ML20005G772

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Forwards Comments on Reactor Operator & Senior Reactor Operator Exams Administered on 891011
ML20005G772
Person / Time
Site: Oyster Creek
Issue date: 10/19/1989
From: Fitzpatrick E
GENERAL PUBLIC UTILITIES CORP.
To: Russell W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20005G764 List:
References
NUDOCS 9001230073
Download: ML20005G772 (72)
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Text

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- Forked River, New Jersey 087310388 3 . 809 971 4000 Wnter's Direct Dial Number; October'19, 1989 .] Mr. William T.' Russell, Administrator ~ (RegionJI; U.S.; Nuclear Regulatory Commission 475'Allendale Road. , King of Prussia,fPA.19406 Dear Mr.' Russell = ?

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Reactor Operator.(RO) and Senior Reactor Operator (SRO) s -Written Examination Comments I Er::losed with this ~ letter are GPUN ' comments on the RO and SRO exams administered.by ] the NRC on October 11', 1989. The comments are in the format' suggested by Examiner ' Standard 201 in NUREG 1021, Revision 5. g LIf there are any questions concerning these comments, please call Mr. Herbert Tritt, Loperator Training Supervisor at (609)971-4204. l Very truly yours, ) l l: E.E. Fitspa ick Vice President and Director Oyeter Creek c.. EEF/MH/$c Enclosure .cc: Mr..Sadanandan Pullani, Chief Examiner Operations Branch, Pivision of Reactor Safety L Region I l-U.S. Nuclear Regulatory Commission ) 475 Allendale Road King of Prussia, PA 19406 \\ 1 :' U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 1 NRC Resident Inspector Oyster Creek Nuclear Generating Station GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation 9001230073 900110 PDR ADOCK 05000219 V PDC . ~.

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Y .i 0 a ( r q EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (36%) 1 j / l QUESTION: 04 (2.50) EMG-3200.01, "RPV Control Power," directs you to reset Alternate Rod Insertion -(ARI) if reactor power is above 2% or,cannot be determined AND insert control l> rods with one of several methods. List FIVE (5) of these methods. J ANSWER: 04 (2.50) =1. de-energize scram solenoids L i 2. vent the scram air header 3. manually scram 4. open individual scram test switch f ~ 5. increase CRD cooling water differential e 6. drive control rode by increasing the CRD drive water differential pressure j 7. vent control rods drive over piston volume Any five (5) [+0.5) each

REFERENCE:

L

1. - OCNGS: SBEOPs, Lesson Plan 845.05, L.O. #I.A.

I 2. OCNGS: EMG-3200.01, "RPV Control Power," pp. 63 and 64. 3. KA Humbers 295015K201 (3.8), 295015K204 (4.0), and 295015K207 (3.3) 295015K201 295015K204 29515K207 ..(KA's) FACILITY COMMENT: There are multiple methods of de-energizing scram solenoids (given below) and each method should be accepted as a correct answer. Draft /TRITT 2.0

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) . (36%)~ t ~~open 100 amp breakers 7 (1) (2)' Pull!uses' t l(3)' operate subchannel test switches. 4 e 1 x FACILITY JUSTIFICATION - -EMG-3200.01, "RPV Control Power," pp. 63 and 64 P t' - = 3 9 C s i Draft /TRITT 3.0

J n t EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (36%) t QUESTION: 07 (1.50) For each of the action / conditions listed in Column I, SELECT the CORRECT reactor pressure setpoint from Column II. The responses given in Column II may be used once, more than once, or not at all. COLUMN I COLUMN II (Action / Conditions) (Setpoint) a. Reactor scram 1. 1020 poig b. ATWS trip for RR pump 2. 1030 poig c. opening setpoint for EMRV NR10BA 3. .1040 psig and D 4. 1050 psig d' opening setpoint for EMRV NR108B C and E 5. 1060 poig + e. reactor hi pressure alarm 6. 1070 psig 7, 1080 poig ANSWER: 07' (1.50) a. 4. b. 5 c. 5 d. 7 e.- 3 [+0.3) each

REFERENCE:

.1. .OCNGS: Lesson Plan 828.05, L.O. #I.C and 828.55, L.O. #I.B.2. 2. OCNGS: OPM, Modulo 05, p. 05-16. 3. OCNGS: -OPM, Module 55, Table 55-3. 4. KA Numbers 295025K201 (4.1) and 295025K204 (3.9). 295025K204 295025K201 ..(KA's) Draft /TRITT 4.0 1 I

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  • s EMERGENCY AND ABNORMAL PLANT EVOLUTIONS

~ (36%). ' FACILITY COMMENT: i For Part b, ATWS trip for RR Pump, should accept either 4 or 5 because the Tech. Spec. value is 1060 but the actual.is 1050 per standing Orders. . FACILITY. JUSTIFICATION: OCNGS Standing Order #1 ti l l l~ l t 1' l ll' j. Draft /TRITT 5.0 l l L:

~ 't 4 i .f 'f 3 Iie f i. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (364) ' QUESTION: 18 .(2.00). concerning the Reactor Building Heating and Ventilation (RBHVAC). System, STATE SIX (6) conditions and their setpoints which cause the Reactor Building supply i fans (SF-1-12, 13, and 14) to trip. (Time delays are not required.) j ANSWER: 18-(2.00): 1.. Rx Op. Floor high radiation - 70 tar /hr. or (B-9) l L '2. Fuel pool area high radiation - 70 mR/hr. or (C-9) l 3. RB ventilation exhaust high radiation - 13 mR/hr. 4. Lo-Lo water level - 86" TAF. or (90") 5. High DW pressure - 3.0#. or (3.5 psig) 6.- RB high pressure - 1" H O 2 4 7.J.Either V-28-21 or V-28-22 not full open. l. l 8. High temperature in ventilation. duct. L Any.six (6)L(+0.33) each

REFERENCE:

i l L 1. OCNGS: Lesson Plan 828.42, " Secondary Containment and SBGTS, L

p. 15, L.O. #I.F.

2.' KA Numbers 295032K202 (3.6) 295032K202 ..(KA's) l. l' l l i-Draft /TRITT 6.0 L':

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Should accept-2.9# for High D/W pressure per Standing Orders..
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FACILITY JUSTIFICATION '. OCNGS Standing Order #1. i 7 i 1 i V s Draft /TRITT 7.0 n.

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~... ~. ~ ls ' ~ '. r. t PLANT. SYSTEMS (51%) AND PLANT-WIDE GENERIC . RESPONSIBILITIES (13%) QUESTION: 02' (2.00) [ Column I lists the mode selections.available for Containment spray Mode selector Switch. Using the attached' drawing (Attachment I)'as a reference, MATCH the condition / valve arrangement listed under. -Column II with its associated Mode. fMOTE: -Valve arrangements / ' conditions' listed in Column II may be ussd once, more than once, or not et all. (2.0) COLUMN I COLUMN II (Mode). (Valve Arrangement) a. DYNAMIC TEST I 1. V-21-11 and -18 close, V-21-17 valve opens and places loop II b. AUTO I in the automatic Mode. c. AUTO II 2. V-21-1, -3, -5, and -15 close, l valves V-21-13 and V-6-27 open d. DYNAMIC TEST II and places' loop II in the automatic Mode. ll 3. V-21-5 and -15 close, valves L V-21-1, -3, and -13 open and l places loop I in the automatic Mode. 4. V-21-1, -3, -5, -7, -9 and -11 open, V-21-13, -14, -17 and -18 close, allowing containment spray pumps A & C to start automatically. 5. V-21-5, -15, and -13 close, valves V-21-11, and -18 and -17 open and places loop I in the automatic Mode. 6. V-21-7, -9, -11, and -18 close, valves V-21-17 and V-6-26 open and places loop II in the automatic Mode. l Draft /TRITT 9.0

j?: El 4 s 1 j + m i PIANT SYSTEMS'(51%):AND PLANT-WIDE GENERIC-1 RESPONSISILITIES'(134) .t n 1 ANSWER, 02 ', ( 2. 00 ) - r J a. 1-1 b. 4-l .- c. - 4 . d. 3 i (+.5)'each i i.

REFERENCE:

'l 1.'.OCNGS: Lesson, Plan 828.09,'L.O. #I.D. OPM' Modulo 09, pp 09-13 and 14, OPM 09, Fig. 9-1 2. OCNGS + 3. KA Numbers 219000A101 (4.0), 219000K402.(3.5). 219000A101 219000K402 ..(KA's) FACILITY COMMENTa~ - V-21-14 in answer No. 4 should be changed to V-21-15 to agree with drawing. No action required t FACILITY JUSTIFICATION: Exam drawing. Draft /TRITT 10.0

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o PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC i RESPONSIBILITIES (13%)_ w I QUESTION: 03..(1.50) r Y LWith the plant.in shutdown cooling, STATE three (3)-conditicas which will k result in automatic closure of the shutdown cooling system. inlet and outlet 't - valves. Setpoints'ARE required.- ANSWER: 03 (1.50) . 1. Low-Low reactor. water level (+0.25), +86 inches TAF [+0.25). 2.. Recirculation loop suction temperature [+0.25), greater than or equal to 350~deg F [+0.25). 3. High drywell pressure (+0.25), 3.5 psig (+0.25).

