Text

Forwards Comments Generated by Util Training Section Associated W/Written Examination Administered on 880817
	ML20155E327
Person / Time
Site:	Beaver Valley
Issue date:	08/23/1988
From:	Sieber J; DUQUESNE LIGHT CO.
To:	Gallo R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20155E299	List: IR 05000334/1988024; ML20155E297; ML20155E327;
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{{#Wiki_filter:_ ATTACH!'Elli 2 h' N,, r yP A Duquesne @ 1.ie.n.ee u m. Noctest Group P.O. Ben 4 snmoingport, PA 15077 0004 g g gggg NDIVPN:5574 i Mr. Robert M. Gallo, Chief Operations Branch ~ Division of Reactor Safety U.S. Nuclear Regulatory Commission Region 1 l 475 Allendale Road King of Prussia, PA 19406 l .leference: Beaver Valley Power Station, Unit #1 ) Docket 50-334, License DPR-66 ] License Examination Report

Dear Mr. Gallo:

i j Please find enclosed comments generm.ted by our Training Section associated with the written examination administered August 17, 1988 at our facility. If you have any questions concerning this report, please contact Mr. T. W. Burns at (412) 393-5751. l j Very truly yours, 1 I h,, , D. Sieber /VicePresident,NuclearGroup I i l JDS/cjr Enclosure i cc: T. W. Burns t l Central File (2) i i i I 0810120245 881004 PDR ADOCK 05000334 l V PNU l-l

QUESTION 5.07 (3.20) ~ How is DNBR affected (increase, decrease, or no change) by the a. indicated changes of the following, and BRIEFLY explain WHY. Consider each case separately. Initial plant condition is operating at 95% power (1.20). 1) Boron concentration in the RCS is decreased by 10 ppm. 2) Pressurizer heaters are energized. 3) Reactor power is increased to 100%. b. Using the attac.5ed TS Figure 2.1-1, Reactor Core Safety Limit, explain (briefly) for each of the three sections (A, B, and C) what parameter is being limited (1.20). c. If Section A of the safety limit curve is exceeded, what protection would be lost and WHY (0.80)? ANSWER 5.07 (3.20) a. 1) Decrease (0.2), would increase Tave which reduces the subcooling j margin (0.2). 2) Increase (0.2), would increase RCS pressure and increase subcooling margin (0.2). 3) Decrease (0.2), would increase heat flux and reduce subcooling margin (0.2). b. Section A. Limits ave. coolant temperature (Enthalpy) at core exit to less than saturation (0.4). Section B. Limits hot channel core exit quality to 15% or less (0.4). l t i Section C. Limits DNBR to 1.3 or greater (for normal ops and nod. freq. incidents) (0.4). l c. All trips that rely on Delta Temperature (0.4). Because if Th becomes saturated there will be no change in hot leg temperature and will no longer be an indication of power (0.4). REFERENCE KA 00300 K5.01 3.9 002000 K5.09 4.2 002000 G0.05 4.1 193008 Kl.05 3.6 BVPS THERM 0 TEXT Pgs. 17 through 20 i BVPS LP-THO-7 E0 12 and 14 002000G005 002000K509 003000K501 193008K105 ...(KA'S) 'i I l . - -. ~, _., -, - -

COMMENT I 5.07.0.1 The answer key is correct for the initial effect on DNBR. 5.07.2 However, the final effect for Part I would be "no change" if auto i Rod Control is assumed since Tavg will be returned to setpoint i i and for Part 2 would be "no change" since the pressurizer spray valves would open to return pressure to setpoint. Please accept either answer since the question did not specify whether the initial or final effect on DNBR was desired. l I I l 1 l 1 l I i i 4 4 4 i f s i i i I I i f I l l f 4 I i 1 i i i \\

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QUESTION 6.03 (3.00) Listed below are valves that position in response to an ESF signal. Identify the exact signal (SIS, CIA, or CIB) that actuates the valve and whether the valve position, after ESF actuation, is open or clostd. a. CCR to RCP IB (TV-lCC-1038) f b. RCS Letdown (TV-lCH-204) c. Stm Gen 1C Blowdown (TV-1BD-1000) 1 d. ORS Spray Pump 28 Suction for Containment (MOV-lRS 1558) e. RCP Seal Return (MOV-lCH 369) f. Prim Grade Water to PRT (IRC 72) 9 PZRVaporSpaceSample(TV-ISS-ll2A1) h. Coolant Charging System (MOV-lCH-289) 1. Main Condenser Air Eject Vant (TV-ISV-100A) i J. BI Tank to Cold legs (MOV-ISI 867C) ANSWER 6.03 (3.00) I a. S CIB b. S CIA c. S CIA i, d. O CIB e. S CIA f. S CIA r g. S CIA 4 l h. S SIS I i. S CIB j. O SIS i 2 l j (0.15 for position) (0.15 for signal) 8 4 REFERENCE BV-1. Chapter 47, Table 1 { ] KA 103000 A1.01 4.2 BVPS LP SQS 47.2 EO No. 4 I 103000A301 ...(KA'S) } l COMMENT ) 6.03.e The RCP seal return valves are MOV lCH-378 and 381. MOV-lCH 369 i } 6.03.f does not exist. IRC-72 is a check valve which does not receive i l any ESF signals. This is an error in the referenced table from j l Operating Manual Chapter 47. Please change the answer to Part f j to read "This valve does not receive an ESF signal". l i j i

{. QUESTION 6.06 (2.20) The reactor is operating at a steady state 25% power, all control systems are in automatic. Turbine load is increased to 100% and the controlling steam pressure detector for #1 S/G sticks at the 25% value. Explain how and why this will effect #1 steam generator level - assume no operator action. Continue your explanation to steady state conditions or plant trip. State any assumptions made. ANSWER 6.06 (2.20) m stm - K(P stm) (delta-P) Since the steam pressure component stays constant (it should go down) while the delta P increases, indicated steam flow will be higher than actual steam flow (0.6). The summing network for flow will send a signal to the flow controller to open the feed regulating valve (0.5). 3 I As level starts to increase, the level error will signal for the FRV to close (0.5). Eventually, the flow error will be cancelled out by the level error, and the FRV will be positioned such that steam generator level will operate at 1 a steady state level higher than desired program (0.6). ) REFERENCE BV 1, Chapter 24 Section 1, Pages 17-20 BVPS LP SQS-24.1 EO No. 6 4 KA 059000 Kl.04 3.4 059000 A3.02 3.1 059000A302 05900CK104 ...(KA'S) COMMENT 6.06 The answer key states that the flow error will be cancelled out I by the level error and the steam generator will operate at a i sttady state level higher than the desired program. This is not true. The level controller is a trocortional intearal controller 1 and it will continue to vary its output and change the position of the feed regulating valve until the level error becomes zero, q The flow error is strictly a proportional _ signal. Please change the answer to indicate that the steady state level will be at the programmed value. Refer to Figure 7.7-6 from the UFSAR. i i I l

REV. 0 (1/82) f, TL*RBlut IMPUL$t STAGE PRES $URE ) LEYtl STEAM GENERATOR PROGRuottR WATER LEVEL SIGNAL I Y sTEAx now Ftt0=ATER SIGNAL FLOW SIGNAL FILTER I'I E (-) g,) g 4.) i 1r l PI COMTROLLER gggpgg REMOTE MANUAL PO$l Ti0ttlNG Y ( GAIN UNIT Y j PI CONTROLLER PI CouTROLLER f I t WAIN Ftt0 WATER STP 633 Ftt0 WATER CONTROL. VALyt CONTROL VALyt OYNAMIC$ DYNAMIC $ l l l Y Y WAlm Ftt0 WATER gtP A33 pg[DW AT!R CONTROL VALvt POSITION CONTROL VALyt P031710N l 1{ FIGURE 7 7-6 BLOCK DIA6RM OF STEM 6ENERATOR WATER LEVEL CONTROL SYSTEM l!Avit VALLEY P Cd i t $fAf!0h Vh!T N0. 1 WP0 Aft 3 F!hAL $4FETT ANALY$!$ IIPott 1

3 QUESTION 6.09 (3.00) The following questions relate to the auxiliary feedwater system, a. What are four of the six conditions that will start the i electric-driven AFW pumps (FW P-3A and 3B)? (1.00) b. What four conditions will prevent auto start of the electric-driven AFW pumps (FW-P-3A and 3B)? (1.00) c. Auxiliary feed throttle valves, MOV-lFW-151A,B.C,0,E.F receive AUTO cpen signals from what components? (0.50) l d. Briefly explain how, when using the dedicated AFW pump (FW-P 4), feed J flow and steam generator levels (component and location (s)) are controlled. (0.50) l ANSWER 6.09 (3.00) ) (Any fot.r at 0.25 each) a. 1) Control switch to start 2) Two of three SG lo lo level 3) Both main feed pumps tripptd 4) Opposite AFW start signal nat followed by discharge pressure 5) Safety injection signal (train A for 3A and B for 38) 6) PNL AMSAC I (Four at 0.25 each) { i b. Control switch in pull-to-lock or stop i Bus loss of voltage (IAE or IDF) Diesel loading sequence (not timed to start yet) j Motor electrical protection c. Breaker closure of either MD AFW (0.25) { i Steam driven AFW steam supply trip valves (TV MS-105A and B) not fully open(0.25) I i j d. Feed flow is manually controlled at the feedwater bypass control manifold (0.25). l jl Level information is from the Control Room or the backup indicating panel (0.25). I REFERENCE J BVPS OM 1.24.1 Pages 15 through 18 and 3 .j BVPS LP SQS-24.1 EO 7 i KA 061 000 K4.02 4.2 061 000 G0.09 3.9 061000G009 061000K402 ...(KA's) l .i i I I 1

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- _ = _ - _ _ B.V.P.S. - 0.!!. 1.24.1 INSTPC ENTATION AND CONTROLS (continued) Its relay rack (see power supply and control location list). There is also a TEST OPEN pushbutton for each trip valve located at the valve. j l j Prem the benchboard. [TV-P-2] is started by placin.c either or both trip l valvo control switches in open. [W-P 2) is stopped by closing the f j open trip valve (or valves). In AUTO, [W-P-2) is started by a Lo Lo l steam generator level (2/3) in any steam generator, a (2/3) reactor j coolant pump bus undervoltage (buses lA and IB, IA and IC, or IB and IC) or PNL-A!! SAC. i l When [W-P-2) is running due to an automatic start signal it cannot be I stopped using the benchboard trip valve control switches. Steam supply l 1 to trip valves [TV 1!!S 105A and B] can be isolated by steam supply } isolation valve [t!OV 1!!S-105). Valve [t!0V It!S 105) is controlled by a { l benchboard CLOSE-OPEN switch. [?!OV l!!S 105) is normally open so [W-P- ) is available for automatic start. Auxiliary Feed purps 3A'and 3B [W-P-3A. El i Auxiliary feed pumps 3A and 3B are driven by 4160V electric motors. j Pump [ W P-3A) is powered from emergency bus IAE and [W-P-3B] is r j powered from emergenty bus IDP. See Figure 24 8 for [W P-3A) logic ( W P 3B, identical). [ W P-3A) starter (breaker 1AE-16) has breaker f l e.itrol switches on both the benchboard and the emergency shutdown panel. Control is transferred to the emergency shutdown panel by a transfer pushbutton located at that panel. Cot. trol is transferred back to the benchboard by resetting the transfer relay located at the l l breaker switchgear. Control logic is identical at both panels. ( j! [W P 3A) is started by: [ t i j 1. Placing the controlling control switch to START l ] 7, Two out of three steam generators baving Lo Lo level i ) 3. Both main feed pumps tripped f 4 Safety injection signal (train A starts [W-P-3 A) i and train h arts-4 m R 211 l l . 5. [W P 2) start signal (not f ollowed by [W-P-2) { _dischar_geg ressure) j e. PS L-A>!S AC i [ W P 3A] is stepped or prevented from starting by: i 1. Placing the controlling control swi.tch in PULL To LC;K or STOP l 2. IAE bus loss of voltage 3. Diesel loading sequencer (not timed to start yet) flotor electrical protection f l I' 1 l ] l 3 ISSUE 2 i REVISION 15 i i i i

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t j INSTRUr!ENTATION AND_ CONTROLS (continued) [FCV TW 102) will be closed by de energizing solenoid operated valve lSOV TW 102] provided any one of the following cor.ditions is met: l i i a. Turbine driven auxiliary feed pump [W p 2] inlet steam pressure j is below 355 psig. l l b. Turbine driven auxiliary feedwater pump [W P 2) suction flow is greater than 505 spm. i In addition. [FIS-N 151A, B) and (FIS N-152] will cause annunciation in the control room if recirculation flow remains below the recirculation valve open setpoint for 10 seconds. a i Auxiliary Teed Throttle Valves { !!OV-1N-151 A. B. C. D. E, T } Each steam generator auxiliary feed water supply line contains two parallel piped, redundant. motor cperated throttle valves. Steam i generator IA auxiliary feedwater flow is controlled by {t!OV-lW 151E ( and T*. steam generator IB by l?!0V-1W-151C and D] steam generator IC by URV 1W 151A and B]. All six valves are normally open, however. l they_.also receive a back up auto open signa b The auto open s a gnalT' j are :nitiated by the motor driven aux. feed pumps [W P-3A or M) i breaker closure or the steam driven pump [W-p-2 } steam supply trip, + 1 valves [TV !!S-105 A or BJ not__ fully closed. Refer to Figure No. 29 4 f or [?!OV-W 151E] logic (other 5 identical). Once initiated, the l A.T.C. main.ains the open signal for 30 seconds. This signal does not l { prevent valve operation by the throttle valve control switches, but if t i the control switch is released within the 30 second period the throttle 1 valves will reopen. / See Figure Ob9 for [?!OV-1W-151El logic tother five identical). l'DV-l IFW 131E] has two three position (CLOSE-OPEN spring return to NOR!!AL) 1 control switches; one located on the benchboard, the other on the emergency shutdown panel. Control is transferred to the emergency t shutdewn panel by a transfer pushbutten located at that panel. Control f is transferred back to the benchboard by resetting the transfer relay at its relay rack (see power supply and control location list). Control logic is identical at both panels. I l:10V-IN-151E ] travels in the open direction when the controlling i switch is placed in the OPEN position. Valve travel stops when the f ) control switch is released. [!!OV-lW-151E] travels clcsed when the l controlling control switch is in the CLOSE position. Valve travel i l stops when the control switch is released or t he full cpe.1 or closed i j positions are reached regardless of switch position, i l l I 1 l i 1 1 1 I j ISSVE 2 l REVISICS 15 I

i \\ r { QUESTION 7.02 (3.50) o l i Answer the following questions concerning E-0,-Reactor Trip or Safety In,jection: a.. The Main Turbine has not tripped and you attempt a manual trip as required, with no response. What additional actions are you required to take in order to shutdown the turbine? (1.00) l b. List three plant conditions that require SI initiation? Include setpoints. (0.75) i c. What four parameters are checked to determine if SI flow should be terminated? (1.25) d. Following an SI reset, what condition must be met before an automatic l reinitiation of SI will occur? (0,5) ANSWER 7.02 (3.50) l t a. Close main steam trip valves (four at 0.25 pts. each) Runback the turbine i i Close main steam bypass valves j Close non return valves i j b. 1) Pressurizer pressure < 1845 psig (three at 0.25 pts. each) i 2) Containmer,' pressure > 1.5 psig } 3) Steamline pressure < 510 psig c. 1) RCS subcooling criteria met (0.25) [ 2) Feed flow to intact SG's (> 350 gpm) (0.25) or narrow range level in at least one intact SG (0.25) 3 3) RCS pressure (stable or increasing) (0.25) 4) PZR level (> 57.) (0.25) d. Reactor trip breakers must be closed (0.5) REFERENCE ) BVPS E0P E-0 Pages 3, 5, 16, 19 1 KA 000 007 EK 3.01 4.6 000 038 EK3.09 4.5 } BVPS LP LRT VII 61 E0 81 i i LP LRT VII-62 EO Al I i i 4 5 i l I 1

