rod control: system",has been_ deleted. A
t. 'elowlecgeable operator may also mention pulling the control- power fuses, which trips?the bistables associated with the failed channe11(N-44). No j other bistables have to_be tripped. j RECOMMENDATION Delete response 5.) from the answer key and accept pulling the' control-power fuses of the failed channel'as a correct' response for tripping:the i bistables. (See item 5.2 of AOP 18, attached.)
~~t '1 o~~
~~. 1 ri s~~
t
~~.q b _n_ E __ _ _ ' ' ' -' ' ' '"~~
~~W, . . *- '~~
~~."._ -FNP-1-AOP.1870 .i < *: ,g ,~~
~~g 73 Immediate Operatbr Actions- '~~
~~, Nonel ;,~~
t
~~' 5. 4 subsequent? Operator Actions.~~
~~' . 'Q "i 5.4.1 -Ir rod' control.is:in automatic ~AND power-~~
~~" range channel N-441fa11s,.THEN place rods in'XANUAL. ?~~
~~5. 4. 2 l 1 Trip:all.bistables' associated-with the: n~~
~~]f~ ' failed chsnnel.byLeemoving-the control '~~
power 7f uses fromithe-;A' drawer for the . o .- L, ' failed channel, and;tipithefassociatsd-i bistables onaTableL1.. .
~~, 5.4.3 Turn th'eLcod stopLbypassiselector to.the position corresponding lto the1 failed i channel.~~
~~_ 5.4.4 Turn the;comparator. channel;defeati selector'to..the position'; corresponding to the failed' channel. .~~
~
~~5.4.5 Turn the upper and lower section selector-~~
~~-to'the: position corresponding.to-the failed channel. -~~
5.4.6 Refer to Technical Specifications'section-3.3.l~and 4.2.4.2Lfor: limiting; conditions; for operation. l I L th [3 Gen'. Rev. 9' '
~~7. (~~
~~4 > i < 1. C~~
~~.f '~~
__.l.m._--__i- _ - -
5.06 (1.00) i QUESTION Which one of the following will cause the Axial Flux Difference to become more positive (less negative)? a.) A power increase with power defect compensated for by dilution only. b.) A power increase with power defect compensated for by rod withdrawal only, c.) The buildup of xenon in the top cortion of the core. d.) The burnup of xenon in the bottom portion of the core. i ANSWER 4 a.) (1.0) l REFERENCE NUS, Nuclear Energy Training, Modules 2 and 3, Reactor Operation; Licensed Operator Retraining Cycle 4 Review Material 001000K506 192005K110 ..(KA's) COMMENT The key answer "a.)" is incorrect. Choice "b.)" is the correct response. The same question on the R0 exam (1.07) has choice "b.)" as the correct answer. REC 0MMENDATION i Change answer key for this question to b. i I l 1 l l l u__
7
. s. 3.4 ' \ ] - ~5.19-(1.00) ,
~~i QUESTION-s Name TWO effects of.. operating a motor-driven' centrifugal pumpiat or beyond a runcut condition.. ANSWER-Any two of't'he following (0.5 each)~~
1) Overload

2) Breaker trips ,
~~3)- Pump overheats '~~
4) Pump'. cavitates i

5) Pump efficiency decreases' j

i. REFERENCE I l
~~NUS, Nuclear Energy Training, Module 4, Plant Performance 191004K112 ..(KA's)~~
~~-COMMENT i~~
l It is assumed that items 1 and 2 -of the answer.are associated with the l motor or prime mover for.the pump. j s RECOMMENDATION < i Also accept as " effects," increased amperage,.beaping overheating, and motor windings overheating.- ' i f f IL L l f f 5 f 1
~~- .- .. -__._.n.__..--.- - - - - - - . ~ . . - M~~
. t 5.20 (2.50) I QUESTION The reactor is subcritical at 2500 cps when one of the steam dump valves suddenly fails open. Assume that the reactor is UNDERMODERATED, at BOL, no operator actions are allowed, and that no trip occurs. Explain HOW and VHY Tave AND reactor power change.