REFERENCE:

1 1.. OCNGS:. Lesson Plan 828.45, L.O. #I.E. 2. OCNGS: OPM, Module 45, pp 45-11 3. KA Numbers 205000K401 (3.4), 205000K402 (3.7), 205000K403 (3.8), it 1 205000K402 205000K401 205000K403 ..(KA's) FACILITY COMMENT: t L. Should accept 2.9# for High D/W pressure per Standing Orders. In addition to Tech. Spec. value at 3.5#, - FACILITY JUSTIFICATION: OCNGSt. Standing Order #1. i I l 1 l l: Draft /TRITT 11.0

g 'l l i l PLANT SYSTEMS (51%) AND PLANT-WIDE SENERIC l RESPOMsit! LIT!ss (134) j l J l QUESTION: 05 (3.00) { Answer the followirg questions concerning the Automatic ,Depressurisation system.(ADS). i l 4. STATE the conditions (four (4) required), including setpoints, for initiation of ADS. (2.0) j b. ALL ADS logic has been established, the timers still have 25 seconds before timing out, when EMRV NR108A opens due to high pressure. SELECT the one (1) response that correctly describes the response of the ADS system. (1.0) l i 1. NR108A is sealed open, the rest of the ads valves function' l normally. 2. NR108A cycles on pressure, ADS vlaves function normally. 3. NR108A and NR21088 seal open, the rest of the ADS valves function normally. 4. NR108A and NR2108D seal open, the rest of the ADS valves function normally. t ANSWER: 05 (3.00) a. 1. Nigh drywell pressure [+0.25) of 3.0 peig [+0.25). 2. Low-Low-Low water level [+0.25) of 63.5 inches TAP [+0.25). 3. Core spray Booster pump running [+0.25) of 50 paid [+0.25). 4. Times out [+0.25) 2 minutes [+0.25). b. 3. [+1.0) l nErERENcE 1. OCNOS: Lesson Plan 828.05, L.O. #I.C. 2. OCNGS: OPM, Modulo 05, pp 05-17 and 05-20. 3. KA Numbers 218000K403 (3.8) 210000K403 .. ( K.', ' s ) i l. l Draft /TRITT 12.0 ~

t i i I I i PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC RESPONSISILIIIES (13%) I FACILITY OOKMENT3: l a. Should accept 2.9# per Standing Orders or 3.5# per Tech. Spec. for High l D/W pressure. L Should accept 56" Tech. Spec. or 64.6" per Standing Order in addition to [ 63.5" which was used in previous questions. i b.. Should accept 4 also since NR108D opens at 1060 also and NR108B opening is a normal ADS function. FACILITY JUSTIFICATION: a. OCNGS: Standing Order #1. b. OCNGS: License and Technical Specifications c. OPM, Module 05 l I t f 9 I Draft /TRITT 13.0 + .-.n..... -n..

t i G EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (36%) l I ] QUESTION: 06 (2.00) l 1 Oyster Creek is operating at 904 power with the feedwater level control i system in three (3) element control when one of the steam flow transmitter l inputs fails to aero (0). Column I list various parameters that may be affected. _ Column II lists the steady state effect on the parameter due to the failure. For each parameter in Column I SELECT the final steady state i effect from Column II., The responses from Column ~12 may be used once, more than once, or not at all. (ASSUME no operator action.). f 1 / i COLUMN I COLUMN II (Parameters) (Steady State Effect)) a. reactor feed flow' 1. Increase b. reactor water level 2. Decrease t c. reactor power 3. Remain the same i d. reactor pressure i . ANSWER: 06 (2.00) a. 2 b. 2 c. 3 d. 3 l. l [+0.5) each

REFERENCE:

j 1. OCNGS: Lesson Plan 828.18, L.O. #1.F.b. 2. OCNOS: OPM, Module 18, p. 18-23. 3. KA Numbers 295009K202 (3.9) and 295009A202 (3.6). 295009K202 295009K202 ..(KA's) f l Draft /TRITT 14.0 1 I

Y i EMERGENCY AND ARNORMAL PLANT EVOLUTIONS (364) i. FACILITY COMMENT: Should accept either 2 or 3 for Reactor Poe r.(c) since there will be some decrease in power due to less inlet subcooling but may not be noticeable on l instrumentation. FACILITY JUSTIFICATION: 1. Lesson Plant 828.18, L.O. d!.F.b 2. OPM, Module 18, p. 18-23. l l Draft /TRITT 15.0 i_:

l i i PLANT SYSTEMS (514) AND PLhMT-NIDE GENERIC REsponsInILITIss (136) z J OutsTION: 11 (3.00) l Answer the following questions concerning the Zoolation condenser j system: l i i a. From the fo1*7 wing responses SELECT the ONE (1) response that contains the correct parameters and setpointo that will cause. l .an automatic initiation of the Isolation condenser system. (1.0) j f 1. Reactor Pressure 1050 or Reactor Level 86* TAF 2. Reac' tor Pressure 1060 or Reactor Level 86* TAF f I 3. Reactor Pressure 1050 or Reactor Level 63.5" TAF i 4.: Reactor Pressure 1060 or Reactor Level 63.5" TAF b. Once an initiation signal for the Isolation condenser system is present, how much of a time delay will exist before the system will begin to initiates (stLECT the correct answer). (1.0) t 1. .5 seconds 2.. 1 second 3. 1.5 seconds 4. 2 seconde c. During manual operation of the isolation condenser system, reactor cooldown rate is controlled by: (SELECT the correct answer). (1.0) 1. Cycling the isolation condenser steam supply valves. ~ 2. shutting recirculation loop discharge valves, throttling discharge bypass valve position. 3. Cycling AC condensate return valves. 4. Cycling DC condensate return valves. Draft /TRITT 16.0

m-l 1 l-5 PLANT SYSTEM & (51%) AND PLANT-WIDE GENERIC { n RESPONSIBILITIES (134) i ? - ANSWER: 11 (3.00) a. 2. [+1.0) l b., 3. [+1.0) + c. 4. [+1.0) l 7-1- i i

REFERENCE:

I 1. OCNGS: Lesson Plan 828.23, L.O. #I.C, I.E, and I.O. 2. OCNGS: OPM, Module 23, pp 23-18, 23-26, 23-27, and 23-40. 3. KA Numbers 207000K401 (4.3), 207000K509 (3.7) 207000K401 207000K509 ..(KA's) i FACILITY COMMENT ' a. Should accept either 1 or 2 since 1050# is the actual setpoint and 1060# is the Tech. Spec. setpoint, for high pressure Isolation Condenser initiation. I FACILITY JUSTIFICATION: OCNGS Standing Order #1. OCNGS License and Technical Specification i Draft /TRITT 17.0 l m

[ l i I I 1 PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC REsPoNSIsILITIEs (134) I 1 i QUESTION: 16 (1.00) ) l SELECT the Ol;E (1) response that CORRECTLY describes the results of i overcharging a Hydraulic. control Unit (HCU) nitrogan accumulator. (1.0) a. Control rod insertion speed is excessive during a scram.- f b. Accumulator will not provide motive force to insert control rod during a scram. c. HCU accumulator high pressure alarm is received. i d. CRDM may be damaged, during a scram, due to high differential pressure. i ' ANSWER: 16 (1.00) t b. [+1.0)

REFERENCE:

1. OCNGS: Lesson Plan 828.11, L.O. #I.J 2. OCNGS OPM, Module 11, pp 11-53 3. KA Numbers 201001A106 (3.4) 201001K106 ..(KA's) FACILITY COMMENT 4 Should accept either b or d because the GE Tech. Manual refers to possible CRDM damage in addition to loss of motive force. FACILITY JUSTIFICATION: GE 1-92807A CRDM Tech. Manual (page attached) Draft /TRITT 18.0