COMMENT 7.02.b "wo other plant conditions require SI initiation in E-0. These are contained on the left hand page. Please add "RCS subcooling less than attachment" and "Pressurizer level less than 5%" to the answer key as alternate acceptable answers. l ) I i i

t } I QUESTION 7.07 (2.75) i The plant is operating at 100 percent power. Urgent repair of a motor o)erated valve must be performed inside containment to prevent a plant j slutdown. The repair is expected to take one (1) hour. The raintenance man that is supposed to do the repair is 25 years old, his lifetime exposure on his NRC Form 4 through the last quarter is 33,000 mrem. He has j received an additional 700 mrem this quarter. The area that he will be j working in has a radiation field of 675 mrem /hr. gamma and 450 mrem /hr 1 neutron. i a. Can the man selected complete the task without exceeding any NRC 1 (1.75) exposure limits. Show all calculations and state any l assumptions made. t b. Technical Specifications, Section 6.12, requires personnel that enter i high radiation areas exercise one of three specified options. Briefly l list TWO of those options. (1.00) j 4 i l l AN5WER 7.07 (2.75) l j a. 5(N 18) = 35 rem lifetime exposure allowed (0.25) Lifetime to date - 33000 mrem + 700 mrem = 33700 mrem (0.25) Total lifetime available - 35000 mrem 33700 mrem = 1300 mrem (0.25) Total quarterly exposure available 3000 mrem - 700 mrem = 2300 mrem l 4 j (0.25) Lifetime exposure is more limiting (0.25) i 675 mrem /hr gamma + 450 mrem neutron - 1125 mrem /hr total (0.25) l 1 1 Yes, man can perform task. (0.25) (Any two at 0.5 pts, each) 3 t b. 1. Carry a radiation monitoring instrument which continuously [ indicates dose rate in the area, t 2. Carry / wear a radiation monitoring device which integrates the l dose rate and alarms at a preset value. 3. Be accompanied by a qualified individual who is equipped with a j radiation monitoring device, i REFERENCE j i i KA 194 001 Kl.03 3.4 l f BVPS LP RC 01 E0 19, 23, 27 l l 19400lK103 ...(KA*S) i 1 i 1 l ll } )

COMMENT 7.07 a The statement "Lifetime exposure is more limiting' in the answer key is worth.25 points. The question does not ask for this information. Please delete this from the key. i l l r l I i 4

I a l. QUESTION 8.01 (2.40) The plant is operating at 75% power and the latest leak rate data shows: 13.2 GFM - Corrected RCS leakage rate I 1.5 GPM Leakage into the Pressurizer Relief Tank i 1.2 GPM - Leakage into the Primary Drains Transfer Tank 3.4 GPM - Leakage through SI 23 RCS Loop 1A, cold leg isolation (previous leakage rate was 1.6 GPM) 0.8 GPM - Total primary to secondary leakage 4.2 GPM Leakage past RCP seals i 1 What RCS leakage limits, if any, have been exceeded? Refer to attached l Technical Specifications. Show ALL work and STATE any assumptions. i t ANSWER 8.01 (2.40) RCS Pressure Isolatinn Valve Limits exceeded (0.70) i (3.4-1,6)/(5.0 1.6) = 1.8/3.4 > 50% (0.50) l UNIDENT!FIED Leakage limits exceeded (0.70) i 13.2 - (1.5 + 1.2+3.4+0.8+4.2) = 2.1 GPM (0.50) l l I REFERENCE RS 3.4.6.2; TS 3.4.6.3 KA 002020 G0.05 4.1 BVPS LP 505 6.5 EO No. 7 002020G005 ... (KA'S) j i COMMENT 8.01 If the assumption is made that all of the.8 gpm primary to i secondary leakage is from one steam generator, then the 500 gallon per day tube leakage Technical Specification is also exceeded. Also, the total identified leakage is 11.1 gpm so this Technical Specification limit is also exceeded. Please edd this to the answer key. l t i i

l. l QUESTION 8.03 (2.00) { Using the EPP/ Implementing procedures provided, classify the following i events. Consider each separately. For each event STATE: a. The classification b. The justification for the classification c. The Tab No. of the implementation procedure ( t 1) During a routine surveillance of the No.1 Emergency Diesel l Generator on your shift, an electrical fault caused a fire in the i output breaker. The breaker cannot be repaired for at least 24 ( hours. (1.00) l 2) Chemistry has just reported the following Steam Generator [ microcurie / gram Oose Equivalent I-131 activity levels: lA, 0.13 l j microcuries/ gram; 18, 0.09 microcuries/ gram; IC, 0.10 i microcuries/ gram. (1.00) l ANSWER 8.03 (2.00) (Three at 0.33 each) i L i a. Site Area Emergency l j Affects safety systems necessary for shutdown 1 Tab 26 EPP/I l i 1 (Three at 0.33 each) b. Unusual Event I I Steam Generator activity level exceeds 0.10 microcurie / gram equivalent l 131 i Tab 6 EPP/1-1 i l i l i I REFERENCE l l j EPP/ Implementing Procedure EPP/l-1 l j KA 194001 A1.16 4.4* i j 194001All6 ... (KA'S) l l l I i l l i ]

i 3 1 1 COMMENT i 8.03.a Since no information was given in the question on whether problems existed with the electrical distribution systems other than the #1 Diesel Generator, and no information was given regarding the duration of the fire, or what mode the plant is in, 4 not enough information is given to positively clissify this event. Depending on assumptions, many different classifications are possible. A site area emergency and the resultant activation of utility, county, state, and federal response facilities is not i necessary fur one inoperable Diesel Generator. We ask that this l l question be deleted from the exam due to insufffcient information 2 provided in the question. l l 5 1 4 I 1 i i t l i [ l l ? i l i 4 1

l 1 QUFSTION 8.04 (1.80) 1 ] You are the on duty Nuclear Shift Superviter. The RCS is at normal Tave i with a Reactor Startup about to commence when the maintenance foreman i informs you that the 1A containment Hydrogen Recombiner failed its six (6) { month surveillance test. He estimates that he may be able to repair the 1 unit in twelve (12) hours. He also noted that the IB Recombiner passed its j surveillance with no problem. WHAT impact, if any, will this have on the ] plant startup and why. 1 ANSWER 8.04 (1.80) The startup must be termitiated (0.6) plant is about to enter mode 2 (0.6) 4 and mode changes cannot be made with reliance on an action statement (0.6). REFERENCE BVPS LP SQS 46.1 EO No. 7 KA 028000 G0.ll 3.5 BV TS 3.6.4.2 028000G0ll ... (KA'S) COMMENT 8.04 This question cannot be answered 'sithout referencing the l applicable Technical Specification to determine whether Technical Specification 3.04 is applicabic or not. Since the Technical Specificaticn was not provided we ask that the question be deleted from the exam, u ) l 1 4 l 3 i

.--v w-

) l QUESTION 8.05 (2.70) Answer the following questions concerning "Operating Shift Complement and Functions" as discussed in BVPS ON Chapter 48, Procedure B. \\ a. The plant is operating at 100% power, you are the on-shift shift l supervisor. Your NCO has become seriously ill and you have sent him 1 to the hospital. Can the plant continue to operate? If so, for how ] long and under what conditions / guidelines. (1.20) b. Who has the authority to restrict access to the Control Room? (0.50) 1 c. List four (4) of the seven (7) people that shall be granted access to the Control Room regardless of the situation. (1.00) I } ANSWER 8.05 (2.70) i a. Yes (0.20). The plant can continue to operate for 2 hours (0.50) provided that immediate action is taken (callout) to return to the minimum shift complement (0.50). I b. The Nuclear Shift Supervisor (0.50) c. Nuclear Operating Supervisors (Any 4 at 0.25 each) Assistant Plant Managei Plant Manager i Senior Manager, Nuclear Operations Manager, Nuclear Safety Vice President, Nuclear Operations Senior Vice President, Nuclear Group i i REFERENCE BVPS LP SQS 48 1 EO No's 1 & 5 1 KA 194001 A1.03 3.4 I BVPS CM 1/2.48.1 Procedure B 028000G005 194001A103 ... (KA*S) I i l ) COMMENT l 8.05.c Some of the job titles have been changed. Please change Senior i Manager, Nuclear Operations to General Manager, Nuclear Operations, Senior Vice President Nuclear Group to Executive 1 Vice President, Power Generation, and Vice President Nuclear } Operations to Vice President, Nuclear Group in the answer key. l l l l 4 i l 1 l

QUESTION 8.10 (2.75) 1 Answer the following concerning Safety Limits and Limiting Safety System t Setpoints(LSSS), a. WHAT are the Th'0 (2) Safety Limits and WHAT parameters must be i monitored to determine if a Safety Limit has been exceeded. (1.25) ] b. What is the BASES for the LSSS reactor trip setpoint values specified j in Table 2.2-1 of the Technical Specifications? (0.50) i c. What notifications must Le made if a Safety Limit is exceeded. l Identify those notificaticns that are required to be made within one j hour or less. (1.00) l \\ j ANSWER 8.10 (2.75) a. RCS Pressure (2735 psig) (0.25) l Reactor Core (0.25) Thermal Power (0.25) i Pressurized Pressure (0.25) Auctioneered High Tave (0.25) l I b. To ensure that the Reactor Core and the RCS do not exceed their Safety !l i Limits. (0.50) c. Reported to: NRC(0.25)withinonehour(0.25) l Senior Manager Nuclear Operations (within 24 hours) (0.25) j ORC (within 24 hours) (0.25) i l 4 r s j REFERENCE j l KA 028000 G0.05 3.6 i BVPS question bank no. 8.1 1 BVPS TS Section 2.0. 2.2, and 6.7 ) j 028000G006 ... (KA'S) j ] CONMENT l 8.10.c The question asks for notifications required within one hour or j less if a safety limit is exceeded. The answer key lists two 1 notifications required in 24 hours. Please delete these from the j answer key. 1 I I 1 I l

ATTACH talT 3 ~ U. S. NUCLEAR REGULATORY COMMISSION SENICR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _DEGVER_29LLEY_112_______ REACTOR TYPE: _PWR-WEg},_________,,,,__ DATE ADMINISTERED _@@f9@f1Z______________,,_ EXAMINER: _DR__IGGS-__t L. CANDIDATE: __._J,______, IU9ISUCII9NS_I9_CONQIp@IE1 U s t-separate paper for the answers. Write answer s on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing geade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. % OF CATEGCRY . C F CANDICATE'S CATEGORY _ _ V_ A_ L_ U_ E_ _ __TO_TA_L_ _ _ _ S_ C_ O_ R_ E_ _ _ _ _ V_ A_ L_ U_ E_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ C_ A_ T_ E_ G_ O_ R_ Y_ _ _ _ _ _ _ _ _ 291@9-_ _2E199 S. THEORY CF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS _EE1E9__ _29199 ________ 6 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION _EE:99__ _29199 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTHOL _EE 99 _.22199 ________ B. ADMINISTRATIVE PROCEDURES, 1 CONDITIONS, AND LIMITATIONS { 199199__ Totals Final Grace All oork cone on this examinatten is my can. I have netther gtven ner received ato. Candidate's Signature l j

- ~ ___ . - _ - _ - ~_ i i l j + t i l NRC RULES AND GUILELINES FOR LICENSE EXAMINATIONS ) {During the administratten of this examination the following rules apply J j} l. Cheating on the es aminati en means an automatic dental of your application and could r esul t in more teveru penalttes. 1 1;. Restroom trips are to be limited and only one candidate at a time may I i leave. You must avoid all contacts witn anyone oututde the examination t' c o ne to avoic even the appearance er possibility of cheating. 3. Use black ink or dark pencil only to facilitate legible reproductions. I !4 Print your name in the blank provided on the cover sheet of the j examination, f l 0. Fill in the date on the cover sneet of the examtnatten (if necessary). l 1 ft. Use only the paper provided for answers. I l i7. Print your name in the upper right-hand corner of the first page of each l 1 section of the answer sheet. I i I t IB. Connecu t i vel y number each answer sheet, write "End of Category as ) apprcpriate, start each category on a new page, write only on one pide of the paper, and write "Last Page" on the last answer sheet. ] I 9. Number each answer as to category and number, for example, 1.4, 6.3. Ij l 0. Skip at least three 1ines between each answer. 411. Saparate answer sheets from pad and place finished answer sheets face down en your desk or table. I; 10. Use abbrevtations only ni they are commonly used in faciltty,1 i t e r,a t u r e. The point value for each question is indicated in parentheses after the J questton and can be used as a gutce for the depth of answer required. l Il4 Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not. I ? \\ ?tS. Partial creott may be given. Therefore. ANSWER ALL PARTS OF THE l GUESTION AND DO NOT LEAVE ANY ANSWER BLANK. jl6. If parts of the examination are not clear as to intent, ask questions of l the gggm(ggt only. ]l7 Ycu must sign the statement on the cover sheet that indicates that the j work is yuur own and you have not received or been given assistance in j completing the examination. This must be done adter the examination has i been completed. I

l 1 k 4 4 l 1 I 4j ;G. When you complete ycur examinatten, you shall: [ J t 4. Assuoble your examination as dollows: j t (li Exam cuestions on top. 4 } (2) Exam aids - figures. tables, etc. (!) Answer pages including figures which are part of the answer. i j b. Turn in your copy of the eaamination and all pages used to answer I the examination questtens. l c. Turn in all -; c r a p paper and the balanen of the paper that you did nat use for answering tne questions. l a. Leave the examination area, as defined by the examiner. If after l leaving, you are dound in this area while the examination is still f in progress, your license may be denied or revokea. i t i l ( i c t \\.i f } I l J l ) I ,I i i 1 l J i l I l l i i l I i t

~ + 1 _ _ ;*i ._,__,.U C L C A G------.-..._:=y------------=-..:.._ DC);En _'ayr r e g g, :. r.;g _.,g,, J u,,.g _,g, ;,D pgg 2 a g .. m I 1 , e. ,.., J ,l.r,, um. .s -o, i 1 a. e alan; 1s cureent1, 1n Mace 3 .41 t n one teatn of PHR in ape'attOn. n 0 s < +e a e c, n i n a l RHR 1en cf 4000 gpm a n e) a reduction in temperaturo i t' GF acenst the AHR 1aat i.* x c h a n g e r. The reacter angineer int'cens you that a, t '.e calctalated detay heat 1 cad ts 0. 2 ". o f rated power. Assume i t

htt you have maximum component cooling water flow and minimam RHR i

bypass 4 1 O r.. With the a;o' e 01 ant Londitions it the o.1 e tratn of RHR i comoving all the decay heat ::et ng genc>r ated at th t i mo ? Show your calculattens und state your a s :.u m p t i e n t.. (1.50) i 1 1 i i i i l 1 i I I I I I I l i { l 1 (***** CATEGORY 05 CONTINUED ON NEXT PAGE

- - - - )

i

l ~ CRV CF lJLCLE AR POWER PLANT CPERATICN. FLUICS, AND PAGE 3 .y. - - - - -..c y::c,y 7 r e

.r n t,m--------

JLCET:ON ~.22 (0.03) J,.!cecq cilut:en TO 730 opm inceaanes tne source ranJe atton to 132 ~rq. C ar. :.; *he d i l uti en. Xenon c.cn c en t r a t i on changed. 47 was the Moen ' t: REACTIVITY centriout:en cur:ng tnis evolution'

N!T AL plant conditions:

Mode 3, SQL Eocen concentration, 720 ppm All shutdown banks withdrawn Actual reac ti vt tv p-osent in the core is minus 4% delta r: / V Sour.ce range counts is 103 St.ferentia; Coron sortn in minus 10 p;m/ ppm i l (**t** CATEGORY 05 CONTINUED ON NEXT PAGE

- - - - )

"U 27 1UCLEAR. v w.n - L :" N...- r.QA7!CN. OLL'DS. AND DAGE 2,--- ECFY t .. _. :._ u 1 M A_ _. -.-- l 1s u l ~- s. m H n..,,, ,.. c., ) I u- ~~ a. E.pla:n t] C t h HOW A N D '. H Y ;Fe 'cilcsing actors affect tii'orential f uor an .<or t h ( m.o r e n og a t.1 - e. '.e., s.egatavs ur no :nanger, c Sorcn concentration increase (0.75) 2. Moderator temperature decrease 'O.75) Fission pecauct buildup (0.75) 4 Core burnup from POL tt ECL

v. i t h CCFstant rod positjen (0.75) b.