ANSWER l The extra steam flow causes Tave to decrease. (0.25) This inserts i positive reactivity. (0.25) Thus, power increases. (0.25) When power l reaches the P0AH, the increasing fuel temperature (0.25) begins to insert ' negative reactivity via the FTC. (0.25) This turns power gradually (0.25) until the power level stabilizes higher than the P0AH (0.25) Tave will be lower than its original value (0.25) by an amount sufficient to add enough positive reactivity (0.25) to counter the effects of the FTC. (0.25) REFERENCE NUS, Nuclear Energy Training, Module 3, Reactor Operation 192008K115 192008K114 192008K113 ..(KA's) l COMMENT I It is reasonable to assume that the positive reactivity added by Tavg , decreasing would not result in the reactor achieving criticality. In this i case, Tavg would decrease, adding positive reactivity, and power increases ; to a higher count rate. RECOMMENDATION Also accept as a correct response for full credit to the above question that Tavg will decrease, adding positive reactivity, and power increases to a higher count rate.
i
~~-5.21 (1.00) q QUESTION. I l~~
Of;the coefficients that compromise the power defect: 1 a.) Which one contributes most to the change of power. defect over core . life?. j b.) Which one reacts 'first to.a sudden power change due to rod movement? ANSWER q a.) MTC (0.5) b.) Fuel Temperature Coefficient (credit will be awarded for: -FTC, j Doppler) REFERENCE j NUS, Nuclear Energy Training, Modules 2 and 3, Reactor 0peration, Module-
~~~3, Unit 11.4, Objective 2; Unit 8, Objective 1 i 192004K103 192004K106 192004K108 ..(KA's)~~
~~COMMENT l~~
~~'j i~~
For Part b of this question, MTC changes'with rod movement. If this J assumed'by a knowledgeable individual then MTC can be an acceptable response. RECOMMENDATION j Accept MTC as an acceptable response als'o. 1
5.22-(1.50). QUESTION Answer each of the following:.
~~.a.).'If an_RTD element fails OPEN, what happens to indicated temperature?~~
~~b.) If an RTD fails due to a SHORT CIRCUIT, what happens to indicated" temperature?~~
~~l. c.) If a thermocouple fails OPEN, what.happans to indicated temperature? ;~~
i 'l l d.) .If a' thermocouple SHORT CIRCUITS in.its instrument well, what happens to indicated temperature?. e.) Which of the two temperature detection elements, RTD or thermocouple, has.the faster. response time? i f.) Which of the two temperature detection elements, RTD or thermocouple,. develops its own electrical output?' 1 ANSWER a.) indicated T fails high'(0.25) 4 b.) indicated T fails low (0.25) l c.) indicated T fails low (0.25) 1 d.) no change (0.25) e.) T/C (0.25) f.) T/C (0.25) ! REFERENCE OCONEE, OP-0C-IC-RCI 191002K114 191002K113 ...(KA's) , COMMENT l There is no reference in training materials used at FNP to indicate the response time of an RTD or thermocouple. Therefore, it is unreasonable-to believe the candidates woulc' provide the correct response to part e.) of this question. RECOMMENDATION Delete part'e.) and adjust point values accordingly. j l s
~~. _ . _ _ _ . . _ ..______m.___. .E _~~
~~.y '6.03 (2.00)- -QUESTION Answer each of the following statements,(concerning th'e AFW system,~TRUE- p or FALSE:~~
a.) TDAFP low: speed coincident with.an' auto start signal will-NOT result in a coninon alarm.on the MCB. i b.) The TDAFP and the MDAFPs.in Unit One have their miniflow flow control I valves failed open.