CEl 9207A - Check the cap on connectot P6 for leaksp; verify that the cap is tight. n. Fully close the isolation ulve (107) in the accumulator water drain line. o. Carefully open the eherging water riser isolation valve until the piston in the water accumulator compresses p. the gas eherp to double the vvae of the Nt procharge pressure determined in step i. above as shown on pressure indicator 131. I CAUTION 1 After approximately 2 minutes, recheek the pressure shown on j pressure indicator 131 and verify that it tomaine constant efter i the nitrogen has cooled. If, after this interval, prosaure onesods I the value recorded in step p., loosen the esp on connector P6 and blood excess pressure until pressure indicator 131 shows the pressure recorded in stop p. Excess soeumulater pressure could -l result in internal CRO de;;; in the event of a rammear meram. 316. PURGING AIR FROM WATER ACCUMULATOR l 317. The following procedure may be veed to purge air from the serem we,ter occumulator (125) prior to connecting the HCU to the CRDHS. With $e inlet and outllet serem volws open and all menuelisolation voim in the HCU closed, proceed as follows: Open the CRDHS vent velve in the line to the CRD under pieton port. e. I 4 b. Open the leolation valve (101) in the insert riser, With a technician observing the outlet of the CRDHS vont volve opened in stop e. above, carefully open the c. leolation volve (104) in the ecoling water riser. 6. When all air has vened through the CRDHS vent volve opened in step e., esose the wnt valve, e. Close the isolation volve (104) in the cooling water riser. f. Close the isolation velve (101) in the insert riser. 318. CLOSING SCRAM VALVES f 319. With all manuel leolation volves in the HCU eloemd, prossed as follows to oloes the inlet and outlet serem velves (126,127): a. Fully open the isolation volve (116) in the serem volve pilot air line. b. At the RPS operations and test panel in the sentrol room, oloes me appropriate toggio switch to apply power to the serem pilot air votes (117,118). Verify est the solenoids of volves 117 and 118 function normally,without chatter or abnormal bussint-c. d. Simultaneous with the performance of steps b. and c., observe the sum travel indiostors on the inlet and outlet screm volves and verify that ths velves are fully closed, j l ( in the sontrol room, verify that the SCRAM indication on the particular rod etetus display has extinguished e, (indicating that the position switches on the inlet and outlet serem volves are functioning proper'yl. l 36 '^ ~ -~ ' - ~ _. - -. _,

yrygprw-y c- ~ wyryng 3 a; a 1i t. i 4 1 r i i t h 1 -{ 3 n i ii 1 4 4 I 1[ t 4 8 FACILITY CONNENTS t CATEGORY $ f 1 i l 4 i i { tr s f n f 1 t I r 2 }. e ? e-c r e c Draft /TRITT 20.0 x A 3 1 L i h Ib d% N N N%4a%g%ay jy, ,4 y p .q. 7

.E pgammmer AMD &ananMhL P1 ANT EVOLUTIONS l l I i i QUEST!018 5.01 "(3.00) l MATCN the immediate effect of a total loss of instrument air during pcmer j operations on the-following valves:- t- { VALVES .MFFECT 1. feedwater control valves a. fail as-is I -(1D11A, 1D113, 1D11C) (0.5) l '2. CRD flow control valves b. fail open f (V-15-128, V-15-129) (0.5) 13. etandby gas treatment inlet _ (0.5) c. fail closed and outlet valves (V-28-23), 26; 27, and 30) i 4. offgas inlet to SJAE _ (0.5) d. no effect (V-7-17 through V-7-28) (i.e. no failure) 5.- offgas valve from condenser _ (0.5) i (V-7-1 through V-7-6) 6. reactor building vacuum _ (0.5) breaker valves-(V-28-16, V-28-18) ANSWER 5.01 (3.00) (O.5 each) l '. a l 2. c 3. a 4. b 5.' c ~ 6. a REFERENCE 1. Oyster Creeks 2000-ABN-3200.35, TABLE 1 2. Oyster Creek TCR 828.43, Behavioral Imarning objective K. KA 295019AK201(3.9) 295019AK203(3.3) 295019AK212(3.4) 295019AK206(2.9) 295019AK209(3.3) 295019K212 295019K209 295019K206 295019K203 295019K201 ..(KA's) ' Draft /TRITT 21.0 ~.

j ' FACILITY 000BIENTs <::e: ~ i r For.the Reactor Bu11 ding.V cuum Bre;ker_V21ve3,-.(6.} chould CT**Pt o or b cince ] .tho' valves do'have accumulators, but the ABN-3200.35 states that the valves , fall open. j ts l FACILITY JUSTIFICATION: ABN-3200.35, ' Loss of-Instrument Air *, Table 1. ] 1 ) i J I p: j; -] i i ) i i i l l 1 u l~ t i l Draft /TRITT 22.0 l l-i 9,

i,, - punnamner ano annonMhL PLhnT EVOLMIonS QUESTION 5.03 (3.00) The plant is at 2004 power when a total loss of 125 VDC power occurs. .For each of the components listed below, MATCH the correct consequence. COMPONENTS-CONSEQUENCES 1. Shutdown Cooling System ___ (0.5) a. Loss of position DC isolation valves indication only 2. Main Steam Isolation valves ___ (0.5) b. Loss of position indication and reset capability only 3. Isolation Condenser (0.5) c. Loss of position DC isolation valves indication, reset capability and control L power 4. 4160V and 460V breakers ___ (0.5) d. Loss of control power ^ and reset capability only 5. EMRVs (0.5) e. Loss of control power only 6. Drywell isolation valves (0.5) f. Loss of reset capability only g. Loss of position i indication and control power only ANSWER 5.03 (3.00) (0.5 each) 1. g { 2. b 3. c 4. e 5. e l-6. f l REFERENCE oyster Creek, 2000-AEN-3200.13, Rev. 7, 06/10/88: Response to Loss of All 125 VDC, Pgs. 1-4. LO TCR 828.12 I,J KA 262002K108(3.1) 262002K116(3.2) 295004AK203(3.3) l 295004K203 262002K116 262002K108 ..(KA's) Draft /TRITT 23.0 i ~ m - m.- _.,-..-.m_ ,.~-m.--

FACILITY coletRNT:; ,'q (4.) thould C: cept o' cr g since como cf the 460V and 4160V break:ro do itse ] position indication in addition to reset capability. ,(5.) should accept e or g since the red and green indicating lights are DC-i powered while the acoustic monitors are not. ) 6.) should accept b or f sinew the DC isolation valves will lose position I ( indication. l FACILITY JUSTIFICATION: (4.) print BR-DW6-E1122 .(5.) ADS elementary GE 729E182 + (6.) print BR E1184 i T t t ? 't t i i l l l~ J Draft /TRITT 24.0 L l 1' l

--vr+ I E gusananer duo AnMQRMkL PLkNT EVOLUTIONS { i: - QUESTION 5.06 (1.00) I 1 The. reactor is operating at 60% power when condenser vacuum low annunciator (9-3-c) alarms. Condenser vacuum is 24.0 in. Ng vac. and decreasing slowly. I Per ABW-3200.14, " Loss of Condenser Vacuum", WHAT action should be taken as a j result of decreasing vacuum? j (1.00) i F a. Scram the reactor ] . b. Reduce power to prevent a scram c. Trip the main turbine l d.- Confirm reactor scram and main turbine trip { N i ANSWER 5.06 (1.00) b (1.00) l i b REFERENCE ABN-3200.14, Pg. 3 f LO TCR 828.26 F fi KA-295002K309(3.2) 295002K302(3.4) 295002K103(3.8) 295002K201(3.5) 295002K202(3.7) F,' 295002K103 295002K302 295002K309' 295002K201 295002K202 i!(. ..(KA's) I ,y it' 1 FACILITY COMMENTS: IJ' should accept (&; or (b) since 24" is close to the scram setpoint of 23". Some [ operators e,ay pick (a) per the 106 Procedure which states a manual scram may be i inserted whm. verified opersting parameters are trending such that an automatic i ecram te in.minent or Anevitable, u) YM:ILITY JUSTIFICATIDH!

t. 1 b;

Sectlon 4.1.3 o.f Administrative Procedure 106. f - Draft /TRITT 25.0

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h EbERRENCY AND 1RNORMAL PIANT EVQLUT10Als j i I I i QUESTION 5.08 (1.00)- ) If altre 3-4-e, " BUS 1A UV", activates and the undervoltage trip on feeder breaker 1A1P fails, then Emergency Diesel Generator #1: (1.00) (CHOOSE ONE) a. may overload during the fast start ooguence b. vill automatically start and idle at 450 rpm c. may need to be nanually started and idled at 450 rpm d. will not function properly due to being paralleled with an unstable grid ANSWER 5.08 (1.00) a (1.00) REFERENCE OCNGS OPM 16B, Rev. O, 03/27/87, p. 168-9, Fig. 168-1A, TABLE 16A-2 KA 295003K102(3.4) 295003K102 ..(KA's) 4 Draft /TRITT 26.0 r

. FACILITY CONNENT Question refers ts c tomatis oper; tion cf EDG #1 12 refCrOsce t9 4160V 1A j undervoltage condition with subsequent failure of 1A1P breaker to trip. Answer .(a)'is correct based on this condition, however breaker 1A1M is designed to I y also trip on an undervoltage condition thereby shedding loads. Given this l ' confusion factor, neither (a)-nor (b) is totally correct. However, credit j should be given for (b)-as RDG will automatically start. l l FACILITY JUSTIFICATION: [- RAP U-1-a i t p i-i t i i ? i t t t e i Draft /TRITT 27.0 i,- 5 I -t s s-v-- e e-r m - m r .v.