Why does the critical borun conecntrat:en :J e c p rapidly from Z to 130 MWD /MTU of burnup as seen in Figure 17 (0,5) (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****>

N_o. _ _ _7_9 C R _< i_ _ _ _ _ N & L_ _C A _R. _ P C_ W E_ _R _ O L.. A N_ _T _ U_ P.E. P_ _A_T _I _O N _ O L_ U_I D_ S_ _. _ A_ N_ D Pf4GE D P -_-___..,\\ .T. o. ;.

m..J r

,. 34 ... mp ) m~ 'nen would a rod be worth more -.i it were cropped whtle at power or if . re ,tuc. cut .v h 1 ] ? al! a t t* er t Cd5 ere ;nserted' EXPLAIN. r 1 l. I l (e**** CATEGORY 05 CONTItJUED ON NEXT PAGE

- - - - )

l l ~. _ - _ - - - _ _. - - _ - - - - - _ - - - - - -, - - _. - -

.-c, ,o ,- -. e r ,7 = - - -.. - - : '= = = = - - - - - y = - - = ' - = :. q c, 7 --.. = u :. - ~ = = 9 -.- 1. - - g. n ggg 07MODYNA*!~3 w r~ s L c i. s..s

m.. vo n.

m ..m .0. 3 7e- :>i l r r.. p l a i n .m *' W ict :.nl i r.:r o t c d procuurt:Or levet inutruments .: u not provide accur ate presuuri:er level i n d i c.a t i on wnen the plant J.,1 .' ode 5 ccid u h u t d a.~ n ). I.9 c l u rj e in y o ur-di scun i on the .:i r ec t i on -f s r r or. (1.50) u. S r t o f l ', g> plain what h a p p e n ", in the pr ent;ur i c or to help maintain 7CE pecsturo during an cutsurge of water. (1.00) (***** CATEGORY 05 CONTINUED CN NEXT PAGE *****>

1 {. TL*ECPY CF ;UCLEAR PCWEP PLANT CPEPATION, FLUIDS. AND CAGE 7

. :- : 2_-

p;.,., - e QUESTION 3.26 c 2. 2 0.) The p l an- ~as just trippec from 100% power due to a loss of all RCPs, after an +<tenced run (4. n = n t h c.i at full ;ower. Natural circulaticn has been estaolished with tno folicwing paramoteru: Decay neat 2.3% of full power Th is !?O F Tc is 55: F a. Calculate the percentage of full flcw through the core. (0.50) 5. Wnat ar e THREE conditions t.h o t will ennance natural circulation and explain WHAT each condition does to help natural circulation. (1.50) i l i (***** CATEGCRY 05 CONTINUED ON NEXT PAGE

- - - - )

1. 4E_?, 2: ;UCm u :Ti 'C t.C 4 F L.^ l i T TERAT: CN. 7 L.u l :-L. AND PAGE E

~gpq.,g--g-------------~~~~~~~~~~-------~~~~~---

..,--.,JJ ..J.u7 .. ~J ' t. uca: t a.

c w i t.

CNER affectec ' i ncr ease, necrease or no cnange) by trie indicated changes of the following and Briefly explain WHY. Consicer each case separately.

nitial plant condition is operating at 95%

power (1,20). 1. Doron concentration 2m the RCG ic decreased by 10 pom 2. Pressuri:er heaters are energi uc 7 Reactor power iu increased to 100% 0. oing the attachuc '3 figure 2. 1 '.. Geactor Ccre Sa4 9ty L;mit explain (briefly) for each of the three sections (A,3 L C) what p ar amet er is teing limitec ( 1.20).

. If acetion A of the cafety limit curve it exceeded what protection

.,cu l d be icst and WHY (0.80). J

\\ '"ECAN CF,UCLEAR PCWER !. AN T 7PEGATION. CL.CIOS. AND PAGE 9 s. 7'- p------------------------------.--------

21'-1 v Lt-_T9 #~%

N i. J -.uS ,% f %, O O - co ~or each of t9a following evolutions, : tate HOW (i ncr aase. decrease or no n a n.; e > E H'J T O OW N MARGIN ' ;: e r 'S de'in;tiani would Se enAnged 4 rom the s 'l J I ' I CL plant condition g;ven by going to the NEW plant condit:cn. Assume t h.n t all systems are :n automatic, a.

he ;;1 an t is in MODE 5

.9 hon a cnarging pump is accicentally started 'U3ulting :n the injection of 100 gallans of boric acid into the RCS. b. The plant is in MODE 4 with all Shutdown bank rods withdrawn to the 'ull out cost tion when alant temperature is increased by SOP. c. ' n.2 plant.; at CCD F uhen all l u t d o.vn aank Ods ar e withdrawn, d. '"v pl am .3 at CC ". power when a ccatrol red drops.ato the corn, the reactor DCE3 NOT trip. (***** CATEGORY 05 CONTINUED CN NEXT PAGE

- - - - )

i i u _. _ _ _ W c_.9_ _v _ _: :_ _. u_ r. L. E_ _A c_ _ _.c '_J _:.; E _n _ _: :. A_ N_ T _ _ :_ R. u_ _ _T0..'s_. _ _-. J_._I D 9 _.J N.D. O r4 G E ..) I 7 i .=_"5.,ma* ge, # a

r'~

. _ = _.'_ g = =

d i l l ...,;,7 i. ww,. + t; uut a. Wnen 1cading :ne care ; ' ve.. r ; .c et;oling) nea.ran catec :e actitien a; :r ta,t. 2

wr 1.

o' c n -. c n z, v a t i v e ta 1.1:: >re care -....s 4.w

.~ c a e t o c ; c e.,

_ plo: n '.s e. r. ( _..20) b. t.s jiOG the rate Of Oct.;tive r c dC f 1 V ; '. V.nGGFtiUn r a t e '-a f 4 o c t the cour ce runge ccont level at r

t t a l i t. v ?

Enplatn W61v. (1.00) 1 j i i I f 1 t ) i i ) (***** CATEGCRY 05 CONTINUED ON NEXT PAGE t****) i t 1

e 1E CP'r 57 NUC;. EAR ?ONER F' ANT ~ i: E R A T I C N. ?LU: DS. AND CAGE 11 ..' ' ~ ~.,-..,,...i.,.,,.,--. ..s. n, :. -,., J _.<.3 uJ : .t 1 ,,4..,.ci Answer tne 4alIcwing questicns TRUE c- "ALGE. a. Celayed neutrons ar e morc ilkel/ to esc. ape e c ', o r' a 'i t e c.2ptura t1an p r C TIO t neutrons. b. Ef iec t i /e C?l ayeL neutron fraction changes over core life cue *o the Ju11aup of Pl u tcn t u<n and *he decle' tion ot U-235. c. Ef8ettivt? del a /ed neutron fraction increases over core life. d. Oel2yed !eutrons M.h e a greater ef f f ec t on reactor period after 3 c q a t i v 0 "eact1itty i n uer t i on than.3fter a posttise 'eactivity additien. l ) l l i (***** END OF CATEGORY 03 e****) 1 a 1

2 s - - : ;. - T cvcir : nFC'"N C"';T": LND 'v5T7 - --- : : = : 1:= = b'-- t=1---- su---UM="TAT'EN-9 A P-1 ~- .a. u

f. n s. < o r the ;ci.

ntog auestt:rs hpecing the R e s t o u.2 ; Heat R e m o v,11 Systems a. 2.. 4,; t.cidcon u .1. 0 c <, A cual"con ate con tr olled' (0.50) r J. WC a>

15..91ninum RHR fIcw ensuroc onen adjusting c ool dow.)

it e' (0.50) .!n at w P2nure anJ

e m p e r,2 t. u r e concittons must ce Gat Gile 0 to open the R +7 nqlet v a l v e t,

( MC'/- 1 R H-7 0 0 ', 701)? (O.50', a. .s n a t condition at.; auto-close t.5 e RHR inlet valves' (0.25) l 1 l l i I (***** CATEGORY 06 CONTINUED ON NEXT PAGE 9eese) l 1 1

b.u _. _ _ _' t_._ N _T _ c v _5_T E_ _ie S _ _E_ _S _I _G _N _,_ _C _O N_ _T F _O _L _. _ A N _D _ _I N_ _S _T R_ U_ M E_ N_ _T A_ _T _ PAGE l ', .m. c '. J o.u- , _. _ ~,, J.n e w e r tne following auestions concerning the Fire Protection Systems. a. .-:n a t dev!c., i; used ta :: r o'< e n t al sc.har ge of T02 inta.in atea where personnel are working ~ (0.50) u. What : s an alternate use for tne 5 Tan CC2 (rP t t. r b i n e enclosure) w stem cesides fire protection 7 (0.50) r c. Wnat mechanism causes automatic ' Wet Pipe" (presst'r i z ed ) scrinkler actuation to occur' (0.50) d. new (wnst mechanism (s)) is the operator not1fied of an automatic actuation of an individual ' net pipe' sprinkler s< stem? (1.00) i i i I (***** CATEGORY 06 CONTINUED CN NEXT PAGE

- - 4e) l l

cf.

t '.N T 3 V (3 7 E M S DE S I CtJ. : NTROL. S t;?. Ii:STRUMENTAT: CN F4GE 14 e

---.u.,

. u.~.

Jut t sw .-.uci ic.tec below ar e "alves t at casinton in e,sec ise to 2n ESP tigna!. !aenti e< the w ac t s;gna; i3I5. C: A. nr CID) that actuates the valve 4 'd s.h e t h e r tne valvo a:Lttion. .a i t O F EO~ ittuation. 13 coen ;" c1osed, a. CCR to RCP ;B (TV-1CC-!CCE) c. RC3 Letcown (TV-lCH-C04) Stn Gen 1C Elowacwn (TV-1BD-;CCC) m. d. CRS Spray Fump 2B Euction from c ont a t r ment iFOV-1RS-1533) ( M Ct - l C h -MR,)g3 7 'd e. RCP Seal Return 4 Crim Grade Water to PGT (1RC-C) g. CIR Vacar 30 ace S an.p l e l'V-155-!iCA1) 9

clant Cnarging svetem (MOV-!Ch-2G7)

.n in c en s ur Air C,ect '/en t ITV '2V-100A> j. DI Tanx to Cold Legs (MOV-1E*-857C) i (ae*** CATEGORY 06 CONTINUED ON NEXT PAGE **ene)

= e, - O L A N. *- - Tr' 5 T E"' S 2ESIGN

L CCNT90L.,..AND INSTRUMENTATION PAGE 13

( n i t (" 7 T. ? N > si 3. .> 4 i".""u. v "An s w e r the f ol l ::wi nc quest;cns regording the Ccntrol Ar7a Ventilation 5ytte ns, a. ,t gn. c.,c en t r a t i o n s of WHAT.; a c m l; c a u u t-Cantrol Room 0- e s su r t.: a t i on .oe Camareence ( ;VS-C-3) 'c trip. (0.5J) ^ b. -i c w M&iN ( compressed atr torage tankG. an a ni n i mum, are nekded t0 -cCppl/ the Control Poem with ;00 percent 4C0 scfm) of its required air supply during a CID isolatten..ind errefly expla.n WHY the 400 scfm flowrate is required. (1.00) C. '4 9 d t CompCnent serves as arner genc y bdCkup in the ovent C4 a long of 'efrigerattan c a p ab i l i t ', of the Comp r est.or -Conden ser unitc. I VE3 4A or 207 (0.50) ( I 4 i t***** CAEGORY 06 CCNTINUED ON NEXT PAGE * ****) i ? 4 i ..-.m-

e,g---,-w-,

g-r.--- -, -,, - -,, - ~, ,y e--mm-w--m.-,- -- wn c-w -+r --eev-we+--et-w- e-*-+-e'*----~= ---^e--.~wvv-*v*-

.d: - m ', N T

- - - = = i r ' ' S :' C c 7 C, N 'u :* 2.T R.~d = 1 -@ c O L' 'u' c 7 P ' ' M c N T A T :' O N CAGC-14 =i t---

11--

na t =---- -- C,,-..,., _c. o. s...., ,a --.ii ~. 'r e s s u r 1.' er pressure t-ansm1tters 6.57-455.156 and 457) orevide six (6) a. aunctions in ado 2ticn

o indication on 89-91.

Li s t four (4) cf those

uncticos.

I1.63) c. Jefcre entering scitct plant operations the low or essur e overpressure arotection system is requirec

o ce enabled.

What conciti ns will attuate the a n n u n c. a t o r-to alert the operator that the overpr essur e pectoction system has rot '] e e n en a tj l ec. Include any applicable cetpointu :n you-answer. ( 1.00) i 1 (***** CATEGORY 06 CONTTNUED ON NEXT PAGE *****>

..._ _ _ - _. _G N T_ - - _9 Y E _T E M S .D. E..S..I. G_ N_. _ C C N_ _T P C L, 21 _ - - - - - - - - - _ _S _T R_ U. M E N_ _T A _T I C_ N_ PAGE 17 f,N D IN m.a, t.., .v= u ua 7h e oacter is operating at a steady state 2 5 *' power. all control systems ar o. r. automatic. Turnine Icac is

icreat ed to 1 0 Z'/.

a n d t tl e controlling steam pressure detector ' cr al S/G st;cks at the C5". value. Exclain n t.. and ,qy t ". i s wil' effact ti l steam Generator i civel assume no courator action. Continue your explanation to steady L. ate conditions or

l a n *

6. r l p.

State any a s.cump t i an s made. l l 1 I I I l (e *** CATEGCRY 06 CONTINUED ON NEXT PAGE *****> m m- _y 7 -m,. w-y - v. ,+ =--w-- e - -

- - - -.'. N T E V 9 'O4 S DESION. Z N PCL. ~.N D 'NGTRUMENTAT'CN RAGE 18 .u. n-,,, ,t-a. 17 C,. m.,go) s Answer the lollcWing questions concerning the eactor protect:cn (RPS) and angineered Lafeguards features system (E5FS). .s. an y

s. ' e the feedwater innes i n c l.3 t ed Dy J 3afety 2njection (0.50)
gnalS b.

L,n a t function does P-12 per'orm c 2l ow itc setootot' (0.50) c. '.s h a t accicent is each of the Jollowing trips designed to protect against .a n d can the trip be bypassed / blocked? 3pecification of auto cr nanual 2s not required. (2.00) 1. Fcwer r.ange high Positive Neuteon flur rate trip r ec %ur::er h2gh ...a t u r Icvel trip Pr essur 12 er low pressure trip J 4 4 4 (eseas CATEGORY 06 CON.*INUED ON NEXT PAGE

- ea

) i

1 a-. %.N T 'iv 5 T Er' s E. E S I O N. C C r J T V._,..ND !NSTiiUvENTATION PAGE 19 UUESTION e.08 (2.00) i l Snuwer the folicWing quentienc concerning the Reactor Coolant Pumps. eal aypasu valse,and when a. .;h a t :2 'ne puroccu af tno 'o. anc ( '. ) 2 (under what four

4) c onci ti ono) may it be cpaned?