, y c.) A loss of instrument air will result in the fail-safe opening of-TDAFP steam supply valves 3235A or 3235B. 'I d.) Individual AFP discharge flow CAN NOT.be observed at the MCB when all 3 AFPs are running. ~l ANSWER a.) FALSE (0.50) b.) FALSE (0.50) c.) TRUE (0.50) .i d.) TRUE (0.50) /
I REFERENCE FNPS, Aux Feedwater System III I,-pages 10, 11, ' 12,.14, and :15 1 061000G007 061000G008 ..(KA's) k COMMENT ;
\
For part b of this question, on Unit I, the MDAFP and TDAFP miniflows are' ] failed open. Reference pages 10 and 12 of Auxiliary Feedwater System- l , lesson plan, OPS-52102H. I Loss-of-instrument air does not result in the " fail-safe opening" of the 1 l TDAFW pump steam supply valves (3235A or 3235B). There are-air reservoirs I installed to allow for continued operation of the valves following a loss-of-instrument air. However, once this source of air is exhausted, the valves will fail shut. Reference pages 3 and 13 of Auxiliary' Feedwater System lesson plan, OPS-52102H. RECOMMENDATION For part b of this question, change the answer key to true. , For part c of this question,. change the answer key to false. 1 i q t - _ = _ _ - _ - _ _ - . _ - - - - - - . - . - . -- -
two service water supply headers supplies the TDAFP. . This line also
~~/'N contains MOV-3216. These isolation valves are controlled from the 80P \ ,)~~
panel. Motor-Driven Auxiliary Feedwater Pumps Two motor-driven au< :ary feed pumps are used during startup, I shutdown, and emergencies when electrical power is available. Each ten-stage pump is rated at 350 gpm at a 1250 psi. MDAFP A and B receive power from 4160V buses F and G, respectively. l l Both pumps take a suction on a common header supplied by the con-densate storage tank, and each pump may be supplied individually by an associated service water line. The pumps discharge into a common line which has individual supply lines for each steam generator. { Each MDAFP has a miniflow line composed of two locked open isola-tion valves. a flow orifice, and a check valve. The Unit I miniflow line also contains an air-operated flow control valve. The flow control ) i valve for Unit I has been failed open to prevent valve oscillation dur- ' ing periods of low flow. i A bypass line around the mintflow line provides for system perfor-i mance and pump flow testing. The bypass line isolation valve is normal-ly locked closed. The miniflow and bypass lines return flow to the con-densate storage tank. I 1% x 10
1
.\
l
3. An ESF sequencer signal.

4. An LOSP sequencer signal.
(~} V Turbine-Driven Auxiliary Feedwater Pump. One TDAFP provides emergency feedwater flow to the steam generators if off-site power is unavailable. The seven-stage pump is rated at 700 gpm at a ,1250 psi. Main steam directly from the steam generator provides the power for the turbine. i h The condensate storage tank supplies the TDAFP through two locked open isolation valves and check valve. An alternate supply may be drawn from the service water system through two motor-operated isolation val-ves (MOV-3216 and either MOV-3209A or B) and a locked open manual isola-tion valve. The TDAFP, like the MDAFPs, has a miniflow line containing (,) a locked open isolation valve, check valve, flow orifice, and in the case of Unit I, a flow control valve (FCV-3218). This flow control val-ve has also been failed open to prevent valve oscillation during periods l l of low flow. A bypass line around the miniflow line provides for system { performance and pump flow testing. The bypass line isolation valve is normally locked closed. The miniflow and bypass lines return flow to l l the condensate storage tank. I i Pump Instrumentation. Flow instrument FISL-3218 provides a low flow alarm on both the MCB and the B0P panel at 80 gpm. A pump suc-tion pressure instrument (PT-32170) provides both local and MCB indica- l tion as well as a low suction pressure alarm on the MCB at 22.5 psig. (N Pressure instrument PT-3222 provides both local and MCB indication of L] 12 4
4. DETAILED DESCRIPTION g, Design Bases b The auxiliary feedwater system is designed to supply feedwater to the steam generator during plant start-up, cooldown, and emergency con-ditions when the normal supply is not available. The system contains two motor driven pumps and one turbine ' driven pump. Each of the motor driven pumps is . sized to supply the steam generators with 100% of the required feedwater flow for a. normal, safe ' cooldown of the reactor coolant system. The turbine driven. pump is-capable of providing 200% of the required feedwater flow for a normal, l safe cooldown of the reactor coolant system. In the event of a main feedwater line break and assuming the worst single active failure (loss of the turbine driven auxiliary feedwater pump), the two motor driven auxiliary feedwater pumps are required to provide sufficient flow to the-intact steam generators to achieve a safe shutdown of the plant. The auxiliary feedwater system design is' based on providing -suffi-cient flow te ;" event the loss of pressurizer vapor space.du' ring a feed-water lir.e break with loss of offsite power. The turbine driven pump is designed to operate with steam produced in the steam gener-ators and to deliver sufficient feedwater flow to safely cool down. the reactor cool-ant system. No AC power is required for -2 hours for operation of the i turbine driven auxiliary feedwater pump. Valves Q1N12V001A-A and 18-B have been provided with air reservoirs with sufficient capacity to open-the valves and allow turbine operation for 2 hours. ' O s V 3 4
pump discharge pressure. Pump bearing temperatures alarm on the Omni- [b guard panel in the main control room. V 1 Turbine Operation (Figure 3). Ccanections on the main steam lines from steam generators B and C supply steam to the TDAFP. Steam I i '
- flows through two parallel lines into a common line,which feeds the TDAFP. An air-operated isolation valve (3235A and B) located. in each line will admit steam to the TDAFP upon receiving a start signal. Each of the valves has an air reservoir associated with it.