_ _ ~. -L ppnENCY AND ARMORMAL PIANT EVQLUTIONS i ~ QUESTION 5.14 (1.00) During a reactor startup an Snexplained increase in reactor power occurs such i that_the, reactor is now operating in Region 2 of the attached Figure 202.1-4, ' Oyster Creek operating Power / Flew Map". In accordance with procedure j 2000-ABN-3200.07,_" Unexplained Reactivity Change *, which one of the following 1 actions _should be taken immediately? (1.00) a. insert control rods in reverse order and bring the reactor tuberitical-g b. insert control rode (CRAM array) to reduce power to below the 80% { rod line t t c. manually scram the reactor d. reduce recirculation flow to reduce power to below the 80s rod line ANSWER 5.14 (1.00) b (1.00) t REFERENCE OCNGS 2000-ABN-3200.07, Rev. 2, 03/24/89, p. 5.0 OCNGS TCR 801.01, I.A.5 KA 295014AK106(3.9) 295014K106 ..(KA's) F t ( f l Draft /TRITT 28.0

Of5ftR CREtt IWCLEAR StutRAT!"3 humber i DMINuolear T1t1e Revision no. 'l Power Operation 16 l i Figure 202.14 l i AATED PeWeR e lateWWF BattB flat e et.5a/13 I .sha

    • ,s-i

,c*/ p #r v/ L =:- ] ,pd 'E s tu.nl )Sm. N .egior. 2 ~ .i t-l i a-l Min Nat. Pump 456

cue, spew g

riew I I I I I I I I I L e is a se e es as se es es see esse new (si Oyster Creek Opersuas Power / Maw Map c.....n.> l E5-1 l.

FACILITY 00setRNT: 3 i should accept cnewere b or c, since 2000-ABN-3200.07 does st"_to that if you j enter region 2 of the attached curve, you should insert the cram rode to reduce power below the 80% rod line. It would be impossible to be in region 2 in the l startup Mode without a Tech spec violation. Maximum power in range 9 is 12% ) 1 and minimum flaw in range 10 is 654. FACILITY JUSTIFICATION: i 2000-ABM-3200.07, ' Unexplained Reactivity Change" ] ) 1 1 t i 3 i e b i Draft /TRITT 30.0

L gagnaENCY hMD kRMORMAL PIANT EVOLUTIQMS r QUESTION 5.17 (1.50) i Emergency Operating Procedure ENG-3200.09, "Lovel/ Power Contro1*, in step LP-2, requires bypassing the MSIV low-low RPV water level isolation interlock. In accordance with Procedure 312.1, " Bypassing Icelation Interlocks and Automatic Scram During Emergency conditions", what three (3) specific precautions / limitations are applicable to bypassing ONLY this signal (containment flooding is not required)? (i.e., Under what three (3) conditions should you NOT bypass the MSIV low-low RPV water level isolation interlock?) (1.50) ANSWER 5.17 (1.50) 1. No indication of gross fuel failure (0.50) l2. No indication of steam line break exists (0.50) 3. Main condenser is available (0.50) REFERENCE - OCNGS TCR 845.02 I.B OCNGS SBEOP EMG-3200.09, Rev. 2, 01/31/89, Step LP-2 OCNGS Procedure 312.1, Rev.-7, 05/06/89, Pg. 7.0 KA 295037G003(4.3) 295037G003 ..(KA's) t Draft /TRITT 31.0

. FACILITY CONNENT8's' Since we do not require oper0cora t3 memorise cpecifi7 proc :tione/limitctions, l ehould accept _any answer consistent with intent of precaution. Example: Gross fuel failure-accept high radiation conditions. t l FACILITY JUSTIFICATION: j J OCNGS TCR. 845.02 1.3 l t l r r i t t t i F P Draft /TRITT 32.0

L,. SHERRENCY AMD ARNQRMAL PIANT EVOLUTIqats f l l QUEST 10N 5.20 (1.00) In accordance with Emergency Plan Implementing Procedure 9473-1MP-1300.33, .j

  • Core Damage Estimation" which of the following methods of core damage I

estimation is preferred if the Drywell air PASS sample is not available and drywell venting has been performed in accordance with the EOPs? l (1.00) i a. Computer routine "EPIP-33" b. Hydrogen concentration in containment I t c. Containment High-Range Radiation Monitor system d. Off-cas system activity ANSWER 5.20 (1.00) L b (1.00) REFERENCE OCNGS EPIP 9473-IMP-1300.33, Rev. 3, 01/26/89, pp. 4.0-5.0 and 12.0-14.0 L KA 295038EA204(4.5) 295038A204 ..(KA's) I l Draft /TRITT 33.0 i

l ~ FACILITY 0000EENT: I We do not require ccndid;tco t3 memorise cetions la 9473-IMP-1300.33. Should f accept b or c.since both of these methods are discue W in the procedure. i FACILITY JUSTIFICATION: OCNGS TCR 0623.2685/780.0.0001, BLO K (attached) 9473-IMP-1300.33, " Core Damage Estimation" 1 h 1 i i l ) I i 1 J ? i C t t i l -t l~ l l l Draft /TRITT 34.0 1

Tile No. 0523.2585/750.0.01 -] GPu Nuoleer minine cone nt neo ee.oc Program Title Number Rev. EMERGENCY PREPAREDNESS TRAINING 30457 2 7832-PGM-2685 Course Title Number Rev. EMERGENCY DIRECTION / 30857800 0 EMERGENCY SUPPORT DIRECTION 0623.2685/780.0 Lesson Title Number Rev. EMERGENCY DIRECTION / EMERGENCY SUPPORT 308578000001 1 DIRECTION FOR LICENSED OPERATORS .01 1 I. PURPOSE / SCOPE: To provide the Emergency Director / Emergency Support Director and their respective key staffs with the purpose and concepts of the l Oyster Creek Nuclear Generating Station's Emergency Plan, its implementation, and the achievement of its objectives through i Emergency Management, Direction and Coordination of GPU Nuclear Emergency Organization. II. BEHAVIORAL LEARNING OBJECTIVES: At the completion of this session of training using only the lesson materials provided, the trainee will be required to demonstrate and have the ability (in writing or by practical application) to complete the items listed below: A. State and explain the responsibilities of the Emergency Director and Emergency Support Director. B. Describe the responsibilities and authority of the ED/ESD to the various-Local, State, and Federal Agencies. C. State the concept of operations for responding to an emergency with the on-shift organization, j D. State the concept of operations when going from the on-shift to the Initial Response Emergency Organization. Responsibility Signature Title Date Origination , fdla d Lead Emer. Planner Yl/ff Review / Concurrence l Approval l Objectives ( Emer. Preparedness MgrM/J f l Final \\/ lJ'M[$5O SupportTrainingMgr.M[M // m V [ N $2F7 0240 4131J

I hr hining Content Rooord. OC Program Tale Number Rev. EMERGENCY PREPAREDNESS TRAINING 30857 2 7832-PGM-2685 3 Course Title Number

Rey, J

EMERGENCY DIRECTION / 30857800 0 EMERGENCY SUPPORT DIRECTION 0623.2685/780.0 Lesson Titio Number Rev. EMERGENCY DIRECTION / EMERGENCY SUPPORT 308578000001 1 ~ DIRECTION FOR LICENSED OPERATORS .01 II. BEHAVIORAL LEARNING OBJECTIVES: (Continued) E. Describe the transfer of authority schemes as the offsite facilities are activated. F. Describe the functions of the emergency facilities, state the emergency levels at which the various facilities must be activated and their location, and state the timing sequence for manning the onsite and offsite emergency facilities. G. Define the Emergency Planning Eones and discuss their purpose. H. Define the Protective Action Guides (PAG). I. Define the Protective Action Recommendation (PARS) and the criteria for each. J. Explain the basic concepts involved in making dose assessments and dose projections. K. Explain in general terms the contents and uses of EPIP's 1, 2, and 3. L. Explain which procedures are used to accomplish Initial Procedures, Callout of Duty Roster Personnel, Event Reporting, Logkeeping, and Reporting Telephone Trouble.. l l M. Explain the concept and operation of Pagers. N. Explain the concept and operation of the Emergency Telephone

System, t-O.

Explain the method used to handle citizen inquiries on inadvertent site activations. t l III.

REFERENCES:

A. GPUN Emergency Plan B. Emergency Plan Implementing Procedures C. Station Procedure 126 4131J-2.0 N 5224 02 W)

i i GPU h Dolning Cofdent R000fd

  • OC Program TMio.

Number Rev. l EMERGENCY PREPAREDNESS TRAINING 30857 2 7832-PGM-2685 i Course Title Number Rev. EMERGENCY DIRECTION /- 30857800 0 } e_arrmarmcy suppent nieretion 0623.2685/780.0 i Leeson Title Number Rev. EMERGENCY DIRECTION / EMERGENCY SUPPORT 308578000001 1 ~l DIRECTION FOR Lierumen oprostone .01 III.