(1.30) 3. Wh.i t type of,eal : n t"e No.1 sual. Why is a minicum differential pronsure of 200 psid across the No. 3eal required for RCP (1.00) e CDer ation? ~ t i r I l l i l i i l l i l s<s4es . r.., u s v R.,, .o .s.,,.....-- n. ve *****/ r-.

4....v u s eJ '. c. A.

'.t __2'=90I_ilSIst!3_iE5190t_20U12CLt_000_109I5utg3IeIIerj PAGE a Outer:an e.29 .:.20) The sc11cwing questions relate to the auxiii.irv feedwater mystem. a. . hat ae 4 our r: f t*e at

. :n c r : an s trat

.9 i ll start the electric driven 'rW pumps ,FW-P-3A c-NC 28) (1.00) { b. shat four concitions will crevent auto start ci the elc=ctric drtven AFW pumps (FW-P-!A AND !S.) (1.00) c. Aux 11 : ar y feed throttle v.11ves. POV-1FW-151A.D.C.D.E,F receive AUTO open signals frem anat components? (0.50) c. Driefly explain how, when unang the dedicated AFW pump (FW-P-4). feud risw and team geno atar :esolo (c omponen t and.:tation(s)) are controlled. (0.50) l l l 1 1 (ae*** CAT 2 GORY 06 CONTINUED ON NEXT PAGE

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i J

7 MJT lVSTE"5 OES:GN, p. - - - - - - - - - - - - - - - - - - - - - - - -..C. C N T A C L. C.N D INS - - - -..----- -- - - -- - - - - -. - - -.T R U M E N. T A T I O N oAGE 21 e n bm. e. -. ms n ,. a r;, s .s. List twc ;2) control ecd interlocks that.9111 inhibit uutamatic cod .v i t"crawal aniy and expldin t n te reason for each inter 1ock (1.20) anat ara L.". e 4 i s se (2) autcmatic runcttens of an URGENT FAILJRE in the cd : antr M systen. (1.23) (***** END CF CATEGORY 06

- - - - )

'7 ,riC C E C L R E S - '.CRMAL. AENCRMAL. EMEFG AND SAGE CC

:7- :::: - :n,

r----------------ENCY uz:=---

u--

u-2

r, m. r....,,. ~.,,. ,.,) mt .w m .~ 3. anac are the two reascnt ;or c, topping ali DCP's in the :aue of 2 im 111 rea' CCA' (1.C0) b. '4h a t t 's the de41ntt:on at adverse containment anditions' (1.00) ..n a t .a the reason 4cr npecifying citferent process parameter c. ,alues ander adverse containment versus normal containmene concittons' (0.50) l i (eee** CATEGORY 07 CONTINUED ON NEXT PAGE

- - - - )