1 The air reservoir ensures that on a loss-of-instrument air the res- l 4 pective isolation valve can be opened. The reservoir may be supplied f from either instrument air or the main steam atmospheric relief valve emergency air compressor. If instrument air pressure falls below 80 j (.% (/ psig, the solenoid-operated supply valve to the air reservoir will auto-matically close. The valve will automatically reopen when pressure re-i turns to 80 psig. A low pressure alarm for instrument air will sound on the MCB at 60 psig, l A0V-3235A and B normally are closed. However, a warming line keeps the supply piping at main steam temperature. The warming line isolation valves (HCV-3234A and B) close on a T-signal and can be controlled re- l 1 motely from the B0P panel. This supply of warming steam condenses in the steam header and as the level of condensate increases, LCV-3608 opens, draining the condensate to the aux 111ary steam condensate tank. b) v 13
in d
-1 i 6.08 (2.00) l . QUESTION 1 The train A RHR suction valve, 8701A, cannot be opened.unless FOUR interlocks are met. State the FOUR' interlocks. Include setpoints as' j applicable.
ANSWER 1; Train A RWST suction valve (8809A) isEshut. (0.5)'. . 2.. Train A char 0ing pump suction valve (8706A).is_ shut. (0.5) .
~~13. RCS pressure.(0.20) is.less than 402.5 psig (0.10) as sensed by the- '~~
~~transmitter on loop C.(PY-402) (0.20).~~
4. Pressurizer vapor space temperature (0.40) is less 'than 474 degrees:Ff (0.10). ;
REFERENCE ; FNPS, Residual Heat Removal System,_1IL, page 8 FNPS, Residual. Heat Removal System, 1986 Cycle 2, License Retraining,. Objective'3 005000K407 ..(KA's) l l COMMENT i Answer key for part 4 of responses states pressurizer vapor space - 'I temperature is less than 474*F. Setpoint is'actually 475'F. , RECOMMENDATION Change answer key to 47S'F. 1 ::
.i
_ = - - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - -_ : - _ - _ - - _ _ _ _ - _ - - _ - _ - - _ _ .
( r 3 a , e - c of -the RHRS' and CVCS, depressurf'zation of the: RCS, or ' overflow. and 'dilu-
~~' tion of the RWST.~~
~~The interlocks operate as' follows: 1~~
~~1. RHR suction valve 8701A;(train A) cannot be' opened unles,s-~~
~~'A. RWST suction valve 8809A (train A)'is shut.~~
B. Charging pump suction valve 8706A (train A) is shut. C. RCS pressure is less' than 402.5 psig '(PY-402 off RCS' loop'C). D. Pressurizer' vapor space ' temperature less than 475*F (TE-454). 2, RHR suction valve 87018 '(train B) cannot be' opened unless - A' . RWST suction val've 8809A (train A) is shut. B. Charging pump suction valve 8706A (train' A) is- shut'. C. RCS pressure is less than 402.5 psig'(PY-403 off RCS' loop A).
~~3. RHR suction valve 8702A cannot be opened;unless' A. RWST suction valve 88098 (train B) is shut. '~~
B. Charging ' pump suction valve' 8706B'(train B) is shut. C. RCS. pressure is 1.ess than 402.5Lpsig (PY-402 off RCS loop C). . , D. Pressurizer vapor space temperatu're less than 475'F-(TE-454).
~~4. RHR suction valve 87028 cannot be opened unless '~~
A. - RWST suction valve 8809B =(train B) is shut. B. Charging pump suction valve 8706B (train B)' is shut.. C. RCS pressure is less than 402.5 psig (PY-403 off RCS. loop A).. RHR inlet isolation valves will automatically close .if RCS pressure exceeds 700 psig as indicated by PT-402(3).