REFERENCES:

(Continued) D. NUREG 0654 E. NUREG 0696 ] F. NUREG 0728 G. EPA PAG Manual l H. 10 CFR 50 I. NUREG 0396 I IV. DURATION: Four (4) hours apProximately. I l 413IJ 3.O N 5228 (1247)

f L, EMERGENCY AND ARNQRMhL PIANT EVQLUTIONS i l i QUESTION 5.21 (3.00) l ) COMPLETE the following in accordance with EPIP 9473-IMP-1300.01, )

  • Classification of Emergency conditions":

(include units where applicable) l The fuel cladding integrity shall be considered breached if coolant activity l exceeds or, off-gas discharge indicates greater than (0.5) (a) (0.5) (b) The RCS boundary shall be considered breached if thera is confirmed leakage i from the R.C.S. in excess of (0.5) (c) t The Primary Containment shall be considered breached if any of the following .{ conditions exist during an accident sequences Unexplained rapid decrease in (0.5) (d) (exceeds makeup capacity ) -or-Unexplained increase in in more than (0.5) (e) one area with known or suspected leakage from Primary i Containment -or-Venting of the is required for accident control (0.5) (f) ANSWER 5.21 (3.00) a. 300 uci/ml (0.5) b. 10,000 mR/Hr (0.5) c. 50 gpm (0.5) d. D.W. Pressure (0,5) e.. Secondary containment A.R.M.s (0.5) f. D.W. (0.5) REPERENCE OCNGS EPIP 9473-IMP 1300.01, Rev. 5, 12/17/88, pp. 3.0-4.0 KA 295038EK205(4.7) 295038K205 ..(KA's) Draft /TRITT 38.0

FACILITY C000EENT - We _do not requira operCtcrs' t3 memorise EPIP's; therOf;re, Chould C0 cept tCras ,l other than the exact words listed. Examples Containment vice D/W FACILITY JUSTIFICATION: OCNGS TCR 0623.2685/780.0.0001, 514 K Draft /TRITT 39.0

VW,, ~' ~ ~ ~ ~ %na f -4?^. ';.. s + _ h.. , h. E T.$ @.AND AR M.P M. M UTImla -l 1 1 i 1 { j fi. g. . QUESTION.5.25' (2.00) y i (Given the'following' conditions: , Reactor powet is 12% I 1 Reactor Mode. Switch is in SHUTDOWN -1 i Recirculation Pumps have tripped j g. .CRD pumps ue unavailable = -4 No boron has been injected $jl, .ARI has initiated-t scram solanoids are'deenergized Scram: air header-is' vented y ~ l. Torus water temperature is 115'T .q H L:, .USE the attached copy of TNG-3200.01, "RPV Control - Power" and STATE ~ e .a.; 'What step (s)- in.this procedure is(are) being performed now (1.00) b. What,1if any, immediate actions-are required by this procedure [ '(1.00) lANGWER 5.25 .(2.00) a. RC/Q-5.. :(0.5 each) RC/Q-6 (or RC/Q 6.1 &l[2 RC/Q 6.2) t k b.- Initiate liquid poison-(0.34) Prevent automatic initiation of ADS (0.33) ,c L Roset ARI (0.33) j[. REFERENCE i OCAGS TCR 8%5.05, I.A OCNGS EOP ENG-3200.01,'"RPV Control - Power", key. 4, 01/31/89 l.: KA 295037G012(4.6) 295037G012' ..(KA's) ,i g l. . Draft /TRITT 40.0 B ai (1 K

k i 'e '; FACILITY CONNENT: !) . -.o 7 Some Candid;tos cn;wercd both part3fo end b in part,c cnd chould be giv;n-. - appropriate credit.,.They gave'other. administrative requirements-in part b ~ - (i.e.,; Alert Notifications, etc.) and should not be penalised. j t' . FACILITY JUSTIFICATION:. 'Mone'needed. i i y.- j I

~.

s

k 4

) I t. J ) F k 6 si g.; t <i if-Draft /TRITT 41.0 ~- s P'- e t 4 v-~ y-

. ~ - -... ' i ' l

11. MIERGENCY AMD AEMORMAL PLANT EVOLUTIONS 3

L ' QUESTION 5.31L (2.00) ~x ,Using the attached IMP-1300.01,

  • Classification of Emergency Conditions,"

i

Attachment 1, MATCH the correct classifications with each of;the following i

plant' conditions or events. PLANT CONDITION / EVENT CLASSIFICATION 1. Annunciators J-3-a and J-4-a,

  • FLOW ~

a. Not an Emergency Action. HI/MN STM LINE AREA TEMP HI-HI.I[II]" Level (EAL). are alarming.' The MSIVs are open. (0.5) t 2. Annunciators J-1-b and J-2-b, ' RAD b. Notification of Unusual f HI-HI I[II]" are alarming. The MSIVs Event are open. (0.5) 3. 24 hours after testing the EMRVs c. Alert torus water' temperature was reduced to 96*F. .___(0.5)d. Site Area Emergency ( 4. The reactor mode switch is taken to e.- General Emergency the "STARTUP" position during a shutdown and a reactor scram occurs.- (0.5)- One candidate requested additional information to answer Parts 1 and 2, such as, whether there was leakage from the RCS and what the power level was. He was informed that there should be adequate information already provided but that if he felt the need to make assumptions he should write them down. L ANSWER 5.31 (2.00) (0.5 sach) 1.- - d 2. e 3. b 11 -4. a REFERENCE i

1.,

Oyster Creekt Emergency Plan Implementing Procedure IMP-1300.01, KA 294001A116(4.7) g-j 294001A116 .(KA's) Draft /TRITT 42.0 a -~m .e u-m i

L *... n ': 1. i ' FACILITY C000lENTt . s Since the cwaminer ctCted th:t the c:ndidat03 could etcto c Cumptien3 if f they-- 7;f.,. felt that: insufficient information+sas given.: ~ Answers consistent'with these-.- ' iK . ' assumptions should be.given consideration.. g., . FACILITY JUSTIFICATION: o ' Exam commenta.. o ( .I t 5 a a . { k 1-l 1 s P .1 . Draft /TRITT 43.0 ,a; K, i

'n- -QUESTION 5.35- -(1.00). In accordance with' Abnormal operating Procedure 2000-ASN-3200.22,'"A0G Building ~ Loss of Power"~ you are cautioned NOT to restore power to MCC-1E13 or MCC-1E14-at-Us8-1El if USS-1El was doenergised for more than 6 hours. The basis for this caution ist (1.00) a. te prevent the spread of airborne radiation to other areas due to the automatic restart of the ventilation system b. to allow the ventilation system time to clear the. building of any hydrogen ic. to prevent an explosion due to a potential combustible gas mixture being present. d. to allow time to restart the ventilation radiation monitor pump -before restarting the ventilation system ANSWER 5.35 (1.00) c; (1.00) Y -REFERENCE t' OCNGS~TCR 801.01, I.C, Lesson 801.01 p. 42 i 'OCNCS 2000-ABN-3200.22, Rev. 4, 05/28/89, p. 6.0 f KA' 294001K115(3.8) s - '294001K115 ..(Kh's)- l O b Draft /TRITT 44.0 i 1 w-i ._.m

~ t . FMllILITY C000SNTt, N ishouldfos cpt c cr a ci~nio Proc:; dura 2000-AB;-3200.22,'

  • nog' Tuilding Lo:s of

~ j gig., ' Power *faddresses both of these concerns.- -- j ' i;; - y 3 1 . FACILITY JUSTIFICATION: l' T 2000-ARN-3200.22, "Aoo Building Loss of Power", sec. 3.7.- I 4'I .I ? t 4 ' ) 1-. IT 1, y w;.); .4, -.. s L 1 ' k: Draft /TRITT 45.0 ),

, p -

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u
.1,

.\\ ~,. i ._(r. l I { i,.1 f V i; y ( ] J i s FACILITY COMMENTS n i . CATEGORY 6 l {:jn .f: . t. w ,f-: 'It4 1 { y -4 1 t x h

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-i ti ~E -t ,) s 3 e i 1 +:p E 1 er. y a e l K i a 1 -i N Draft /TRITT' n i i e.f s 4 " ~ L w w ~ a

r - M PphMT SYSTEMS AND PLANT-WIDE GENERIC RESPONSIBILITIES QUESTION 6.09-( 2. 00 )._ MATCH the following conditions with the correct and most severe automatic action. Severity increases from a. to e. No instruments are bypassed. . CONDITIONS AUTOMATIC ACTIONS (severity) 1. Reactor Mode - STARTUP (0.5) a. None (least) 3 SRMs not fully inserted Count Rate - 50 CPS b. Alarm Non-coincidence jumpers installed c. Rod Block 2.- Reactor Mode - REFUEL (0.5) -All SRMs fully inserted d, Half-Scram Count Rate - 10 CPS y Non-coincidence jumpers installed e. Scram (most) An IRM mode switch is taken to STANDBY .3. Reactor Mode-- STARTUP-(0.5) IRMs on Range 8 No SRM is fully inserted one SRM is reading 0 CPS' Non-coincidence jumpers installed 4. ~ Reactor Mode - RUN (0.5) Power - 10% All SRMs are fully withdrawn Non-coincidence jumpers installed one SRM period meter is reading 25 seconds ANSWER.6.09 (2.00) (0.5 each) 1. c 2. d l 3. b 4. a l' l REFERENCE OCNGS TCR 828.29 I.B, I.E - OCNGS OPM 29B SRM, OPM 29C IRM l-( KA 215003K101(3.9) 215003A103(3.7) 215004K102(3.4) 215004A105(3.8) l 215003A103 215004K102 215004A105 215003K101 ..(KA's) Draft /TRITT 47.0 L l l

Em r .ai o 'F - d... : FACILITY CONNENT - - j . i 5F.;r P rt;4,'chould cceept a Cr b'bertuse the CICrm is-not bypapCCd in *RUN*. U even.though the OPM module does state that'it-is bypassed. [ a [4 ] s Y

j
' FACILITY JUSTIFICATION:

i Alarm Response Procedurei 6-7-D~ - 1 1 .' i -2 t-6 '1 3 e [-. t 1

71 lll.