CCEDU9ES - N

~~~~::::- :::: r :OPMAL. ABNCCMAL. IMERG AND PAGE 23 ~r,::pr-~~~~~~~----~~~ ENCY ~~----~~

=:.

==n =CL ::JLlab QUEST!CN 7.02 (3.50) Answer the 'ollowing ccncerntng E-0. Reactor Trip or Satety injection: a. ~5e Mato Turbine has not tripped ane you attempt a manual trip as e equi r ad, with no resocnse. What additional actions are you required 'o

ak e in er :!ur to snutdown tne turbine 7 (1.00) b.

List three plant conditions that require SI int"iation? Include setcotnts. (0.75) c. What 'nur parameters are checked to determine if 51 f l ow should be terminatec' (1.25) d. -ollowing an 51 reset, anat condition must be met before an automatic virittattar 24 51 atl' eccur' (0.5) toes ** CATEGORY 07 CCNTINUED CN NEXT PAGE eee44)

7 N C C C '.J O E E - 'jCPMOL A Gl s:W S.' i:'ERGENCY AND 74GC- '4 "-- r : -

q:,---

r,- q-. --------.. 26::.==-

=--

e q e w ;s - T '. ^ *. . a" ' '. " u" ) a An..wer tne fcl;cwtng c an c er n i rig the E023'anc Status Trees rules cf usage, a. 4ca cces LMc caer ator s now if t' e sequent:a1 performance of buttasks atthin 1 arecedure i s reQutredS (0.50) b. ' a f t er entering E-0. WHEN dces manttoring of the STAT!)5 TREE's beg utut two circumstances. (1.00) How is a particular task that a.ust be ccmpleted bef cr e pecceecing to the next step identtFied? (0.30) d. .n a t. act.o, )s reca: red ta ce performed af wn:le performing a Furctional Recovery Procedure (FRP) that addresses an Orange t e r r.)i n u s fcc Ccr o Ccol:ng an Orange tar m 'us 4cr "eat 51ch s encountered. 3rtefly explain your answer. (1.00) 1 i (***** CATEGORY 07 CCNTINUED ON NEXT PAGE

- - - - )

i

'7 CROCEDUPES - :CRPAL. ABNORMAL. EMEAGENCv AND PAG ~ '5 C

3 ::st:,F: : :- ::,; ;,-------------------------

21;-J: : - ca 2__ = CUESTION 7.34 <C.50; Answer the following questions conc:ening E-3, Steam Generator Tube 574.a t ur e. a. A NOTE prior to step 41 alerts the operator to run RCPs in ceder of pricrity. What is the REASON ter the preferred order of RCP operation. Se JPECIFIC. (3,80) c. Step 41 tells you to start a RCP if none are running. It also tells the operator that, prior to starting the RCP, the pressurtier level ts "c ce raised to gr eater than 657. (90% adversos and succooling is to de increased, based on core exit Tcs, to 25F plus subcooling listed on a t t a c hin e n t 3. What ar e the BASEG for these r equi renien t s and WHAT could 1: car .f these actionn are not taken prior to atarting the RCP' (2.00) 1 l I l (***** CATEGCRY 07 CONTINUED ON NEXT PAGE

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.'---- :CE"sLPEG - NORMAL. GBNJAF'OL. EVERGENCY 'ND

' AGE 26 TEC 7:7,-::-,;,------------------------- .. =,:.==- : : w= r, rnTery .3> .? -s Answer tre 4ollowing ausst;ons r e,;ar ci ng FR-St. Respense ;c Nuclear Power S t a r ii r. ; * ; r, A I *n 3. a. ..n a t are THREE '-) ind: cation, *nat a trto HA3 ccruered' (0.75) d. ..n a t 's the basis for t-2pping '. n e turbine. (0.50) C. Why 's tri; ping 6.he turbine wtthin 3D accends important fce an ATWS coincident Wi th a lesn of norma) feedwaterS (0.50) d. Wh S t dCtiCPG are PeCuired under immedi0.0 dCt1Cn step 6, Initiate 6 Cwrgenc, Daration of DCS" (1.50) I l i I l (*s*** CATECCRY 07 CONTINUED CN NEXT PAGE

- - - - )

i I - - _ ~, _ I

'J. GOCEDunEE - NORMAL. ABNCRMAL, EMERGENC - - - - - - - - - - - - - - - - - - - - -.Y. _ A N_ D pAGE e, _JE :::J: c-- u :CL OUEST:CN ' D6 '2.2C) In ECA-0.1. Loss of all AC Ocwer Recovery Witnout 51 Requtred. Step 16 >;uiroc the c;2 er a t t:r to. er 1 4y ratiral circulatien. What FIVE (3) p a r a t e t or r., anc thG1r 3650ciated indications /trondu would be chected by the ccerator' I 1 I 1 I l i f f (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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1 1

?.

POCECUREE - NORMCL J 8k 7-: :::;- ::., ::,---- 4M4L. CP'EAGENCY AND

,5 AGE 28 l UJ === 2 b a:2.2 = QUEST!ON ~.07 i .'5) The plant is cperating at 103 tercent gewer. Urgent repair of a motor

. er a t ce d s.il ve rust t: e ;; er ; ;r :nsc t r. s t u e _cntainmen-to p r even t a p l a n t.

3 n a ; d :..v r. The recatr :s e. a e c. t a .a tak e one (l; hour. The imaantanance man tmat .s supposed t o <;o the op ai r is 25 vears old, his lifetime axposure ;n 91L NRC Pcr9 theougn the ias quarter t: 33.220 mrom. He has r v e ; vec ..n adcit:cnal ~U0 rem tn; 3 avar

er.

~he area that ne wti1 be woePing in :ias a r ac t a t i cn i1 eld cf 673 mecm/hr. gamma and 450 mrom/hr. neutrnn. 1. Can the run celacted c;mplete the taub without evceeding an/ NRC (1.75) uposure limits. S h c., all calculations and state any assumptions made. u. ~ 2:nnical C;c:t 1:at.:n3. cett;on c.12, equires persornel 0,at ontor high radiation areau exerc1SO One of three specified options. Briefly '. a s t TWO of these cotiens. (1.00) (*?*** CATEGORY 07 CCNTINUED CN NEXT PAGE 8tss4) i

~... __f3.EE.E.E23E.E_ _UE.3[Obt_02SE5[9kt EUESEEdgy,QND DAGE

? { _d 1 :sdi_,=_2:2_2b: OUES T :CN .08 (2.231 Anawer t h c-following questions ccncerning Technt:a1 Specification Basos for Reft.eling Operationc. a. What :s the reason that l'eaciated fuel ca' rot be moved in the reactor sestel unless the reactor has been shutdo'*n 4cr at least 150 (0.60)

hours, b.

Why must at least one RHR iccp ce in operation when in mode 6? (1.00) c. What .s the reason for the minimum water evel above the reactor vessel flange 7 (0.60) (eeeee CATEGCRY 07 CCNTINUED CN NEXT PAGE

e***)
2.

DRCCEDURES - NORMAL. AENCRYAL. I"ERGENCY AND DAGE 'O - ::: - :; ; - :;.::,-------~~~~~--------~~~--

2

==itb C

=u 1 1 QUE3~*3N

7. ZG

'3.20) Anuwur the following questions :Cr ?rntog FR-H.1, Response to Lass of Nc c.: Jar 4? a t 5.' a. Jhat

the reason ice the Caut.on croceding the first st?c which

.tato: that 'ved flaw uhould rct ce es t ata l i s h ed to any 'aultec steam p?.neratcr .f a non-faulttd 3G .3 available. (1.00) b. Step ! has the operator stcp all RCPs if NO feed ficw can be (1.00) at t abl i shed. What ;u the r?ancn for this' ' Jh a t .3 t he r eason 4or the Caution pr? Ceding %tep 19 wniCh stJtO5 if C. 7437.csel 0-cos to last t h a r, 20 fuet ne GI system uhculd be 411gned 3ar c u l :: leg ectre.ulatic

t. s i n g ES-1.3.

(1.00) f r 1 I (4**** END OF CATEGORY 07 eeest) t

p.~ _ _ _ _' 0 M _:

__ _ _ _S _T _W._T _: v_ E _ r P C_ _C E_ D_ U_ R E S_ _ 1_C_'.c.C_1_'_! CN_S_,_ _a N_ _D _ L_ _I M _I ' A T _I O_ _N S_ PAGE 71 e _.,a;_. 4 u,, ') t -. "N9

s. ant

.5 CDerating at T. Dawor and tn2 13tCGt l el> ' J t e 0 3 t.3 'i h C W G : '!.: GPM - Car-erted 3 7. E 'eakage r at e .. "a OPM Leavage.nt: the cr o s cur t : e.- Relief 'ank 1.2 GPM - Leakage into the Primary Drains Transfer Tank C.4 0M - Leakage through 31-C', RCS LOCp 1A. cold leg isolation (Fr evi ou s leakage rate.9 a s 1.6 GPM) 0.8 GPM - Total primary to secondary leakage 4.2 GPM - Leakage past RCP seals What RCS leakage limits, if any, have been exceeded? Pofer to attached Te;nnical Specifications. C h c.v ALL werk and STATE any a s surnp t i en, e t (***** CATEGCRY 08 CONTINUED CN NEXT PAGE

- - 44)

2 3.. '..t..;141 L".J .L :... i; p. d. r- -.:: 1.: d.!:. ,.,r . c.,, n 7. q. enn. ,. q. v a-1...t h '. i? 1. 0 2_D h 10 2..' f'. 2: mAgg

- - eN-F i'*?

a$'

m 22

,L...m, c,. a- .- a ). s... ] I '. P 3 CM 1/ 2. 40. 0 d i c;;u a ws THREE (0) types et status b oar rM / p r i n t s ratnrainec in the control com. l 3T tne types at ;;ntrol room Statut, t: a a r d G / pi i n t s. (0.73) 3R!EFLY discut,s the FRIMARY E'URPOSE of each. (1.50) LIST the pc-rson( s) e r. s p or: s t b l e for updating tratntaining) each conte al ecom status ocar c /pr Int. (0.75) I i 1 9 1 1 I l l l (***** CATEGORY 00 CONTINUED ON NEXT PAGE * *eso) i 1 1 4 4 s

9,. ACM NISTGA' VE PcOCECURES

.---- L.CONO!' CNS--------- L-AND L*MI.~ATIONS PAGE 33 Uning the EPr-/ Implementing p ececurec provicea, classt fy the 'cilowing evcott.

Con s t i:er eatn separately. For eacn event STATE: 1. ne classtitcation 2. The J uu t i f i c a t i c.n for the classtiitation 3. The Tab No. of the Implementatten cr ocedure a. During a ecutino curveillance of the hc. 1 Erner genc y Diesel Generator an your anift, an electrical tault caused a fire in the output breaker. The breaker cannot be repaired ice at least 24 hourn. (1.00) 6. Chemistry has just repceteo tne s ollowing Steam Generator (1.00) j in t c r ec ur i e / g r am Dose Equivalent I-131 activity levels lA. 0.13 mi cr utur i es, gr am

3 0.09 x.t cr c: u l eu/gr am 10, 0.10 microcuries/ gram.

I l 1 i 1 I t I t***** CATEGORY 08 CCNTINUED ON NEXT PAGE

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1

a.a..it - - JL.- 1'a 'L= q aT' c' - 9 Crc N==~L==J'"t'.': w'J'c:L : d .'N D '=:*v ?**TT'b u"l ~;AG"L '1 ~$ 1L-L

==1-- l J tL=..a4 .a. u w .--.r.. s., -n es! VOu see tne Cn-cuty Nuc. ; o,t r ihttt 3 acevincr. The GC3 is at r er ma l T a v et a;th .4 Reactor Startt c a r c t. : to t omerent e nnon the i1aintenance 4areman vde ng ers Rcscactner

a i l q$ :1

.t, 51r (6) 1*i?"*5 yCL th3t the 16* C ': n t.3 ;. m : n t 'e c ", t : urwe'1;ance test. '* 4 estimateE that he may ::: 0 ablo tc r e;; a : P the 1 4.71 t :n 10 hours. He also c'cted t *1 a t th9 16 RecOrb;ner pasbod ita wr.ut"!ance nitn ro craclan. WHAT mpact, af any. ,wi l l this Mrvu cn the ,21 a 0 0 start-up and why. P l f l I i I i l l i i (****e CATEGORY CB CONTINUED CN NEXT PAGE

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J l i - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -1

l 1 1 '2. ADM!NIE ;ATI'.<E TRCCEDU9EE. CONCITICNS, _- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - _ A N D. L _I M_ I T A ' ! O_ N S P AC.E 35 J r L E ;,., ..s. e; . -.sc; Anouer the tcl;outng q u e s t t o r. c concerntng "Ocerating Shift Co.mo l stren t und Funtticns' as discassed tn DVPS OM CHAPTER 48, Procedur e Ef. 2. rme alant i s oper,a t i r.g at 20CP acwor, you.ee the on-antft shtit gupervisor. Ycur NCO has tecomo sertcusiy 111 .-a n d you have sen* him to the hooptta;. Can the clant centinuo to operato?

( so, for how l erig and.a d e r

.s h a t conctttant/gutcelines. (l.CD) t;. Who has the authority to restric t access to the contrcl room 7 (0.50) c. L;ut four (4) of the seven (7) people that shall be granted access to the control rcem regardless 04 the 51tuation. (1.00) 1 J P 1 l i i 1 l a i 1 1 1 1 .I d (***** CATEGCRY 08 CCNTINUED ON NEXT PAGE

- - - - )

5,1_ _ _._; 3 v ;

j ; 3_ _7 p A_ _T _; i,. [ Sqgggg(

___jpg[, _ _ _ 3 *. _7 _* C_ N_ S_ _,i N_ O _ t_ _I M_ _I _T A_ _T _! C_ N_ G_ MGE 16 [gq_ , i, _; _:.... v c.64

m. 9us Anuwer the following c;u es t t en o c c n c rir n i n g Control Of Operating Procucures" a+

d:scussed in BVFS CM 1,'C.4G.C L. a. ..;r : e r what c on c i t i c,r can 4 0~ Thr' Spot Ca or a t i n.) '*'a n u a l ".hange Notice CMCN) te made to an eon anc 'WO makes that c ec t ?,i c n. (0.80) d. ?o must approve a prop: sed CMCN that affo;ts a procedure used on both ur.its? (0.80) c. k*;w long dces CSC and the Plant Manager have to review und approve on the spot nhanges made to operating proceduresS (0.40) long c:32 a O*CN r e r.a t n i., oftect after appreval av the n; ant _m 'anager7 (C.40) 1 l I l I 1 l 1 t (**e** CATEGORY 08 CONTINUED ON NEXT PAGE

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=

C _,

Wd _ ___ _ _.... _ _I N _I C T 7 A_ ' _t V_ C_ _ P_ A_ O_ C C_ O U_ R E_ S_ A _ C C_ N_ D_ _' T _I O N_ S_ z _ _S N D _ L_ _l '_d ! ? A T_ _I C_ P_ G_ DAGE 07 ~ OLE 3T:CN 3.C7 (C.'-) scco, dance with CLC UAP Chaptor 'D (provided) determine for each of the 4citaning events: co _i o c +, L i t t a t i o n (1 'v., hr., atc.). ! ', J a v. c u a. runpOnsible +cr making the I n t 't t a l notification. 7,pu af report required and time frame teg. 30 day spec i al repor t ). Tle r adcon 4 cr ernan hac.nformed you that through a valving error the u. low level waste drain tank contents, which were supposed to be pumped to the high level natte drain tank, has been dischargea directly to the saoling tower Olowdown via the effluent f i l t er'5. He also states that althoujh the level of actsvity did not exceed two times the 10 CFR 20 limit he had informed the state department of environmental resources. (1.00) i c. "au are the NGS and,4ve just ceen infccmed that a c_onttracticn group acrking just off site has damaged the ENS Onone line. Repates are 1."cocted to take eight (S) hours. You test the ENS line and it does ,ot wor s'. (0.75) c. 3afety Injection Tank 51-TK-1 A has develooed significant backleakage from the RCS. As the NSS you have decided to close its discharge valve and declare SI-TK-1A inoperable. (1.00) l I i l (e**** CATEGCRY 08 CONTINUED ON NEXT PAGE .****) .m

l I

~.

.s '.;'d : N I ~ n A * : '. E CAC ---- - - - - - - - - - - - - - - - - - - - - - -.C. E D U P E..G COND!'IONE. Y4 D '_ : t' I ' A T --- . - - - - - - - - - - - - - - - - - - - - - - - _I O N S PAGE 28 I esTa

- - p, 7. e dp (m. am) 1 i

4 -w- .w., -u r

t

.~a7 d i s:cvor od today, Aaguct ;'. that a D10u01 Gener a t er "0NTmLv .. a r m t l '. a n c e ' hat was due co Thur scay, August 4, was actually per4cerod on

r. Jay,

' u t; u s t Thi-1erW: 1;anca car the last thece mentet nac meen c per urmec en July 3, June 5, and Ma< 4, 1789. It t"i s Di esel Generator ::nandere: operaelo' E4 plain your arswo-and the api:!: cable criteria u s. e d to cetermine operability. 1 f -f 9 f 'I 1 t t h I. 1 1 I i I (s**** CATEGORY 08 CONTINUED ON NEXT PAGE