~
However, the same pressure-transmitter that allowed the valve to open is not necessarily the- same one used to shut it. If.the pressure transmitters were' cross-connected-8
355 E-t =. . .
~~= )~~
~~325- , .~~
- d. - .E ~;. i ~ ~;-
~~Tf&. p ,F----, , 1 A 1 ..:. ................. g~~
~~a e ...,~~
~~i................. :. .. w =.~~
.I - . *: = l . + .5Es= .
~~w. 3 <~~
~~g . e. .~~
~~.s a.~~
~~.i ' ,~~
l
=g .-.-1, 6--- E .. =. *.5 !...=
~~m g~~
~~= r =~~
8
= . . e-3 . . , . s
3
~~- .i a j (- (- g=~~
~~o (* -~~
~' '1 i
1
*____i - , . =- .C g- . s. .
~~ag =~~
~~w a. d a w 4~~
~~o o 8 ,,, d o a. s =. 4 l~~
. = .< ,- - ==-
m' 1 1 w%o l E 2 g . ,. . _ . . . . . . . . . _ _ _ _ _ _ .... .........._-.. g . Ef a f- _ _ . _ - - . ., .i 2 5 e I ) a _ - 1---. - - - - - - - - - _ - - - - - - - - - - - - -- I a e Eyyy5 4' i j**** ,.l...,
. l a -
~~I e i E g r ,A~~
* ; - a a ..... 4 u. " E s o 1
~~e is nl s.~~
~~- a 0 3 a~~
~~UEg~~
~
~~l i. I35 g . 833 2 I-~~
*w **w..*.* = == , -
~~2 2 3 ' 1 *1 8... .J~~
's: = p ; = g... a ===. e l ; g _r= -- . I
~~e. . .~~
a I s .' *.- .s .i .T 3 *
~~= ,i 4~~
~~1: aw s!.O ggME i e v~~
~~=si: - - i, -~~
i_ . . i ; i , i= ,
~~,m '~~
g
- :. . . - - - ., . , . _ _ _ _ _ g. - - . . . . .g.g _.. . 3 _ _ _ _ _ _ _' ( _ *l* !, g t.s Ei / - = .: , ,i ..________._.___._____._.__<.____2;, . - S_M, c.5' ,.T.._s e l 3, ,
ser a , 7T ., e .e. i ; e e, =a 4== i, i es -! =,
~~...; g : si g__, ' -= :3 s :~~
~~2 :. - -~~
= _ _{ l . ._-_ _ _-_ _.=___n _ \__.. ..J .e ...
~~e e .-- =~~
~ ., a , T , ._ _i,= .s . , ,E, . ( .... : _ _ == . ,_a_
~~m E g~~
~~E 5" .M C -*v~~
~~,;_ . .._ _i s: :E .- I:~~
5
~~. .~.~~~
~~5,. .~~
~~0 m s e :~~~
, 3: . .. T - == ,1. . =
~~Ivi: v,, -- ,1.~~
.T= r . . . _l s . , = --9 . _
l
= = = , * , =, : , , ,= ,, u . . - _ _1 1_. i _.
~~s _ n,. -~~
. = T T = = n =. -- = =w -5 l = =
~~e r ! a~~
- sa !! >- 2H !! . __'T ; .-a i , . .. i .= . .u :
~~tss. st~~
- =. n: - em .t cs'v) STEAM DUMP CONTROL FIGURE 3 ;
~~i :-)~~
., q 6.09(2.00)I ,
QUESTION' Containment' Cooler Fan A-has'been running in' fast' speed for ten minutes. :q Containment Cooler Fan B'is not running. The control switch for each fani 4 is'in the AUTO position and the LOCAL / REMOTE selector. switch for each fan 1 is in the REMOTE position. Answer EACH of the following' questions 1 independently.. a) State the.TWO fast speed auto-start signals.for Fan B. .) b) State the.TWO fast speed auto-trip signals for Fan A.