T :. m -). t o t k L ?.:. l S p. t-s l l^ 1 1 Draft /TRITT 48.0 ll-I L

g. ' k PIANT SYSTEMS AND PLhMT-WIDE GENERIC RESPONSIBILITIES a QUESTION 6.11 (2.00) - - With regards to the feedwater control systus i A., il

a..

! State two-(2) reasons for.having feed pump runout protection. (1.00) l b.- Stat'e'when' feed pump runout is reset.- (1.00) -I 1 ANSWER 6.11 (2.00)' Any 2 of 3 for'(a). <q a. 1. Protect feed pump from over current (0.5) -. 2. Protect cond. Domin.:from high D/P.(not.per procedure) 3. Prevent feedwater pump trip on low suction pressure-(0,5) i b.: Whenever'the FRVs. receive a close signal (1.00) , REFERENCE OCNGS TCR 828.18 I.G OCNGS OPM;18, Rev.'O, 02/19/87, pp. 18-18,-18-19, "Feedwater Controle" 'OCNGS Licensed Operator Exam Bank, Item Code 3-8 1 - KA -259002K410(3.4): 259002K506(2.4) 259001K108(3.7) 259001K405(2.8) 259002K410 259002K506. 259001K108 259001K405 ..(KA's) c; o 1, Draft /TRITT 49.0 e f i -

m- ,4 i l, , FACILITY C000SNT ; ,j 3

n,.

" L(b.)ichouldcec:ptcetu21'cpercticnlcfin;trumentcticninlicucf'whneyra-a. y 3 close - signal" is, received" - .0. h t z. . FACILITY JUSTIFICATION : ,,g , g - -D-308-7K11-246 ' I L t f:. i , s: .s y 4 c/ 1 t I b -L ..s, l Draft /TRITT 50.0 1 l

1 ~pos? ECRAM REAcTOP LEVEL EETDOWN PROGRAM -l + ]p{ . Circuitrv Ooeratien' B. q a j n 1. Remeter Level Setdovn i# .The signals which' initiate the RLS are low reactor water level I ~ (137 in. TAF) and a full ceram' signal.. The scram signal comes from new relay 3K10X in the scram reset interrupt circuitry. ] (Fig.1).- This closes a contact,in the RLS circuit (Fig.;2). The j g L low water level signal comes from a new alarm unit,.ID91, which ) h receives a Aevel signal from narrow range GEMAC channels A or B q (determined by the selector switch on Panel'4F). 1 When both signals exist, relays K22 and K22X energize. Contacts I ~ f rom K22 seal in the relays; one bypasses the full scram signal and the.other is in the reset circuitry.. Reset pushbutton ID35' i (to be on Panel 4F below-the Master Feedwater Controller) illuminates and an alarm sounds on Annunciator H l (H-7-f,="RX LVL SETDOWN INITIATED"). L Relay K22X actu, ally initiates the RLS signal (Fig. 3). The ' l output of limiter ID32 is added to the sensed level signal L (either single element or three element as selected by the L operator). This adds 24 inches to the sensed level signal input - to the Master Feedwater Controller; thus, reactor water level will be maintained 24 inches below-the setpoint selected on the Master.Feedwater Controller. ' Assuming a normal setpoint of 160 inches TAF, the RLS. mode will control level at 136 inches TAT. Three conditions must exist before the RLS'may be reset: l') tLe low-water'1evel condition must be cleared (ID91 reset); 2) the Master Feedwater Controller must be in manual (ID66 contar t'); and 3)-the= reset pushbutton ID35 must be depressed. The requirement to have the Master Feedwater Controller in manual is.to assure that a step increase in the automatic mode output does not occur when the RLS logic is reset. The operator must also ensure the contro11er 'is balanced prior to shif ting it to man sal. 2. Feedoume Rumout Protection Runout protection is actuated by high feed string flow, at 2.67 x 106 lbm/hr (same as present setpoint). On Fig. 4, this will close the ID92 contact, and energize the K11 relay. This relny seals itself in and energizes K11B and K11C. Relay K113 br.s a time delay of one (1) second before its contact closes to ensure the runout protection initiation is sealed in before making reset possible. t Relay K11C doec several thingr; 1) it energises relay K112, which gives the amber RUNOUT indication on SF and bypasses the loss of signal contact for feed regulating valve (FRV) lock-up; 2) disconnects the signal input from the bias M/A station (ID15) to the FRV and connects the output of flow controller IDB6 to the FRV (Fig. 5); and 3) it opens a contact in the K11 path to prepere for resetting the runout condition. y 3513b -.m.

jz' jf' POST SCRAM REACTOR LEVEL'RETDOWN PROGk M, f /; 3 /k ThG FRV isLatw b31Ag PDsition3d btsso up3D th3 Output of th3 flew ~ /

controller ID86. LThis' controller receives the compensated feed f/Y.

flow signal (forfthe appropriate. feed string), and an input from the runout flow setpoint-controller ID87. The final result.is. / ~ the TRV will:be positioned to maintain that string's feed flow at' theirunout setpoint;(2.67 x 106 lbm/hr). Reset? occurs automatically whea~the output of the bias N/A station (ID15) is'less than the output of flow controller ID86.. This would mean that the ID15 signal is wanting to'close the 'l valve from the present position of maintaining 12L67 x 106 lbm/hr.. Dif ference alarm ID95 monitors the signals from ID15 and ID 86 and closes a-contact in the runout protection circuitryf(Tig.4) which energises relay K14. Relay K14 deemergizes'K11, which then drops out relays-Kilt (instantaneous) and'K11C'(two second~ time delay). The time delay on K11C is to ensure the condition is reset.before placing the ID92 signal (runout flow signal) back in the circuit. This~ prevents false reinitiation of-the runout circuit due to spurious ID92~ actuations from electrical noise. 4 When relay K11C drops out, it slso deenergizes relay-K11X. This clears the RUNOUT _ warning light on ST and removes the bypass around. the loss of signal contact for FRV lock-up. Relay K11C also. ramoves the IDB6 signal to the TRV and reconnects the ID15 signal (bias M/A station' signal). JIII..QETRATIONS A..'Nermai Oeeration l ..ThesRLS circuitry has no effect cn normal power operation, as the L ir.itiating signals are a full scram condition and a Itw water level .in the vessel. The runout protection circuitry should also have no l effect on normal operation, since-feed flow is typically-less than the runout setpoint. Should.an individual feed string (which is R running close to the setpoint already) bounce or spike up to the setpoint, the circuitry will operate as designed and no operator action is.necessary. Also note that except for the amber RUNOUT warning light the operator receives no indication +.he runout l: protection circuitry has initiated (no annunciator alarms). B.. Tr amm ient oeerations l The RLS circuitry and the runout protection circuitry will normally operate together to control vessel level during a reactor scram, which is the transient the system was designed for. L V 1, f t 3513b x. 1

$ @ SYSTEMS AND PLANT-WIDE GENERIC RESP 00tSIBILITIES L* v -. QUESTION. 6.15 ;.(1.00); ~Considering the fire protection systems: What signals williautomat.Leally start-the diesel-fire pump'l-27 =0ive setpoints- ~ where~ applicable. ,G . AN8t?ERL6.15 - ('1. 00 ) 1 1. 85 +/ 10 psig fire main' pressure'-(0.5) 2. -Lose.'of AC power (0.5) REFERENCE W-OCNGS Licensed' Operator Exam Bank,' Item Code 2-119 l.. s K4 286000K402(3.5)- 286000K402. ..(KA's) $ ). L f 4 - g [. P 1 w 9 ,g. Draft /TRITT 51.0 d j

gg;;yt w = jl , w: s# z ..g

s,.. FACILITY COMMENT -

l k .Should accept loss.of control power as.. sensed ct 102A bec:uco thia'io whit '. starts the diesel;on a loss of ac power. 4 FACILITY JUSTIFICATION: 4 . 1 1 1 OPM Module 19 see attached.OPM'1'9-59, Rev. 0-1 1 .i ? I t gi;. : c:. r l r t b 4 t } t: + t E L 4 4 5 I' (= i ~ < 4 / (: l :' t* L. Draft /TRITT 52.0 tli

p i. ' [ ;,.