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l

'O.. AC"!NISTRAT:VE PRCC200RE2 CONDITIONS. AND L:MITATIONS PAGE 39 QUCE':DN 9.C' (2.'C) Answer the follCWing questi ons cncerning Conduct of Caerations as da2:uwsec in DVPS CM 1/2.48.;. 'Operaticos Ghift Rules of Practice", a. < hat :nt ti al cporator actions should be taken if an instrument er c on tr ol appears to to operating improperly. (0.90) O. "CW can the Op0ratcr cne:L Cper.lotlity/incporability of the instrument I or :cntrol' (0,30; i c. If operability cannot be vertiled, the operator is authorize to take certain action to gruvent/ protect the station. What action to authert*c) and WHAT three (3) items, specifically are, to be provented/ ,; r c t o c t o c. (1.50) 1 l 1 t I l 1 1 i 1 l l t i i i l i ?, I l (***** CATEGORY CO CCNTINUED CN NEXT PAGE

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I

"i _ _ 22 CI U I 3123_~ 125 L' 3 E E E E 22 E 5 : _12 *_; 91_'1999 : _ O $ _ ; i MI I6112 e 5 AGE 40 ..e-.,J A,' s v. e e tne f ol l :rs t n ; c:ncerning Caiety Limttu und 'imiting safety cystem 3etcaints (L3ES) a. @4 A T 3re t*e TWO (2) 5.i f e t y a i t t 'i and WHAT par a neter t rust ce renitorea to <s t e.n a : e.i a safety Limtt h a t. t; e en e.ceeden. (1.25) O. mat to *he BASES +or ne LCSG reuctor tria setpoint values spacteied .n 7 a b l 61 2.2-1 af the Techntcal Spec i, t at 1 onS ' (0,00) ~ What notifications must ce made ai a Safety Limit in exceeded. Identify t h a t, e .m a t t i t c a t i c n s, that are recurred to be Tade within one hour or less. (1.00) i r I I J i v l l l a J (***** END CF CATEGORY 09 esess) (esas**sete*** END CF EXAMINATION s6zessettaessee)

.. _ = - Thormodynamics Formulce, Conversions, and Ccnsecnts k l 1ft = 7 48 gal. air L gal. = 3.78 liters R,g, = 53.3 ft - lbf/lba 'R 'R o = 0.172

10 STU/hr - ft 3 lbm.

= 454 grams 23 1W = 738 ft - lbf/see mole = 6.023

10 particles t

= 32.2 mm - f tM(1bf - sM) 1W = 3413 BTU /hr s e l 1 HP = $50 ft - lbf/sec 1} { ~ # ) 1"I'2 1 HP = 2545 BTU /hr r, = (r2 1 AT, = (aT, - 4T )/in(AT, / AT ) l 1 BTU = 778 ft - lbf b b i 1 1 1 ata = 14.7 psia g ~ U* 14.7 psia = 29.92" of Hg (1 + h. + 1 ) h k h 1 2 29.92" of Hg = 760 mm of Hg 1 $ = ;YA = ek U" l l# 1 h *#1 k * 'm h j, TDH=fg/g

c(z)
dz t

2 h = AP/ = aPv 2 2 f t p ] NPSH = (P,, - P,,g)

v m = (h * $)/BMP = a?
D/ BHP 3. p /p j

p p (k - 1) CPR = P = (2/(k + 1)) t 2 e in + 2 ~"1"'*

V Q

(h - h )

1002/h,

. h =u g g D*2*g *# **2 e l I "cycle " "net 9 source I 0 = Me *(AT/at) A.E. = q -T AS .P source sink source l 0= Meat p l 0 = $dh I ) k*U^AT C =C + R/778 m P V t j 0 = hAaT py. RT. I k, p,y ) 4=:rAeT yy .2 4 4 11 0 = OA(T -T2 )F

F i

not 1 a e ) T (k - 1)/k v (k - 1) f = (F ) =( ) ] at Q= L L, L 1 1 2 1 n . k ^*2. ' " k,Am k An au = c 4T j 1 g 2 n y ah = c aT l y ] ut + P vi t + v,/2s, + s s/s, + 912 " "2 + # "2 +,/2g, + 2 s/s, + w;1 g i 2 2 2 4 l i 1 1' n

EQUATION SHEET f = ma y a s/t Cycle efficiency =N6t Work ( oin t ) Energy (in) a o = ag s - v,t + 1/2at a E aC a = (v, - v,)/t -== a KE = 1/2av y, v, + at A = AN A,e*** = PE a agh w = 9/t A = In 2/t,, = 0.693/t,g g g U = v&P 4R = 9314a IIt/t)(tg) tt/sI'ffI " ~~~~~~~~~~~ Q = aC,4T Q = a Ah (t + t,) t/s I = 1,e*8' h=UAAT h=UA(T,,, - T,,, ) I = I,e,,, i P'E "We" I = I*10../,,,, F = P 10 '" 8 TVL = 1.3/s e = r,.,,, MVL = 0.693/u SUR = 26.06/T sCR = s/(1 - K,,,) 7,g,gg S/(1 - K,,,,) CR, = A e SUR = 26 eff CR (1 - K,,,)g CR (1-K,,,), = g a 8-p M = 1/(1 - K.,,) = CR /CR, g T=(t */s) + (() - p)/A,,p] M = ( 1 - K,,, ), /( 1 - K,,, ) g T= t*/ (e - h) SDM = (1 - K,,,)/K,,, = (K,,,-1)/K,,, AK,,,/K,,, s' 1 x 10 seconds p = = e=(t /TK,,,) + [h/(1 + A,,,T)) A,,, 0.1 seconds ** = P= I4V/(3 x 10*') I d, I d, j = g n I = No I da - I d's g g 3 AT AT g LMTD = --- ----- In AT /AT a t WATER PARAMETERS R/hr = (0.5 Cp)/da(aeters) I gal. 8.345 lba R/hr = 6 CE/d (feet) = 1 }.-3.78 liters MISCELLANEOUS CONV M SIONS 1 - 7.48 al. I curie = 3.7 x lodps 3 D;nsity = 62. Iby/ft 1 kg = 2.21 lba D0nsit = 1 ga/cm I hp = 2.54 x 10 aTU/hr 3 Esot o vaporisation = 970 stu/lba 1 Mw = 3.41 x 10 stu/hr tient of fusion - 144 stu/lba 1 stu = 778 ft-lbf 1 Ato = 14.7 psi - 2$.9 ip. Hg 1 inch = 2.34 cm 1 ft. 5 0 = 0.4335 lbf/in 'r = (9/5'C) + J2 3 'C = 5/9 ('r - 32 )

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o OJ 14 ES OA 1.0 12 FR ACTION OF RATED THERMAL POWER FIGURE 2.1 1 REACTOR CORE SAFETY 1.lMIT THREE LOOPS IN OPERATION BEAVER val. LEY - UNIT 1 2-2 Q a. l

CC'.Y '.D C C..' ' ' ' L ~ FACTOR CCOLA!C SYSTEM ~~ OPERAff0NAL LEAXAG2 LIMITING CCN0!TICN FOR OPERATICH 3.4.6.2 R6 actor Coolant System leakage shall be limited to: a. No PRESSURE SOUNDARY LEAXAGE, b. 1 UM UNIDENTIFIG LIAXAGE, 1 GPM total primary-to-secondary leakage through all steam c. generatorti not isolated frem the Raac. tor Coolant System and 500 gallons per day thrcugh any one steam generator not isolated from the Reactor Coolant System, d. 10 UM IDENTIFIED LEAXAGE frca the Reactor Coolant' Systam', and 1 28 GFM CONTROLLED LEAXAGE at a Reactor Coolant System e. pressurt of 2230 120 psig. APPLICABILITY _: M00E51, 2, 3 and 4 ACTION: With any PRESSURE BOUNDARY LEAXAGE, be in at least ACT STAND 8Y a. within 6 hours and in COLD SHdTDOWN within the next 30 hours, b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE SOUND 8.AY LEAXAGE, rsduce the leakage rate to within limits within 4 hours er he in at least HOT STANDBY within the next 6 hours and in COLD SHIJTDOWN within the fo11cwing 30 hours. SURVEILLANCE RECUIREMENTS-4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of th.e above limits by: l i a. Monitoring the centainment atmosphere particulate and gasacus radioactivity monitor at least once per 12 hcurs. l .uf a BEAVER YALLEY - UNIT 1 3/4 4-13

OGNTr '.3D ' W Y..',:_ > REACTOR CCOLANT SYSTEM .j SURVEILUNCE RECUIREFENTS (Centinued) Monitoring the containment sump discharge at least once per 12 b. hours. Measurement of the CONTROLLED LEAXAGE to the Mactor coolant c. pimp seals when the Reactor Coolant System pressure is 2230 + 20 psig at least once per 31 days with the modulating valve ~ full open, Performance of a Reactor Ccolant System water inventory balance d. at least once per 72 he'trs during steady stata operatien, and 4 Monitoring the reactor head flange leakoff tamperature at least i e. once per 24 hours. l .l l \\ l 09 BEAVER VALLEY - UNIT 1 3/4 4-14

e REACTOR COOLANT SYSTtH l' PRES $URE 150LAft0N VALVtf - ~ t.l.M! TING CON 0! TION FOR OPERATION 3.4.6.3 Reactor coolant system pressure isolation valves sna11 te coerational. APPt.ICA9 f t.!Tf Modes 1,2, 3 and 4 Action: 1. All pressure isolation valves listed in Table 4.4-3 shall be functional as a pressure isolation device, except as specified in 2. Valve leakaoe shall not exceed the amounts indicated. l 2. In the event that intecrity of any pressure isnlation valvc l specified in Table 4.4-3 cant.ot be demonstrated, reactor operation may continue, provided that at least tyro I l va'ves in each high pressure line having a non-funttional 4 valve are in, sad resafn in, the mode corresponding to the l isolated condition.tav

3. 'If Specification 1 and 2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold i

shutdown condition within 24 hours, i 4 The provision of specification 4.0.4 is not acclicable for entry into Mode 3 or 4 ) I l i l l 5"IMotor operated valves shall ne placed in tne closec Ntiunn Mc scict supplies deenergized. l t I I 'itAVER VALLEY - UNIT 1 3/4 4-14a Order dated April 20,1981 l t i

t REACTOR COOLANT $YSTEMS ~~ ~~ SURVE!LLANCE REQUIREMENT (8) on each valve listed in Table 4.4.6.3.1 4.kidie3 sha $ak$$eaccomplS!hedpriortoenteringNode1afterevery l De test time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in a cold shutdown condition for 72 hours if testing has not been accorplished in the preceading 9 months and prior.to returning the valve to service after maintenanca, repair or re s,lacement work is performed. 4.4.6.3.2 Whenever integrity of a pressure isolation valve listed in Table 4.4-3 cannot be demonstrated the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall te recorded daily, i I (a) To satisfy ALARA requirements, leakage may be meacured indirectly (as from the performance of pressure indicators) if accomplishec in accordanca with approved procedures and supported by computations showing that the method is capable of demonstrating valve ccmpliance with the leakage criteria. RAVER VALLEY - UNIT 1 ,3/4 4-14b 9/Mf/d32fd/.Afff?/lil/JH1 ANENOMENT NO. 101

t Tall.[4.4-{ l REACTOR C00LWT na.c, rRES$URE !$N.ATION VALVES ..u g (a)(b) System Valyc No. Allowable t.eaksee Loop 1, cold leg SI-23 < 5.0 G/M 31-12 { 5.0 GPM

l. cop 2, cold leg

$!-24 < 5.0 GPM 31-11 I50GPM Loop 3, cold leg $!-25 7 5.0 GPM S t-10 E 5.0 GPM l l I I l I l ("I 1. Leakage rates lets than or equal to 1.0 gpa are considered actestable. 2. Leakage rates greater than 1.0 gpre but less than or equal to 5.0 gem i are considered acceptable if the latest measured rate has not exceeded i the rate determined by the previous test by an amount that reduces l the margin between measured leakage rate and the maximum permissible rate of 5.0 gym by 50% or greater. 3. Leakage rates greater than 1.0 gpn but less than or equal to 5.0 g;m are considered unacceptable if the latest maatured rate exceeded the rate detersined by the previous test by an amount that reduces the margin between measured leakage este and the maximum permissible rate of 5.0 gpm by 50% or greater. 4 Leakage rates greater than 5'.0 gpn are considered unacceptable. (b) Minimum test dif ferential pressure sFall not be less that 150 psid. 3/4 4 14e Order dated April 20,1981

S __IUE98Y_9E_Nyg6[@@,ggWgE 86ANI,98[$$IlgN,[(ylgS,@NQ PAGE 41 z

g g ISE6DQQyt!@digjj e ANSWERS -- EEAVER VALLEY 1&2 -88/08/17-BRIGGS, L. i ANSWER 5.01 (1.50) i c. 4000 gprii x 60 min /hr x 1 cu. ft/7.48 gal x 1 16./.0166 cu.ft 1930000 lbs/hr CE.33 = Q = mc (del ta-T) 1930000 lbs/hr x 1 BTU /lb-F x 8F= 15440000 BTU /h- = [0.33 4.52 MW t0.33 l 0/(3413088. BTU /hr/MW) = 4.52 MW/2652 MW = 0.17'/. powerte.33 No, it is not removing all decay heat CO.33 REFERENCE BVPS Thermodynamics Manual Chapter 3 BVPS LP-TMO-3 EO No.7 4-DVPS System Description Chapter 10 KA 191086 K1.83 2.3 193007 K1.08,3.4 e-IP a 7', ~ n 191006K183 .193807K198 ,... (KA' Si : ~ ~

e

,m3: 1 3 l .k 'E.. ; % : ? tr.f n'ai, Mb;/,. 2 1.- s NA ANSWER - 5. 52 ' ' ' ' ' ( 3. 99 ).. :. ' < 4 3 1 l'. + Keffi = 1/(1 4 rholi ~ > Koff1 = 1/(1 - (-0.04)) = 0.9615 .C 8. 5 3 - ~c CR1 (1 - Keff1) CR2 (1 - Koff2) = 100 (1 - 0.9615) 132 -(1 - Kef f 2) Reff2 = 0.9709 (8.53 = 4 rhol = (0.9709 - 1)/0.9709 = -0.03 E8.53 delta rho a rho 2 - rho! = -0.03 - (-0.04) 0.01 1000 pcm (0.53 = = +,3 . :y. 5 L :,' Doron~ delta rho.= -150 ppm x -10 pcm/ ppm = 1500 pcm ,CS.53.:,,. l Xenon delta. rho = 1000 pcm - 1500 pcm = -500 pcm , C S. 51 s .r. y,_ 3- \\ ~ ' h..N . + d REFERENCE s I 'l ai ~ y BVPS Reactor-TheorycLP,E;0 4.1 and 5.1 a l SVPS Rx THEORY 4TEliT.Pgs 43=thru 45 Ch. 5 .iJ. r i + KA 001000 K5.29'3 9 a '192883-K1.82 2.3 0, eM&. L 001000K520 '192003K102 ...(KA'S) .i e -L{, ., + [' ... [ '.dy + i- + s p 7 , m.,- m. y,- - i f 5 i ' ((

'I

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y w u-.- ~

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Ut__IUEQBY_QE_UUGLE0B_EQWES_EL60I_QEESGI190t_ELVIDSt_QUQ PAGE 42 IUE60QQXU$d[GQ ANSWERG -- DEAVER VALLEY 162 -08/08/17-DRIGGS, L. 1 ANSWER 5.03 (3.50) O'

c. ? ? l1M v a.

1. Delta boren worth becomes loss negative (0.25) due to increase C l.; i competition for neuwons by more boron atoms (0.5). de,% 2. Delta boron worth becomes mor e negative (0.25) becausamorh' neutrons.are thermalized due to densergmoderator.ar'd si.ncey ,,s a 1/v absorber, the probability of absorption increases'(S. 1.x p ; 5. e 3. Delta baron worth becomes less negative (0.25) due to inte competition for neutrons by the poison atoms (0.5). 4. . Delta boron, worth becomes.more negative.(0.25) due,to;r boron soncentration f rom NOL. to Ect. ( #6 5). < : +. w-0; sn ' owy y,. e s Nedat[ve (react,ivitf(ciaused! bh 'the[.tpuik %.m, d Roland [ M [n] f$ b. d. REFERENCE BVPS ReactacuTheory.MenuallChapter Ob y.734,s s 3h. ? w Ni a3S?3.'1?>.192, . KA 901890fKd;28;3.2i 301003.K5.28 3.8( Set' i BVP9 Rx THEORY'LP EO Para.=8.1 C01000K528 881000K528 001000K530 192807K194, _ . A uf,p e =-,, v, d s /- r 'g ,y I ANSW2R 5.04 (0.00) e p., ; n gi, ,n The stuck; rod w uld be worth more (0.5).

8easthvity worth is -

,sreportional.to'2he relative flux squared (0.S).. For a dropped. ' the flux " le depresseds adjacent to it :(0.'5)" wheroes/if.the: same. .%'; 3 rod was stuck out, while the others were inserted, it would be. to a much higher.. flux than ths:fluxsin the rest;of the core ~ (S. . h 'y ~ ' ;' P; x<

p' b e

REFERENCE DVPS Rx Theory. Manual chapter.O pgs. 14, .,... i j, , qi = MA 000093 EK1.83 3.'8 '999995 EK1.05 4.1 192995 K1.25 3.1 'c C00003K193.,L g eS p 5K 'Q,,192SO5K195.,.jy (KA?S) y j :< - a; i ,w t'- 1 (1,r ? e ., ya '+ f/ "? I% V',.l'( 9, t p s ^ t ysyrgp 6 e l* v:s3 p g :pypa q* ' y t".h y ,, j Q - n pg 1. ,g*[ 4 I j*,4 ,pg;, A* s A , p'y,; J g k 4 ey >,* 5, ,,,,y e es. -}4 4.. 49 ~ <>

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d-'

*4'f 'V 4 .g ., p,, 4 e1 1m w