]
~~ANSWER i a) overload on Fan A (0.5) low d/p on Fan A (0.5) !~~
-b) bus UV (0.5) l SI signal (0.5) < -]
l REFERENCE l FPNS, Containment Spray and Cooling System, IIID', page 21' . l FNPS, Containment Spray and Cooling System, .0PS-52102C,1987 Cycle 3,.' ,
~~-l License Retraining, Objective 5 I l~~
022000G007 ..(KA's) COMMENT i For part b of this question, since an overload condition can start an auto ! fan, it can be implied that an overload condition must be a trip signal for the running fan. Also in L;cordance with ARP-1.2'(annunciator'801),1 > the fast speed breaker will trip on an overload of'the fast speed. fan. ' l l RECOMMENDATION Accept overload as an acceptable response. l l. L---.__----___.____--____..-..-_-___--.__-__.l.. - _ - - - - - - - . _ . . _ - - - . - _ _ _ _ - - _ __-_---..-_;-
~~-_. . - . - _ - - .l.__~~
~
b " t! ' U i' T - P D )S A R , T (} 0 T , . H S C TR - D
~~,I, I~~
U
. WO ,i E SF E DF . ' ! O ,
NO T A U P H L A A T S E C T P I LM U T . g O Y A O N F N M T U T E R P N A E E S S S O T F I U B D R A S v WE OE E K F ' LP SS A E R B S E S I S E R O T S O E E H E M C L L E P, R E R O S , o_ " K A O E W O R B C L O S IP M _ R T O R L T N F A C _ R E K E O L 0 A E M O A L R B N I R E D V N A E O A R] E T S O ~ O [C M N H C L E R UN A A D O CR T U S A S F E S C I O E O W S F RS L PT C F R D O L A O N A T T AL I T S HAC N] L I E D P R[ A A Y E S C O T F 8 R F E L I N V L D A F E R W C T ONI L D V E T O N
==m*
l 11
i
~~'l . i + '~~
~~t [ FNP-1-ARP-1.2' {l i i LOCATIt6 B01, CONTAINMENT , s SETPOINT: 1. Variable Current / Time COOLER !~~
2. Variable Current / Time 1A i

3. Vibration: 2.3+fmils FAN FAULT !

4. Press. Diff: 0.5 + { { inches H 2O (
~~ORIGIN: 1. High Speed Breaker EA10, Overload - j Aux. Relay 74. j~~
2. Low Speed Breaker ED15, Overload 1 Aux. Relay 74. j

3. Excess Vibration Relay (N1E12YSH3186A-N) ,

4. Diff. Press. Switch (NIE12PDSL3190A-A)
~~PROBABLE CAUSE~~
)
1. High or Low Speed Breaker tripped on overload. l

2. Excess fan vibration

3. Low differential pressure across fan 10 seconds after starting.
~~J AUTOMATIC ACTION l~~
~~1. Cooler Fan 1A low differential pressure or overload )~~
l on High Speed, starts Cooler Fan 1B on high speed, j i ) l
)
~~IMMEDIATE ACTION~~
~~1. STOP COOLER FAN 1A, E IT HAS NOT ALREADY l l~~
~~TRIPPED.~~
2. START ANOTIER FAN COOLER, H REQUIRED. l SUPPLEMENTARY ACTION *

1. Refer to FNP-1-SOP-12.1, CONTAINMENT AIR COOLING SYSTEM.

2. Notify appropriate personnel to locate and correct the cause of the alarm as soon as possible.