p 1h . j, at . ~ -- L

l .. D g .jp ne fire punpa will not start unless both wiuv1 switches j t 4 are out of PULIMD-10CK. 1 2.. Interlocks-i l: i a. Diesel Fire Puno i Diesel Fire Punps 1-1 and -2'. autcsatically start Whenever a the pu:@ control 'switdes are in NJIO and Fire suppression 5 Water System pressure decreases to 75~ and, '85 .psig respectively or if Ac power to lighting panel 1B2A is lost. ne diesel fire punps autanatically shut down after autcreatic starts with a 15 h time 6elay if the centrol . switches are left.in AUIO. I Diesel fire pu=p shutdowns are delayed 15 minutes after manual starts. Be time delay begins dan the purrp miuul switch is placed in AUIO. he diesel fire punps shut down hwiately if the wiaul -t switches are placed in OFF. l i l l J i a Page 19-59 Rav. 0 03/31/87 i

.. y .i hl , L,. ; FIANT SYSTEMS AND FIANT-WIDE GENERIC RESPONSIRILITIES j .j a-i i

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"' ~ ' QUESTION'6.16-~,(2i00)? ] With regards-to the Main steam Line (MSL) radiation monitor systems- - ) .. i = . What four (4) automatic actions: occur on~a MsL high-high trip function?- Specific componer.c mumbers are not required. .(2.00) .l ANSWER 6.16' (2.00)- 'I ? 1.. _.Off-gas' isolation-(0.50) 2.. 'MSL. isolation (0.50). 1 4

3. - (Rx scram (0.50)
y 4. Trips vacuum pump, (0.50)~

] REFERENCE '.OCNGS Alarm Response Proc. J-1-b, Rev. 13 OCNGS OPM 04, p. 28- .& a Item Code 3-30 ?;: . CCNGS-Licensed Operator Exam Bank, u KA 272CDOK103(3.8) 272000K402(4.1).272000G007(3.5) 272000K402.. 272000G007 272000K101 ..(KA's) l-1 lt;- + ~ n t ) t b l l l Draft /TRITT 53.0 4 ~ i o r m

y,_' 1 4? --FACILITY COMMENT: 3 s m . i ^ .Shouldfaccept V-7-31' closes;in lieu of off-g:n icsittien cinc3 thic is the ! valve that' closes'on this isolation.; l w I i . FACILITY'JUSTIFICAT!ON :' .:. i 4 T OPM'04' See. attached 2000-RAP-3024.03 i. 3 j 3 E 'l -s 7. ) ll. N[ z s 2 3. w ? s I 1 1 I t i, Draft /TRITT 54.0 u i + t e

7 Group. Heading j Hn N S: TEAM J-1-b e (RED) i RAD Wl-W1 1 AND 1 CAUSES: SETPOINTS: ACTUATING DEVICES: Radiation levels as detected at the main 600 2 100 units RN06A and RN068 steam lines 10 x normal background at power. Trip signal to Reactor Protection System I. Reference Drawings: GE 846D686, Sheet 2 GE 237E566, Sheet 1 CONFIRMATORY ACTIONS: For half scram signal check the main steam radiation level at Panel 10F and 1R/2R. AUTOMATIC ACTIONS: Reactor scram, reactor isolation, closes V-7-31, V-7-29 and trips-vacuum pump with 1 coincidental Channel II trip. Also, recombiner inlet valves A0V 001A & B close. NOTE:'If A0G is on-line, V-7-31 will already be closed.

MANUAL CORRECTIVE ACTIONS

For erroneous or spurious trip, reset the half scram. refer to Procedure ABN-3200.01, " Reactor Scram". For a full scram condition, This-alarm indicates that a parameter has exceeded or has the potential to exceed an Emergency Action Level (EAL). Classification of Emergency Conditions. Enter Emergency Plan Implementation Procedure #1, EAL - Radiological Effluent Release Subject Procedure No. B0P 2000-RAP-3024.03 J-1-b Page 1 of 1 u ' Alarm Response Procedures Revision No: 13 1

b_ FI,5N? SYSTEMS AND PLhMT-WIDE GENERIC RESPONSIBILITIES i (.' t 4" i QUESTION 6.18_ (1.00). -The. reactor is operating at 1004'and a full flow surveillance on the Core spray system is in progress. The Cs system is recirculating water back to the torus when a low-low vessel water level signal is received. How do the test-to-torus valve and the CS discharge valve respond, initially,. to this signal?; a. The test-to-torus valve will remain open and the CS discharge valve. will remain closed b. The test-to-torus valve will go closed and the C8 discharge valve-will remain closed c. The test-to-torus valve will remain open and the Cs discharge valve will;go open d.' The test-to-torus valve will go closed < 1 the Ce diccharge valve will go open ANSWER-6.18 (1.00) b (1.00) REFERENCE + 1- !~ 'OCNGS OPM Module 10 Core-Spray System pp. 19-23 OCNGS LO TCR 828.10 E l - KA 209001K408(4.0) 209001K407(3.0) 209001A108(3.2) 209001A301(3.6) 209001K408 209001K407 209001A301 209001A108 ..(KA's) 1; h t l Draft /TRITT 55.0 1 m m

ww,~gew;sm ~e. . mew vn gg~ g nsyy ggn ,s.; { f @ J't:1 FACILITY 0000 TENT:. .-?. Comment withdrawn. t ,V .6 t a .+ 1 3 i D r. t. 8' ? ,G ,t t -. .,i .f i ? t= ( -l ? y 3 ' '.}i i 4, s ..g -[ i-4 1 b ) 1. si - ris V . 4., 4 - r.tb

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' t, tj k e.. f gr... a t t c 4 s DS i i 5 ) 4 a F y v. b. Y y s h. ' Draft /TRITT 56.D a s --+W~+%,n9-;wk.xyg ,mwp,.,_.g_,,,

h FIANT SYSTEMS AND PLhMT-WIDE GENERIC REEPONSIBILITIES 1 QUESTION 6.20 (1.00) j 1 COMPLETE the followings a. In accordance with Technical Specifications, a fire brigade of-at least members shall be maintained on-site at all times. (0,5) ) b. In accordance with Administrative Procedure 101.2, " Fire Protection i Organization, Responsibilities and Controls", each fire brigade j leader shall perform at least fire drill (s) per year. (0,5) ANSWER 6.20 (1.00) a. five (1,5) 0 b. one (0.5) REFERENCE OCNGS T.S.~6.2.2.g s DCNGS Admin. Proc.~ 101.2, 4.14.7 KA-294001K119(3.8) -l l 294001K119 ..(KA's) l t Draft /TRITT 57.0 c.

,r .y: FACILITY C000 LENT l (b )-in 00 n rd nel with Adminictrativo Proceduro 101.2 th3 Firo Protocti!n Instructor is-responsible to ensure A H-Fire Brigade Members are fully. -. qualified and.the Gss only responsibility is to use fully qualified members on ,the Fire Brigade. Therefore, this part;of th6 question should be dropped. FACILITY-JUSTIFICATION: -9: Administrative Procedure 101.2 ' Admin. Proc.'.106, sec. '3.6 (NOTE: 3.6.9) and'sec. 3.7 -Admin.~ Proc.'101.2, sec. 4.14.2 H y 44 t .I i E f.* ..i. . Draft /TRITT 58.0 t 4

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E-FIANT SYSTEMS AND PLhMT-WIDE GENERIC RESPOIISIRILITIES

QUESTION 6.21 (1.00)

. Which of tho'following is NOT an acceptable reason for defeating an alarm circuit? (1.00) a. Malfunctioning. alarm. b. Alare due to equipment tagged out-of-service-4 c. Known alarm condition which has the potential to mask additional alarm conditions j d. Known recurring alarm condition which may distract from other' alarm conditions-ANSWER 6.21 (1.00) d. (1.00) .l REFERENCE OCNGS TCR 830.01 I.11 OCNCS Admin. Proc. 108, Rev. 45, 07/16/89, p. 90, 7.2.3 KA 294001K102(4.5) -294001K102' ..(KA's) Draft /TRITT 59.0 s

M. + <r l o k @,% //jjp\\NNNp g5 g,# // IMAGE EVALUATION gpyyg, 9/ TEST TARGET (MT-3) x g 4 \\\\\\ M/ ) /k[+// +4 1.0 lf m E4 ' lj ILE j l-l E m llin t: _T l.25 1.4 1.6 4 150mm 4 6" [% /$ >,gy>$,i// s<g,.g,4 7777m , ;A w o

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/ e N,p g TEST TARGET (MT-3) k>, l.0 EEa En ylj liai! i,i [m HM l.8 1.25 1.4 1.6 =4 150mm 6" 4 pl*%, /$ o>p 7tp+k;+ +yy A/////r js Q- .2:.s.ud.. _________,__.a <W

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l c 77/jg\\NN'N / ($ #, IMAGE EVALUATION f 4 TEST TARGET (MT-3) '% [ *[q$*4 y# Q+g,9' //4 p ' W Eda d I.0 y ll ILE I.I [* UE I.8 l.25 1.4 1.6 4 150mm 4 6" 4 %,, /4 >(giF. b,777777 48),y{ A i a ut =-

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%iWf'& '" i O 4+ [ig 3.- $d:yd,y::S PACILITY COMMBNT: -a hif f[ This question has no correct answer since standing Order $40 allows an operator 4h <-. to bypass a CRD Migh Temp alarm if it is distracting from other alarm 'i .. conditions. Should either delete question or accept (a) or (d) since (a) would require more investigation before the GSS could byptes the alarm. 4 ( FACILITY JUSTIFICATIONi OCNGS Standing Order $40 i i Draft /TRITT 60.0 2 M

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is 4 - .1 / i PLamT SYSTEMS AND PLhMT-WIDE GENERIC RESPONSIEILITIES 4 - ;A-i 1

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~ ~ QUESTION 6.25~- (1.00) E 3: -- Concerning a Drywell. entry for a 1000 poig inspection with the~ rsector at. less-

than 104
powers.