Di_ IEE96Y_9E_U9GLE08 EQWEB_E60NI_9EEEGIIQui_EL91 psi _0Np PAGE 43 IDEE 00D100r1GD HNSWERS - DEAVER VALLEY IN -88/00/17-DRIGGS. L. ANSWER 5.05 (2.00) s a. P:: r. fluid temp. in much lower in cold G/D which incroauen the density, of the liquid CO.53. Lovel is deturmined by a comparison of height timon weight (dansity) of the prousurizer fluid to that of the E ge. - reference leg CO.53 (which basically remains constant). Since the cold; water in more denso the indicated level hill bo higher than actual < ). level CO.53. l }. [, b. The utnam bubblo expands which causes the press, and temp. of the. steam' spacu '.c start to drop CO.53. When this happens the fluid at the-liquid steam interface is at a temperature above Tsat for the'new-S',' pressure and it.will flash to steam CO.53. This tends to hold pressg eg up CO.33 ,.d 'y X REFERENCE ^ ' ' s E.', 4' " ' ' ~s m DVFS THERMO TEXT Pos.5,0 & 9 BVPS LP-TMO-7 No. 5&3 KA 011 000 K4.07 3.2 010 000 K5.01 4.0 193 001 K1.03 2.6 - ; ?[ y. q 010000K501 011000K407 193001K103 ...(KA'S)' .3 A 2.y D .>* j 9 ", ANSWER 5.06 (2.00) , u kk l C '. a. C = v3/30 v= C34 x 2.33.,3 a 4.1% of full flow.

h ' %,

1 .-,f i <. ;3 b.

1. Mairtain heat sknk CO.253.

To me.intain thormal driving head C 8.' 25 3. ' '

2. Maintain' coolant inventciry (pressur t z er level) CO.253.

Halps ~; *. W * ' prove.nt fo mation of vapor pockets in the system (0.253.. _ ..,4 3. Maintain subcooling (50F if possible) CO.253. Prevei.ts steam /'O iddh, binding of> coolant icops CO.253. i.. REFERENCE a- ..l g f" M. c p'.s e KA 193 000 K1.23 4.1 _ 000 015 EK1.01 4.6 000 055 EA2.02 4.6 DVPS THERMO TEXT,Pgs 23 thru 25 (g[' l' g DVPS LP-TMO-7 (Jo. ^16 7 000015K101-IMh0055AR02 19300GK123 ...(KA'G). ,Q r, y, a g, r , 9 ;1, hg g y..s.. g 4 + A

c d6.t

'Ag* 1 i i S ,I g4 I 9 j..l... b u.WgQ ~ e .....*tr* 4 m';. 3* 4 t e,'y L.. -3 e't) '.g -y},,. t, g < 1 j.v

f.

j t. F '[ d ~ A yr.

mN. e + .4 .e .g 44 ) j r.t ,, ', 4 : h, '. y '/,4 q - ( t q ) ')* W. i_ 1 -..W p.. r .v. ry ,4i A.,\\_ 2.1.11 ~_A i m 2* b~^^^' ~ ^ ' .t s = t -1'

l L __IUE96Y_GE_SYGLEGE_E9 WEE _ELGUI 9EEEBIIOL _ELY19h QND PAGE 44 IL:EED991 nod 192 AN5NERS --- DEAVER VALLEY l t.2 -G O / G'8 /17-DR I E GS, L. 4 th ANSWER 5.07 (3.20) .. t O

j.p'(

i. a.

1. Decreano CO.2], would increase Tave which reduces the subcoolingi margin CO.23.

J' 2. Increano CO.23, would increase RCS press and increase subcoa margin CO.23. OAs, No C.4NGE o f SPfet t o 6AL ANCIMCs HEATAP.5 Q.s

3. Decrease CO.23, would increase heat flux.and ruduce subcoolk 4

margin CO.23. ? . t. - .. -9 b. Section A. Limits ave. coolant temp. (Enthalpy) at core exit to than saturation CO.43. 7 5 : Section D. Limits hot channel core exit quality to 15% or leen; s s. c.. Section C. Limits DNDR to 1.3 or greater (f o ' normal opa and ? freq. incidents) CO.43 E' c. All trips that rely on Delta Tempuraturn CO.43. Because if Th. saturated there will.be no change in hot leg temperature and :stn lf no longer be an indication of power CO.43. ,y REFERENCE VA 00!:'O V5.01 3.9 002t100 K5.09 4.2 002000 GO.05 4.1 193000 M1 DVPS THERMO TEXT Pgs. 17 thru 20 DVPS LP-TMO-7 E0 12 and 14 0020000005 002000K509 002000K501 193008K105 ... ( KA ',S ) .c y .3 's t ,. A ANSWER 5.00 (2.03) ') L.A s J. :, c. Increase (0.50 pointu each) \\ M b. Increase + c. No change Y $I* ~ d. No chango ne

(-

REFERENCE DVPS Rx THEORY LP REAC{IVITY BALANCES Para. 9.1

.i.

':4 BVPS Rx THEORY TEXT Pgg,10 thru 27 ~ KA 192 002 K1.14 3.9 o; ( 192002K114 ' ..(KA'S) c-p 4 T s ?'N,, v i't

y k

k .t- ,.. sm. 4 g,

7 f,,,

e h. 4

- 'g-

.L. ~4 %--a* ,et 3 yg .) - M[.,,, _. ' y- ~ i 's .,i,, c..,.s. ~ --.., i f.; s. s. + - . i, '3 .s s w.- 4,

v 4

". i[

i OR

',./ ' i Ik ~ e -( 7 \\ +

h IU5GEX_0E U6C6s06_EGWGE_E.60NI_GC5.60Il002._E6W.Rh_0NQ PAGE 45 1Gi3GGZS6bJ1Gi R T. SERE - EEAVER VALLEY 152 -- G S / 0 9 / 17-- E R I G G S, L.

2. iO ANSLEP S.09

'N o 1. Non-conservative [0.53 A.5 the core is loadeJ toward the detector the detector becomes oo.nt nated by core flux [0.52 and does not see changou due to cubtritical multipliccation until it overcou,ou the occi gr ound core flux [0.53. E;tr i y v a u r o p u i,.u. t o o at uno a<ii givi .- s a l i s ir _ ' m i. u 6 1 i. c t i c o, a'

- i t i m sli_y

D.w a. A S.

The faster the reactivity tnnection rate the lower the count ra*:0 at arttical1ty LO.53 due to the reduccJ time for cuberitacal multip1tcation [0.53. REFERENCE DVPS Rx THEORY LP PARA. 5.1 AND PG.15 LVPG Rx THEORY TEXT PG 47 and 40 UA 192 000 K1.04 3.0 015 000 K5.06 3.7 01500;'KCC6 19:008K104 ... W.A'S) t 1 ANSWER 5.10 (2.00) a. False b. T r.t e c. F a l t.e d. True REFERENCE DVPS Rx THEORY LP PARA. 5.1 j BVPS Rx THEORY TEXT Pgu. 11,11 S 17 LA 192 003 K1.07 3.0 19200?M107 ...(KA'S) 9 , t 4 [ s . + - a 4,. y*59.'- . $cg V.N g'- a A..'c. h..,.__, . i.m:. m hi

s at _Lt0GI_23IDJ52519Ui_G90IBG61. 0HD_iULIEWSUIO.E100 PAGE 46 ANSWERS - DEAVER VALLEY ILO -80/09/17-ERIGG3, L. ANSWER 6.01 (1.75) -:v :, 34 .c a. Adjusting RHR cooler flow rate valve (MOV-1RH-750) CO.503 .l 'a. e b. RHR bypaus valvo ( MOV-1 RH-60'3 ) will open or close to maintain'f en adjusting RHR flow control valve (1RH-759) (i f in automatic)...C x h I c. RCS prennure < 430 psig CO.253 d I' Pzr vapor space temp ( 475r CO.253 ,,,g. .\\ y, !5 i d. RCS proosure > 600 pulg CO.253 .....,q' c '.V F.4h REFERCNCE .,4 DV-1, Chpt 10, Sec 1, p0 2 & Sec 2, pg 6 *l+' c ^ KA 005000 K4.07 3.5 005000 K4.03 3.2 'MI. E' DVPS LP-SOS-10.1 EC No.3 L 5 005000K403 005000K407 ...(KA'S) . hh

l'fl

.m 9-:2 'l l ANSWER 6.02 (2.50) Ns x a. Manual Lockout Switch CO.53 A- ~i b. A means to purgo air or Hydrogen manually from the generator CS, k % c. Fusible links in each sprinkler head will melt (above 165F)' cause sprinkler actuation. CO.53

lc; r.

d. A pressure switch will i nitiate an area "Fire" annunciator:16 gi control room CO.53 and a local water gong (born for PAB El ga 760) CO.53 e. REFCRENCE x .m n a KA 066000 K4.04 3.4 086000 A3.02 3.3 006000 A4.03 3.4 ,; g BVPS LP-S08-33.1 EO.No.3'

,;f2 DVPS OM 1.33.1 Pgs. 3 THRU 5 v'.h,

.c 006000A302 BB6000A403 OB6000K404 ..(KA'S) ,, _ c g., j. t ' s g., 9

4 i.

,. K'}; .A' .N, 'C saQ3 _.g ~ .....c. _, ~ .i t .a .s,, w .i**. Q,$I N ' i e.,.,, M e h, t4 '

A g M w Asd.,*.PYt" Q J.4,p Q, j e.,4, g

{. s ,, m. w. w e s ,..., ~, ~... i nej, ', t dij A

vy y

c' 4 me bu ^

N 6t_.E603I_ifSICdG_QEe199t_GGUIECL.m_000_10SIBtfEUIGIlQU PAGE 47 ' NGi,EFF -- SEAVER VALLEY J."e: -GC/00/17-DRICOS, :. A!' '2 W 2P o.00 (0.00)

s NON E S# V/)LVJ-(0 15 for position) a.

3 CID f. r b. S CIA g. S CIA (0.15 for signal) c. S CIA h. S SIS d 0 CID 1. S CIB c. G CIA j. O SIS FEFERENCE DV-1, ch. 47, Table 1 MA 103000 A3.01 4.2 DVf S LP-SOS-47. 2 EO No. 4 105000A301 ...(KA'S) 1 AN3tJER 6.04 (2.00) a. Carbon Monoxide to.5) y,,. b. Four (4) tanks CO.53 ", j f, 'r y To maintain a positive pressure in the control rcom CO.53 c. lei ver water cooling calls, 1VS-E-14A and 14D CO.52 REFERENCE tA 01:000 K1.13 3.1 DVPS OM 1.44A.1 Pgn. 10 thru 15 BVP3 LP-SOS-44A.1 EO No.1 &2 013000K113 ...(UA'S) i l >:.sw. . + l 8

+)

o ) jI,' 4 9 4 g', l f i\\ k9h A - .f, ) P h ' N l.' p-,,. >e, f, + - ' f s , g.h -5 i;T ,k. ~ . ',.,,{ [*d)

_

i h.. Et4UI_GISIGus_2Gi1002._G001E L _000_IUGI6YUGUIGIIGU PAGE 4G ANC WER'i - EEAVER VALLEY 3.2 -GC/03/17-BRIGGS. L. i 4 ANGWER 6.35 (2.60) t tany 4 at 0.4 each) i s.

uu press. Ru t r :. p I

High press. Ru trip Safety Injection actuation Accumulater Discharge Valve Dlock (2000 psig) FORY actuation bloch taelow actpoint (2000 poig) l .e Low prenu, alurm fpcepp y 0 7*a 7- /Wp P// 4 b. RC3 pronuuro CO.25] leuc than 2"O psig CO.253 AND cither keylock SWittih net to the automatic position 00.253 OR if either pressurizer relief a line t uolation val vo (MOV-1RC-535 or "s37) not fully open CO.253 60 REFERENCE I DVPS OM 1.6.1 Pg. 5? t< G4 DVPS LP-SQS-6.4 EO No.2 AND PG.1' I:A 010 000 K4.03 4.1 w10 000 GO.07 3.4 0100000007 010000K403 ... ( L. A ' S ) A E t ANSWER 6.0" (2.20) t )' [ ) k (F-utm) (del ta-P) m-utn u i

, 3...

1 1 q 3iace the cteam prouture component at.yu constant (i t should go down) whilo I the delta-P increases, indtcated steam flow will be higher than actual ] steam flow. (8.6) 5 The qumming network fnr flow will send a signal to the flow controller.to-i ) open the feed regulating valvo. (0.5) I i Aa level starts to incrcase, the level error will signal for the FRV to4A l clone

g,5) l i

i W%- i I Gventually. n .u l l _e cliwu wd .hu igvu. .-r, M d.' l w 27 ihe FRV will be positioned uuch that uteam generate-level will operates i ] N steady stato level,'!gm. :S w.., m _g (g y DOC,R e m M f D l a. REFERENCE e% l DV-1, Chpt 24, Sectica 1, pgu 17-20 l BVPS LP-SOS-24.1 EO No.6 j KA 059030 K1.04 3.4 059000 A3.02 3.1 a 039000A702 059000K104 ...(KA'S) ,'41 I, g 1 l w y T [' g*- 1 l t_________, .Q :4: y. na

l l \\

o. __ 3.: i _ l'CCE 2{5310ba.._Z DIE [ b _d.s2 1 3I6Wd[dIGIlGU PAGE 49 i

_ca.. t u . % : %a. L. -. - ~, 2,. s... .n v a a _a r i J l it; b a,27 C.40) 'o arevent.n<cucsive couldown of the reactor-coclant cyntem CO.253 and ela che consequenceu of s staam 11no break in containmann CO.253 2, Diccks the steam dumps (TCV 106 SERIES)and CO.253 Alicws manual bypan:5 of the uteam dump block to the thrco ecoldown valvon CO.253 1, Rod ujection accidunt af Icw worth rods fecm mid power CO.25) s, cannot be bypassed /blockt;d C (J. 25 ] 2, 3ackup to high prenuure trip CO.253 and to prevent dicchargo of water thr ough precaurister safoty val'.us CO.25] Tr ip can be blotted (auto T7) CO.25J 2. - r o t. o r. t from low prest,. Whi cn c.aul d lead to DNDR 1.0 CO.?.53 and L. ni t nececuary range of protection from OT delta T C3.253 Trip can be blocked (auto 'P7) CO.25] r,CFERENCE D 'v P ' ,M

1... i Pgu. 5 thru ?

DF C OM 1.21.1 Pg 9 DVPG TS CASES 3/4.3.1 and 2 T" 'P% 1.P-T S-1.1 En 1 and 2 L A.31 300 K4.02 4.3 012 000 K4.06 3.5 006 000 CO.06 4.04 00.iG00C206 012000K402 012000V406 ...(UA'S) A N Cl ?".R 6.08 (2.50) a. To 2nuurc adequate :ooling and lubiicaticn to the radial bearing CD.503 (4 at 0.25 each) . Ju, i neal lem of f ar RCP beering ecapuraturau a;)p r e ac h alarm limits RCS pressure lu '100 but.1000 psig No. 1 cual leakoff flow is leun than 1 gpm 9eal injection flow La between 6 and 13 gpm b. Centrollod l e a k ag t* film riding face seal CO.503 202 puid ts the minimum presuurc that can float the seal CO.253 and .enture enough flow to cool and lubricate the ueal CO.25] REFETENCE DVPS CM 1.c.4 Pg 7 EVr? EXnM DANV. No 6-12 avFC LP-SOS-6.3 Pga. $ thru G and EO 4 AND 5 VA 003 000 K6.00 3.1 003 000 A1.09 0.8 T 000A109 007000K602 ...(UA'G) 1

e 4.. T- - -.3..~. 6 M 9. - D E.".,.t.. 3.M. x C..C. N T P C. L1 J N 7. .[..N. S T. E U r ' E N.T. A. T : C N PAGE 50 "Y c ...,, h. s -s. t. i. f .. a. s,

7.,, 3.,

,.,,-r m.s.. l -11:\\. m ):

s.. t i.'

i...t,' 1,<- -e a.r. ... o p ....s..ee o a .nv e at 0.25 each) c;ntrol witen to start No of three SG lo-lo i r2 v o l ~. Doth main fred pumpn trippea B'R8WE,M AFW -i t a r t a l ' n a '. not 2 allowed t: y d L T:n wge preinure ^ Ort s /s *- %iety inj. algna i tr ain. 's icr TA and D v or TE. s. b. FhL-AMSAC t;My U .t 3.25 each) ? a. i.~.o n t r o l switch .n

t. u l l -- t o -l a c k o'

it o p

' u.i iJus of * 'al t a ge <lAE er 1DF) Cas:ael leading equence tact tlined to ctart you'

dater 210ctrical protectten ST FAKER RncKip 097 PreaFer clonuro of either MD AFW [0.253

' tam driver. AFW ' steam suoplf tria valvon (TV-MG-105A c-3) not !s _1 y - lost.D

C O. Z:!]

C 3 Fo"d i1ow iu manual 1y control 1ed at.he ieedwater bypanu control ant.21d CO.252 e.el inicr mati cn tu ir m Dw ccotr01 e atm er tha cati:up indicating manet CO.251 REF r,ENCE ~ .,., 1..s..., Fyu, ,. o

a.

W r ": LF-505-24.1 EO 7 iA 061 000 F4.02 4.2 061 000 G0.07 3.9 n, ,,, n ~t c a. u h o w 0 c, 0 61 C u,,.,

u. -..,s a.,

...sfti.-a) r w i 1 + s l a 4-m

a. .. r c.. e.

a, 3.

. =. s a u - J a,,e., _ e, a l b,,, y,,-... c y < ngg y u r u U 1.. w_ , _..,....1 . :1.u. = a. 3 o r.1 .o..,,, ~-

n.., u.,... < -

u n < ~, C e, !,, - t....,.-. c.:.. v_4 i n,.. F. ,..s - n sa a u_ ..n a i l r l Jn'O ZR c.1O s.:. IS) A. .. c,s power (C 5) i n t er l oc 6: p r o v en t.s auto ead .,o t i on .s h un impuluo power 'c 15 purcont cr le 52 CC.33 to preven *; unstable operation CO.33, Hign Lin t: O rad e.i t n d r a. n l 2tep (C-111 E0.23 to pro mnt.;cunter miaalignment i.0.33

- at 0.2.3 cach) 1.

Counoe gt.:c ; itit >; a i l a '. Energiron both s t a t i o n n r',' and novable gripper c ol.' s at a reduced voltage ~ ~. En u r g t.:.-: c red UAGENT F MLURE light ~n 'h-f r on t v.n el of :he power cabinet -1 Gtops al1 autcmatic rad mot son 5. Energtecs ROD CONTROL URCCNT FAILURE annunciator r.EF ERE NCE DVFG CM 1.1.1 Pga. 1G and 40 BVF9 CM 1.1.C Pg. E, r.> V r 5 LP-SC3 1.0 CO C 10 f (. C' 01 010 V4.10 3.4 001 250 A":.01 3.9 JJ '!O' 410 0 C 10500:: ~' 1 ...(tA'O) t t l l

I C rc.D'JREi; - nCtML W N O R M r. '. - - - - - r : 1 - : - )- - -- - -- - ;- -- 7, - - - - - - - t - O ? F R 'i r N C Y- - - - - - - ~ ~ - -aND PAGE 52 a.s _ 2 -a a _. u. .=.:.- : .., y ' \\ ., - -., ~ - - *. -e l. t w w -.-,,- J o .n. N.*

j _F