3. Refer to Technical Specifications, Sect. 3.6.2.3, for LCO Requirements.
~~References:~~
~~A-177100, Sh. 91; A-177048, Sh. 11 & 48;.B-175968, Pg. 26; D-177221; D-177222; D-175010, Sh. 1; B-175810, Sh. 10A, C & 102. Page 1 of 1 Revision 10~~
~~' *m : . ' 6.13L(2.00)-~~
~~QUESTION ,~~
~~- a); Indicate whether each of the.following situations:: ' ARMS ONLY,' ARMS'~~
.AND. ACTUATES, or.HAS'NO EFFECT on the: steam dump systsm.- - l'. ) .: 50% power, 18% step load INCREASE, Tavg is 6 F.LESS'than Tref, steam dumps are in the Tavg mode _of operation. I y
2.). ' 80% power, .7.5%/ min ramp DECREASE in turbine ' load for110 . minutes, Tavg is 7 F GREATER than Tref, steam dumps'are in the Tavg mode of_. operation. '
~~' 3. ') Hot Zero. Power, Tavg = 549 F / steam dumps are in .the Tavg mode-operation with 985 psig. set into the steam pressure controller.,~~
4.). Reactor trip,-.Tavg = 549 F, steam dumps'are.in the Tavg mode of , . p ' operation. ANSWER a.) 1.) HAS NO EFFECT (0.50)' 2.)' ARMS AND ACTUATES (0.50) 3.)' ARMS AND ACTUATES (0.50) 4.) ARMS AND ACTUATES (0.50)- u REFERENCE
~~.l FNPS, Steam Dump System, X J,' objectives 2, 5, 6, 8; '~~
~~041020K414 014020K409 041020K417 014020K411: 041020K105)~~
~~..(KA's)~~
COMMENT ' E I For part a.3 of the above question, it is~not-stated whether or.not~the-turbine is latched. Due to possible surveillance; testing,.the turbine may. be latched even at hot zero power;'.'If the. turbine'~is' latched and the' mode selector switch is in the Tavg mode, then there would be no effect'on the steam dumps. RECOMMENDATION 1 Accept either '" ARMS AND ACTUATES" or "HAS NO EFFECT" as a correct' response. ,
~~-j -_w-w-_- -wa----,----__-aa_a___.,-----_n.-- ,---1._-- -- -_s.. , - -- -~~
~~6,16 (2.00) i QUESTION' q The Post-LOCA Atmospheric Control-System consists of.four-(4). subsystems.~~
~
i One of these subsystems.is the' Post-LOCA Air Mixing System.. I a.) List the remaining three (3) subsystems. b.). How is the automatic start signal for the Post-LOCA Air Mixing fans reset? j I
~~1 ANSWER )~~
l a.) ALL.of the following at (0.50) each: I 1.) Hydrogen Recombiner System 2.) Post-Accident Containment Venting' System. 3.) Post-Accident Sampling System-(PASS) .
~~'i b.) ' Momentarily-(0.10) placing each (0.10) fan's switch (0.10).to the.~~
STOP position (0.20). REFERENCE l FNPS, Post-LOCA Atmospheric Control. System, III E, pages 1 and 15 028000G007 028000G004 029000K103 ..(KA's). l COMMENT For part a of this question, the hydrogen analyzers are.used to determine! lj hydrogen concentrations in containment following~an accident as described' j in the lesson plan under Post-Accident Sampling System. The post-accident' l sampling system is commonly referred to as the hydrogen analyzers L-u RECOMMENDATION Accept hydrogen analyzers as'an acceptable response'in lieu of post-accident sample system. i i
~~, l 1~~
L L __.._.____i.i..________ _____ _ __ _ _ _ - 'a
Post Accident Sampling System The sampling system will provide samples to determine representa-tive hydrogen concentrations inside the containment from at least two independent locations. Hydrogen analyzers provide continuous monitoring of the hydrogen concentration of the containment atmosphere following a LOCA. This system has the capability to provide grab samples. Post LOCA Air Mixing System A. The system design provides for maintenance-free operation for a period of 100 days following a loss-of-coolant accident. B. The active components are redundant and the electrical cables and instrument lines are separated so that no single failure can incapacitate the entire system. C. The active components receive power from separate power supply trains, and can be powered from an emergency power source (i.e. diesels) if necessary. General A. All systems rate as seismic category I systems, and are de-signed to sustain all normal loads as well as temperature and pressure transients from a design basis loss-of-coolant accident. B. The system components are protected from damage by missiles or jet impingement from broken pipes. I till i 5
~~~e o r .,,~~
i \ 7.12L(1.00) QUESTION-FNP-1-ESP-0.2, Natural. Circulation Cooldown To Prevent Reactor. Vessel: Head Steam Voiding, contains a statement on the foldout page that calls ~for'the operator:to monitor. " adverse containment criteria.! State' the criteria l . that constitute ADVERSE containment conditions. List'setpoints. 1 ANSWER Containment pressure (0.20) a't or > 4 psig-(0.20) l ORL (0.20) . Containment radiation'(0.20).at or > 10 E+05 R/hr.- (0.20)- REFERENCE. FNP-1-ESP-0.2 103000G015 103000G014 103000G010 103000A101 ..(KA's) COMMENT Answer key for the above question has containment radiation at or > 10' E+05 R/hr. Correct response should be > 1 E+05 R/hr. RECOMMENDATION Change answer key to the above question to > 1E+05 R/hr. l
],
I Cm _________m_____m_ -------_l-_.--.