H I Which one of the following conditions is intended to ensure that reactor power lis maintained lees than.1047 (1.00) U ~ 1 a. Level is controlled between 150 and 170 inches-above TAF i y 1 H Recirculation flow is minimised i b.- L 1 c.- Main' Turbine Bypass valves are closedi l a d. IRMs are limited to Range 10-I L rANSWER'6.25 ,(1.00) 1 ? (1.00) ] c.. l' REFERENCE u OCNGS General Plant Operating Procedure 233, "Drywell Access'and Control", Rev. 16, 05/22/89, pp. 8.0-9.0 l OCNGS' Licensed Operator Exam Bank, Item Code-4-93 l{ KA-'294001K105(3.7) 294001K105 ..(KA's) 'l '1 l l i Draft /TRITT 61.0 d

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.. g1. m.,, ,,. _ 3(, <,-i t P ,G ,, - FACILITY COIOGNITS 31 .1 ,tg ' !): . T i $,f"M.

shouldTaccept_a(or e since the_procedureidoes~ require thie level band-to

4 6 minimise pressure and power transients.. ,3 n FACILITY' JUSTIFICATIONS. ..u Hi j g, General'_ Operating Procedure:233,- ~ i,; 4 ,e ll 1; L Vs i - l L 1 L 1 l' ls i I i l ) t-3 1 ,l s l l l l. 1-p. ..a l: 41 i

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n; cr PMNT SYSTEMS AND PLhMT-WIDE GENERIC RESPONSIBILITIES L;z Y

h ? e QUESTION 6.26i l(2.00) m ' Fill in the blanks below to describe Admin. Procedure 106,-" Conduct-of - Operation", limitations on overtime.- _p 1. An! individual should not be permitted-to work more than hours straight. (0.25)' 3 (a) An individual should not be permitted tow work more than~ hours in any 24 hour period, not more than (0.50) .(b) (c) hours in any 48 hour period, nor more than hours (0.25) in any 7 day period. (d) L 2. Deviation from the guidelines must be authorised by the , or higher level of Management, and logged in the ( 0. 50 )' (a) log to describe the circumstances that prevailed. (0.50) (b)~ ANSWER 6.26 (2.00)' 1. a. 16 (0.25)' b. 16 (0.25) c. 24 (0.25) d. 72 (0.25) 2. a. Plant Operations Director (P.O.D.) (0.50) b. Group Shift Supervisor (G.S.S.) (0.50) REFERENCE OCNGS Admin. Proc. 106, p. 69 . OCNGS Licensed Operator Exam Bank, Item Code 8-72 KA 294001A103(3.7) 294001AlO3 ..(KA's) Draft /TRITT 63.0

p;;;c, o : =- 3 :y,;g e v s. l .p i '. 4 d.FACILITYJ CostMENT: e E < yp:,e.s.- '2.6 credit should be given for control Room Log since this log'aust show all; j g jTech-Spec:deviationsand'theirreasons. l

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Administrative' Procedure 106 4 i..,' ,-Admin.~ Proc. 106, Sec. 4.4.10 %.p + {V;

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pp b 46 L: c1 Y i R' a i RESOLUTION OF FACILITY COMMENTS ON THE P l .SRO WRITTEN EXAMINATION ADMINISTERED AT y 0 OYSTER CREEK ON OCTOBER.11, 1989 n: ~ SECTION 5-8 -1 .f 5; O1 Di sagree. This was discussed during the pre-examination R review and theidecision was made that the correct D answer was (a), not (b). This-_was one of the reasons 'immediate* was underlined. The correct answer is (a). 5.03 Agree. For parts 4 and 5, (e) or (g) will' be accepted l as correct-answers. For part 6,.(b) or (f) will be accepted as correct answers. .j 5.06 Disagree. The question states ' decreasing slowly ' indicating that an automatic scram is neither i mmi nent nor i nevi t abl e. The correct answer is (b). 5.08 Di sagree. While the EDG may auto start it will definitely not idle at 450 rpm, therefore (b) is clearly incorrect. The correct answer is (a). 5.14 Disagree. The question states that this is an ' unexplained increase in reactor power', furthermore I the question clearl y ref ers to the crosshatched area of the power flow map and does not refer to an unexplained criticality. The correct answer is (b). -1 5.17 Conditi onall y agree. Answers consistent wi th the intent of the precaution will be given credit provided they. ] are sufficiently specific. Example: ' Gross fuel failure

  • will accept 'High main steam line radiation conditions' not simply 'High radiation conditions' 5.20 Disagree. Thi s question was di scussed and accepted during the pre-examinati on revi ew. Procedure 9473-IMP-13OO.33, ' Core Damage Esti mati on ', at step 5.11.2.2 on page 13.0, under*section 5.11.2,

' Contai nment High-Range Radi ation Moni tor System (CHRRMS)', states 'This method is not valid if venting has taken place or if containment spray has been I initiated.'Therefore, (c) is incorrect. The correct answer is ( b ) '. Ie/F/91

emagg:; e rb Y .{O + i F.. ~ r '5.'21.Condi t i onal'l y agr ee. Terms-other.than the exact'words ~11stedrwill be accepted provided-theyr are sufficiently specific. I Example ' Pri mar y Contai nment ' - vi c e,. ' D. W. ' not J si mpl y

g.,

L ' Containment' "WC l 5.25. Agree.. However, the correct' answers. must be provi ded ~ somewhere in the' candidate's response. Furthermore,' [Li pr opo'r t i onal gradi ng: will be applied. should any incorrect addi tional 'inf ormation be provided. 5.31' Agree. onswers consistent with candidates' assumptions will be considered provided the assumptions are .rel evant? and val i d. . 5. 3D. Di s agree. OCNGG TCR 801.01, Lesson 801.01, on page 42 ! states that the basis for not restoring power is to ' Prevent ex pl osi on '. Answer.(a) applies to the sequence ~in which to restore power but' is not rel ated to the condi ti on given in the question that 'USS-1El-was deenergized forimore than 6 hours'. The correct answer. is (c). l Wn/81

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SECTION 6 1.09 Di sagree. Si nce the ' al arm-i s, i n f ac t ',' oper eble i n RUN,.

6 the correct' answer'will-be~ changed:to: (b). Credit.will not be gi ven f or (a). 6.11 Agree A-description of the' actual operation of the appropriate instrumentation will be accepted. q 6.15' Agree.'For ' Loss of'AC power',' loss'of control power.as . sensed at 1B2A' or ' loss of AC powerL to lighting panel ' 4 192A' will be accepted and given 0.5 points credit.- 6.16 Part'i all y agree. The question stated that specific-componentinumbers were not required. V-7-31 (Off Gas Isolation /A0G System Bypass) closes on. thi s isolation;' however, the procedure also indicates that V-7-29 (Off Gas Del ay Pipe Drain) closes. Theref ore, O. 25 poi nt s credit.will given for each valve. 26.18 Faci'11ty comment withdrawn. 6.20 Agree. Part b will deleted as not all senior licensed-operators nor licensed operators are necessarily trained as fire brigade leaders. 6.21 Di sagree. Answer (e) would not require f urther investigation as it states the alarm IS malfunctioning, not that a determination of whether it is malfunctioning is required. Standing Order 40, 'CRD Hi gh Temperature Alarm Bypassing' applies to bypassing inputs to a single alarm, 'CRD HI TEMP (H-5-c)', and appears to actually be based on the reason given as answer (c). The correct answer is (d). 6.25 Disagree. Maintaining level between 150 and 170 inches above TAF may minimize pressure and power transients but does not specifically ' ensure that reactor power is-maintained less than 10%.' The correct answer is (c). 6.26 Disagree. Administrative Procedure 106, Section 4.4.10, regarding the minimum items to be recorded in the Control Room Log does not require the recording of ALL Tech Spec deviations. Only equipment-related devi ations are required to recorded in the Control Room Log. Credi t for part 2.b will only be given for the ' Group Shi f t Supervi sor (GSS) Log. hdN m. .- m.--.. ..--m. - ma +r -}}

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