/,Oi '1.30-t - revent 0:castive inv.rit ry. a i;u ; 0. ~. 2 iireclude core uncover" from RCP'. trtpping an a 'ater time CO.53 ' :n t ai nmen t pr er. ;ur e C anig : 0. > 2 cr contc.inment radtation _000C0 R/hr (10EG) [0.332 or integrated containment radiatica 1000000 R (10E6) C0.33] h e%e containment value inccrporates additional instrument error s' t o ad vurne envi rcnmental factcr- [0.33 GE7ERENCE 3'.'F S E::ec Vol E-0 utop 21 pg. 02 BVPS EOP E-0 pg. 13 Gtep 21 EVFC EXEC VOL GEN. I'!FO. Fgu. 11 AND 12 A '.S0 C0? EL 3.2 4.T 000 01' a !.14

1. ;

3W9 LF-LRT-VII-61 EO Al and 65 Turin. Cbj. A.2 LVrt LP-LRT-VII-62 EQ A1 000.W 7 C 2 000011C14 ... O '. A ' : ) ANSW:P 7.0 t!.50) ANY a. Cicce main steam trip valvey (/ our r at 0.25 ptu anch) runnack the turbine

ce main utCam !Jyp 4 %. d l '. U L

.toue non-return valveu L. 0 c.M. m A Wr+ L Tref CF TVMS WL gyy b. (1) Preusurt or prencure 1G45 FGIG [three at 0.25 each) (2) Cantatnment prannure 1.5 FCIG.

)

teas.1ino Sresnurn 510 F910 m) a atch

s. < nyra w e m H t.j) sys yttitu t.4 vrt. < tr %

r. '. )

RCS nubcooling criterta met P0.252

C)

Fued fIow to intact SG's( !GC GP?1) [0.[5] or Narrow Range level in at l e a t. t anc totact SG CO.253 <!) RCS pressure (stable er i n c r e a t., t n g ) 0,253 (4) PZR level (.> 5 '/. ) [0.2CJ w Lar tr ip be val ar..cuut b.- m lace - '"4 REFERENCE "tr 1 CCr E-0 pgc. C, 16, 10 LA 000 007 EK 3.01 4.6 C00 038 EK3.09 4.5 0,Te LF-LRT-VII-61 CO Di LP-LRT-VII-62 EO A1 -..w

_ _ _ - n.. n. -.s ' '.r.. -- N QF.,.Mn L_.t rA C. MALT

!"ETC DJCY. ~, N D "nCE 5: q

?.

a t 4.d.:.. a . i. JL. 4.1v, L : \\ ..l!. ... c..wi s i ".c.. J.r? J. L. ' J /.s. R / 6 ?P 6 a 6 i 4NSwiA ~.02 (3.00)

u. - 6. or u d en o t e sequential a mp ar t anc e, ( bul l e:"3 do not)

CO.G3 N 'i r ::C t c J 2n E-0 EC.52 .t : n tronciorrang cut of E-0 CO.5] T h.: itop r an nucc1ated nota wt11 .sp1icitly state tha m qui r etnant. C O.,5] "a action ic required CC.5: Core Ccoling in a higher priority utatue cr e - W.an Heat Gink. CO.3) DEFERENCE CCP C;; ' 'a l Chap. 5?.B.2 pgn. O thru O ': A 000 007 GO.12 3. '? ' YF : ; ~ -LU W1I-61 TERf11NAL CEJECTIVE Ce C 307001': ...(KA'G) i ANWCP '. d 1 (2.00) l a. 5 7ar ty in pr'forred method of prennure contiol). Spray line . m.:r.1an4 2 r e p e r '.' Jud .r'

. n t '

t.a 'c-p. 'a.41, an C Ci' ihould be run

n one of those tWo loops C0.43.

J. .:r GC3 depr mer t. a t un u: tt :.u t a ACP.- anning <:aul d have formed a .. 2 :. m ut.t t l e in the N v e r. n e ' heed). Starting a RCP could causa a >~.J n oe:: aa t t on a4 t tu o.< e u l e L O..; 2 ana draw ileutc fram tha

r. r e n s u r t.: e r <nd reduco RC3 uubcco)ing CG.4].

T1 s0 1ccal flanhing coul d at: cur .f subcooling is not adequate CO.43. '; u. o ccnditions would requir'> GI re t ni ti at.i cr CO.43 :4n d increano .vatage toto the ruptured 3!.eam Guneratcr C0.43. r.trtspN;t OVf3 LP-IRT-VII 67 EO Nos. 3 AND 4 LA 000 030 EK3.06 4.5 .. ' r r ". "\\..- ' ' ' '. 1. '." D. 4 F. r r' ". ~ .o ~ p. .' ~~. - "r ~ ' 00003m 206 ... Wfn ' 3 )

o 7.r... - r.- _ _ c cA m_. t ,.:c. c.r. _.,v_.n t.., _ _7 t i r. y M..N C..Y .V. !. D. i AGE 54 .f' 7 . u G._ _.. = L. a .' t. i t # ;. a. K g,Gg ~ _ O /.,., J / -, .1 J 4 sC 2 [ <"...it-> -- J,i., 3% a .u,

. t o. o

-it 0.25 encni a. Iienctor trip and bypass breakeru andicate open t'eutran flux indicaten d ec r n a.i t n g ~oa bottcm l i g h t t-1;t 3P: W..:ero 5. "< :.v in t uncontrolled cooldown of RCC CO.53 c. Gintain 5 team Generator inventary CO.53

ter-c.T ar g A ng / HH51 pumps 2 0. '5 ]

Align car ati on patri s Open (MOV-CH-350), Emer. Boration valve (DB-A) C0.253 Start in-ser BAT oump in FAST upaed (BD-A) [0.251 411gn charging fIcW: Open (FCV-CH-122), charging flow control valve CD.253 or t f y letdown flow to E TiG .f VCT :ovel i ncreancu to dive, poin; LO.:D] >c ; g r e s c u r t.: et pr a.5%r e : u% than 2335 pntg CD.CS: . 3-7 = >, -: FA 000 029 GO.11 4.6 000 029 EF.3.36 4.3 000 029 EU'.12 4.7 EVFS ECP FR-S1 Pg.4 EVT C CCP E<EC. VOL.

1. C'*

4 rg.o4 fVPS Lt-LRT-VII-61 EC B1 ?- 34 200% 'GI'1 000029 TD6 u00.)29 ~12 ..(CA'G) i NhsR .Db 1:.00) i f i v e c. : 3. 4 euch) 1. RCS subcooling bated on core e.< a t TCs greater than subcooling listed $in 2. GG pressure-stable or decreccing 2. RC,3 Thot-stable of decruaning 1

-:;r u ' ;1 t T C s., t o t 1 :2 tr dei

.ang 1 5. RCO ' cold-at naturat en temp. 'or ~3G pressure nEFEFENCE DVPG EOP ECA-0.1 Pg. 13 D\\" LP LRT-VII-S t EC A.C. VA 0C0 0550 EMI.02 4.4 000 056 EK1.21 4.2 i 4

o ^ I TCCOURE ~ ~ ~ ~ ~ ~ ~ :,~3; 7;Q ~~ ~NQRtd AL g-@ NC R M%~ ~"~ p~~'~~~~~~~.iND PAGE 55 IM rEXCY ~ ~~ g n. - --~~ _.: ur.u w. w_6_..wa. h i h EF: - ECAVER VALLEi O -90/0G/ 7-r ; GCC, L.. 7; m ~ ,7 q~z y,., - 3, O A G,ER 7.07 (2.,_ C(N~10) - 35 rom lifetime expouvre allcwod CO.25] 1 1 4etimo to date a 7 000 mrom - 700 mrom - !!700 mrtm :0.25] L t.v.21 'ifotime a. alt al.- "3000 trom ~;?00 mr :m

CO mrem CO.25]

total quarterl y aapocure available 7000mrum 700 mrum

2!00 mrom z

'O.TS] i.,y .l175mrom/hr gamma + 450 nrem neutron n 112"mrem /hr total [0.25] nn..aan can pur+ arm tau::.:0.25] an. 2 at 0.5 ua:n) L.

1. Carry a rudiation monttcring instrument which continuously indicatou dona t*ato in the area.

I 2.Cairy/ wear o adiation monitoring device which integratus the dose ato and a l a r.wa a t a grocet valua.

1. L te accompanied by a qualified i ndi vi du..tl who i n equi pped with a radiation monitor ing device.

i CFCT,CNCE UA 194 001 K1.03 3,4 .M 3 Li~ -RC - 01 CD 17, 2~. 7 19M001K103 ... WA'E) t V ' 1lCP

7. OE (2.20) 6 a,ilea ancrt-land t.

.ito producta no accay _0. J J. ~ha 150 hour i decay time la uned in the accident analysta CO.13. h. 1. To itnnure Iufficiont cocling cpacity to cemove decay heat and ma t n t. a t n the reactat ' e u.

h ar i 140F au required to

(. a e rotuuling todo CO.GJ.

2. To maintain uuffittent circulation t a.attit m i.' t the effectu of a t:or on dilution incident and prevent baron statificaticn CO.53.

c. To ensure the depth iu ;ufficient to remove 99% of the atinumed 10% luJine gap activity ' a '. c a u e d froa a rupture af an ir wat. mad fuel assembly CO.52. The 25 feet of water in used in the accident analyntu CO.13. ECFERCNCE i 'A 004 030 GO.06 3.4 034 000 F1.02 7.2 SVFS LP-FHP-1.0 EO No. 10 )

g _..... _..u,,, e D t n C..3. .. N Q ? n ta n E N O R_ M_ (' L... t J M_ E.R G E. N C.'./._.'-. N D P(4GE 56 1 u =. sa u.: t. - a -. 2-4.t.; . n. ,i.u_.. ,xJ,,Ofi<,,, o,-1.;(n.. .. r u.s t s .6. +,.,.. s3., ., 3.,.; _ %,,2 .. _.. L. 3, y. di. m - m t ,E T. E F 7.09 (:~ 00) ..t. Pocutablishment of food flow may renult in thermal a n d / ct- ;nechanical .;h oc !- to the *:v t: c c that ;c. tic result in 19o1 age or tubo rupture CO.333. If thia occurreo to a faulted CG, leakage through the fault could not he controlled until the fault w3i cocrocted CO.332. Feeding to a non raultoJ GG would allow conteal of the r el eat,e af tubu l eal:ag e occura CO 333. D. ~ _, e saucu heat input to the ACC CO.03] which a:< t u n c.a the affectiveness et the rematning water inventory in the SGc C0.332 and allows more time avicro the operator nuut initiato +'oed and bleed C0.002. Food and bleed deplete RWST inventory CO.333. At 20 feet thern should Ou ;u f fi ct ?nt wat er in the recirc. cuap for SI nuttion CO.333 and the m.s t i ; n g F.J5T .9.a t e r.... rouervud 4 ar upr.ry pump usagi :003]. REFEfiCNCE t 4 N,'PC ECP E X EC. VOL

1. 5 D. 4 FR-l t 1 if' v:

.I $ FR-H.1 DW G LP -LRT-VI I-/ C 'lon E, * .1 2 FA JJO 000 Eh !. 06 4. ', C00 030 El'.7.00 4.2 [ 00007 f3): ~06 C 000 ? C}'.50 9 ...(l'A'0) i l I i i ,t 1 g.. 'e "%) i 4, l i 4 I _xl i

e.s .,...r. . - 7.-, s. - - - .. c A....

-..2 a

L.: w : = H a.. iL u.L - g: w h ' q' J' -- ' T 'L MG E- .g e .. L,.s .s.A '12ar la:attm. -2, "., , 0..., i ~ ni t' utuaccoc i ., a d.,.,. m,, ~. .s. r.

'EN 7 7 71ED Le hts l iru t

';coadod CC."01 O R /PrN71F/ID LEBKMGE (AFEDED ?,; , ; e, i o. m-,. - -u r3,;3: og # 5. 2. Gtv) Z. / GPni : ll l 6M @ L. C ACC s tr > $co GPD S.G L E Abt AG E LIiniT (IF AsswnP ritN$ GT&TED) r.' .1 _. ~.w. . s ?..o.2; T5 3.,.6.U V 1 'nJ3) 3,- s.. 3. o. t- ._s.__. t .. a t ec or. r a t e, t.; cut or .w vice. I < : t. t ;. av r?r od bt;rd unea to 11 :,t uut-of-Service Ma;cr safety and 1 . a f. v, 21, ',d .: G.

.: n t b..
1 L ,e.s) .l i. .peraticnn person perfor<ung ;he val,ing a +- .t w i ' c h t i : q peration. 2 I x.tcr Operator cuatgneJ
t. a tha :nntrol bs.Ard.
T r.] NCOI ?ncur en board t u av d: t.>d b, L1 tot aporc tar r.- rr.r. r ,,.I -, -, -, n._1 . d,.). _. U., e i. -a l. rga.+ the.u 6 u >A 1 c11.?D 1 A1.06 !.4 194001A106 .. O A ' S.' 1 l l l I
6
. _.. C.M_ _! !_) 7.C T R _A T _7 t., r-_. u _ F._ i_c 0 C_ Z_ D U r_. E 0_ x C C N.. D t. _.I. n t J _3z _ W. D..
'u _I M_..I T_i."_ T..!. " N_ G PAGC 58 2 2 a .....v .~4.__....,- c .:c. i.;n_. -. R I.~m~_~,.. a s v ...r.. 4 33 .Mut' 3., , u s,1 i; h t R a at O.!! aach) t .h i LEER 9 Afiuctc saioty gutamo 8 Tah '6 EFP/I-t FIR F. W )+ l C H PCT'UNT//74 4 y) mc.~.. l.!n u u u a l Event 3 team Genur'atur activity levul recueds 0.10 microcuric/ gram aquivalent I-101 T al; o EP*'/I-1 .;EIEAENCE IT P 'Icipi ementing F'roceaura EFP/1-1 tA l'74 C 01 A1.16 4.4* 174001A116 ...OCA'S) ANEWER 8.04 (1,80) ~c , r e r ; -- u p runt be c ur rn a n at e d EU.LJ plant t u c.ib o u t to enter mo:2 e 2 C O. 6 J anc no a u c h.a nig u n c a n n o t. be made s i t t-oliance an an action statement CO.63. .,t DVTC LP-ECC-46.1 EC 'Ja.' l FA 020C00 GQ.11 2.3 n, c j ~ l 0:30003011 ... o:A',) l I i ?A S 4 .I W .i i 1 l i I ul%fu%-- _ e-.
,o 6 l< m- -s
-- - e r
._. u 2 ".r..V.1 A'2.C _ _r.:.n - - : L w n x a 'a _. n s. a::t w a.._ _A..r'. i o I Lv _ N1'n w ': p e c "9 4 v.= w a = a + s r- .-.; L. .7 if u t. ' ' 's J Mrs/ 'O/ O i
o.. c o
.,Je suu ;0.20]. The plan-an <; u:.t i n tie to caer.ite for _ icera :0.503
dec ths-A ann

:d t. ; u.i c t.
2 tai.cn u.'.11.:vt .c
ver, ta the
' t.r.ua ..h t f t c omp i c men >; :D."OJ. i. i ' u r l 2 2i r Jih t f r .up ar' am ' O. 's C l a c i ct o r Opernting Cu p u '"..or (any <t J. $ oach' . i t.; t. 2 n t Plant 11ana g er ~1ont.1an a sj er h iN E@- - Mancger, .'Juc l e a r Opcr v. onu UNIT Nnage, Nuclear S a f e.t' ,. s. 2 P r o u l t:en t, .b c l e c r g --- GR90P A ce Pe n dant. _Po w s t. G EIJUR AT)tU u C C VTNE r c_ F. f. r.e- .s t m. yr. tr.g03..1G-1 EO No's 1 '- *: ,.,, 1. u.,s.. .s.* 4. DVP' CM 1/2.4G.1 FROCEDURF. 0 0 2 M'0 C O 205 194001A103 ... (i: A ' S ) Arc d ii J.06 (2. ;0) ~. al. J;atI c.. vi .!.o '? oculJ i.t a.. ' - t. i. t .:.. c. ] Th; Unit % clear Ope stiroj Gupervincr CO.42 r _, E rs C f r L T. unch uni * :U.43 _s n d one a c c i 1. u n.u tu c - c t
r.m the plant n.
a;ement utaff CO.41 4 ;ayu C3.43 T 1av: [C 42 . 7. r y.. g ia
C01 A1.01 '.. 4 DVrF uT-900-4E.1 CO No.9 P/F 3 C M 1/2.48.2 D

G4001A101
... O: A ' S ) t
f s 4 g... _ _ J_ D_ M.I. N._ _I S T, F V...T V Q. *.'.R_ G C_ E D U R E. S... _. C.. ' ). E I. _ _I_ Q F ii. t _ A_ N D.. i I M.I. T o_ _T _T. C N_ S.. PAGE 60 . N. M.~ ~ -. ;m ER u,' h P 'l'-ERI:G5, __ O si,. - ..k, ,. 3 1-3 No.Kl )a % SourF. s,.. ,n ot i f t c a t i c o (nu reo phtne) ( CO.251 4. 74 2.2 . s o 7-
p. g..., s 70 day 00.25] -
--7 i CO.25] L. E R ' ' i a u.- ~pcrt tNa.1177 CO.25] 4 NO3'NGCF CO 25] No rapart required CO.232 c. I hour report (No.127) CO.25] NGS/NSCF CO 25] !O day CD.252 LER CO.252 P~FERENCC iA l'74001 A1.05 3.6 194001 A1. 08 !.1 EsVFG LP-505-40.1 EO No.19 DVFG EAP 3D .' ' 0 01. + 10 5 191001 A10E .r A ' :' i, e. n a..,. a ( _, <, n. ) - s 1 .it .n t t al .u cpor,L;u C D J,3 1 _r ms.iteeval .;u m a .e_ te c.cc.
vd 2-earval CO.53 or 3.25 t.mun the apectfaed 1 n t er v.31 t or tt:r no (3) consecutive uurvoillanco
. n t.: t-al a 10.52 ~, c.u.th; .v a u per f ormed a. t i n t r. e .il : avec 7 9. 7 5 c 4 v <, 21 . 25 a 30./5) Jul' 5
t. a August 12 in 23 days CO.52 3
f "n to August 12 as 100 days rhich tu althin the a l l t. W e d 100.'5 days s:1 ( ;.25 100.75) CO 5) u REFCRCNCC i A 064000 G0.05 2.9 064000 00.11 2.7 OVFS TS Para. 4.0.2 I LVP3 LP-SOS-36,2 EO No.5 064000G005 064000G011 ...(KA'S) i i l \\ t
( L i \\ .r ~ .,. 7.,.,.- _r q .-...~.._1 _1..=.__,,,..t... m u. _ u.. p ~1 z t _ _ n... =. _ _ _. u e.r. u u '. ':. ' F "~' 's
r s
.(.. 6.. 4 ,,r ~y .u.- il _ the _m,trunun
0.!] ~ n.cnc c.: n u t r v e. t i s c l,. [0.21 ar allow

1
'a att<a an; 2u-at '. tion C0.03. a' e ..ct cn . n
e ccmpar.ucn in th two e c d u n d c.n t i,1 :.t r m.c n t u ~eading the a r. e parameter rp utt'
,,.s.- ! .s t 1, t. e '. 3. T ',. o, ,ction
r. e c., u a r y C0.2],
t o c i ' 11 r. q ". r ' p. p i n g the cerctt- 00,33. tos I arevent exceeotng a a uvy .Amt.. . L,. .- a per oonnel CD.T2 ~
r o t ec t stettan r e.-
ot J.3 y.a g u :c a t a r.; o n e qa t p n.en t t,o, .s .rL -.... : n.,, .~_o .u. ...,,.. v. 1. h. r ,,., m L. n, e n R. A. 1 i 1 N C01 A1 !! 4.1 f..A.c) ,.Ly,! ,..L ) ,.h.i-pa rg k) {.m. -w re g t .s r.w=., g,... e s (
7 ', -
F P- ..-. g p, i .'r,7 ) t-U Ts C t C r =. O r 3 r )..w r*, 6 a. e .,f.,.s 'A t,. W ,f-r '4 r r.' G L U T Z Of~ If OG LVI 6,. IC.US) 4 '. u c t :. an acr ed Hi g.) Tave CO.25] incure tnat the ...ctcr ~ -tu 7CC Co 10? ,4.: n. -heir Gafety .s.. ,s 2. r uported z; i NFL C 3. nathin ^no i tc ur E2.25' 3entcr Manager-f.uc ; ear J p e r.a t.1 n a twtther. 24 r c ar,, ~. C. _ S 2 0FC m + hi n 24 Scut CC.23' -....,... -,.,C n. <..e i,4 .L'OD00 GJ.05 3.c ' ', T ', C'veut t on ban 6 No. 3.i T.VF# TE CECTICN 2.0, 2.2 UND 6.7 ,1
1
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ML20155E327

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ML20155E327

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