m ~ s , . w +-b. z s. , -:.e a:r ~., .:y . . ..rm v. . ,&.w.www?; .s. .mnw.:m;. , c:9..r,:a., ,.g& gay ;,g,,4;weg, ::.s, man e.. . 3 1 FOLDCUT ftiE-FNP-1 STP-0 Meac*er Trip or Safaty injectien~ Revinien C '- Step. Action / Expected Response. -Response'NOT'Obtained- 1
~~.l l- -l .l_ 'l- - -l '~~
4 4 't & '&' & 1 Monitor RCP criteria. I 1.'1 CORE COOLDKi MCNITCR indicates .l.1 -IF at sleast.one charging greater than 28'r subcoolingl ' . pump running, THEN. trip, in T/C positien (88*T all RCPs.- subccoling in R'ID position). ,_ h 2 Monitor'SI criteria. 2.1- Greater than 28*F subcooled" 2.1 . Verify SI actuated. ~ l in T/C position (88'r L subcooled in RTD position) AND PRZR level above 7% TFO%}. 3 Monitor CSF red path criteria when directed. - 3.1 Nuclear power below 5%.- . 3.1 Go to FRP-S.1.' 1 3.2 Core exit TCs belcw 1200*F. 3.2 Go to FRP-C.1. . 3.3 Total F 4 flow above 377 gpm 3.3 Go.to FRP-H.1. CR at least cne SG narrow Tange level above 6% . (34%) . - 3.4 RCS cold leg temperature above 3.4. Go to FRP-P.1. 266*F CR ccoldown rate less ;i than llT0*F in last 60 minutes. 3.5 C'IMT pressure below 54 psig- 3.5 Go to FRP-Z.1. 4 Monitor switchover criteria. ' 4.1 CST level above icw level 4.1- Shift l Fd pumps suction alarm ( 5.3 ft) . to service water'per- ; SOP-22.O.- j
~~- t 5 Monitor charcine minificw criteria (durina SI).~~
5.1. RCS pressure belcw 1900 psig. 5.1 verify miniflow valves open. 5.2 RCS pressure above 1300 psig. 5.2 verify minificw valves; closed. 6 Mcnitor adverse containment criteria. 6.1 CTMT pressure < 4 psig 5 I 6.1 Use adverse CTMT conditien-AND radiation belcw 10 par . numbers ( }. 7 Mcnitor EIP-9 TAB 3 criteria.
? t t t .t-1 I l l I l-62/62:
q g.: , 8.06 (1.50) ' J QUESTION-J List the FIVE individuals, by title.- who~ report to the'. Technical: Support i Center.(TSC) following full activation _of-the TSC..
~
~~l ANSWER ,~~
~~.,. '1 All of the following at 0.3 point.each: ~~~
I 1 Emergency Director l Operations Director i Maintenance Manager l Technical Manager l l Health Physics Manager I
~~' REFERENCE 4 j~~
FNPS, 1987 License Retraining Objectives, Cycle 3, OPS-565,. item l' . COMMENT For the answer key on the above question, Operations Directo'r should be Operations Manager which is the correct position ' title. RECOMMENDATION ' Change the answer key for the above question'to Operations Manager. l l l i ! I
~~l. i~~
~~J EMERGENCY PLAN TRAINING ; OPS-565-~~
~~'1987 LICENSE RETRAINING OBJECTIVES -~~
CYCLE 3 . Unless otherwise stated, each of the following objectives should be accomplished without using referance materials and without error or omission. i l Acceptable performance of the objectives. stated below shall be dem- { 1 onstrated by passing either an oral or written examination in accordance with the 80% criteria.
~~1. State the five individuals, by title, who report to the technical support center (TSC) following full activation of the TSC (EIP-0).~~
~~ANSWER: Emergency director Operations manager Maintenance manager Technical manager Health physics manager. L 1 . k}}~~

ML20236M893

Text

G. PROCEDURE

References:

Navigation menu

Search