ML19241A840

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Forwards Info Re Examinations Administered to Licensed Operators & Senior Operators.Includes Examination & Grading Key Summary of Test Results.Individual Answer Sheets Encl
ML19241A840
Person / Time
Site: Arkansas Nuclear 
Issue date: 05/28/1979
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Gilinsky V
NRC COMMISSION (OCM)
References
FOIA-79-98 NUDOCS 7907090450
Download: ML19241A840 (50)
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{{#Wiki_filter:* 7 l-ff0 / q (9. e i. R. Boyd ?1. Groff (NRR-2908) (c / 4 DISTRIBUTION: p- 'yG y s H. Denton N. Huahes (_NRR-2908) r )d E. Case D. Vassallo D. Runch D. R.oss w/ encl. R. DeYoung h - ~ ~ - R. ".attson V. Stello U fiEMORANDirt FOR: Comissioner Gilinsky FR0rt: H. R. Denton, Director, Office of Nuclear Reactor Regulation THRU: Executive Director for Operations SUS.1ECT: EXNtINATION RESULTS - ARKANSAS MllCLEAR N0.- ONE, tmIT 1 In accordance with our telephone conversation on ?!ay 27, 1979 with D. F. Ross, we are furnishing you with the followina infomation regarding examinations ad11nistered to licensed operators and seni e operators at AN0-1. 1. Examination 2. Exanination Grading Key 3. Sumary of Examination Results 4 Individual Answer Sheets (10) These examinations were administered to evaluate the operators' understanding and knowledge regarding the Til-2 incident, new AMO-1 nomal and emergency operating procedures and new administrative procedures. We will provide you with copies of the Oconee examination, grading kc., and sumary of results per your amo by June 1,1979. , c.= g :- =

== Harold R. Denton, Of rector Office of Nuclear Reactor Regulation cc: Chaiman Hendrie Comissioner Kennedy Comissioner Bradford p= Lomissioner Ahearne

Enclosures:

I?- 1. Exanination 3)l 2b4 E 3. Sumary and Exanination Results [G 2. Exanination Gradinq Key 4 Individual Ansver Sheets (10) E i: '79070909 f' SEE PREVICIIS YEt.f.n't Fno DpcVin!!; crytritnnc?tre L. E CO 1RR E- .,,,c..N T A CT : Paul F. Collins, OL8 NRR . 49-2NP.4 .u .. e

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I.... 1 I; s t*:0M'"X" FOR: Comissioner Gilinsky . M.. ~ Denwood F. Ross, _ Deputy Director, Division of Project Management Office of Nuclear Reactor Regulation EXgNATION RESULTS - ARKANSAS NUCLEAR NO. ONE, UNIT 1 R M CT: In accordance with our lephone conversation on May 27, 1979, we are furnishing ya; with the fol'owing information regarding examinations administered to licens- - ed aperators and senior oper'ators at ANO-1. N 1. Examination 'x 2. Examination Grading Key N ':. Surr:ary of Examination Results 4 Individual Answer Sheets (10)N, N Nse examinations were administered to evaluate the operators' understanding and r.r.a.: ledge regarding the TMI-2 incident, ne+ AN0-1 r.ormal and cergency operating, enadtres and new administrative procedures.\\ The passing grade for this examination was 85% Ihis grade was considered appro- .riate for this examination and equivalent to the 90% passing grade required on e t.conee examination because it contained sixteen' questions vis the six at Gconce and the questions explored each area in greate'r pth than Oconee questions. ' 2 tiil require S!:UD, Crystal River and Davis Besse to develope examinations of this length and depth for their licensed personnel and require a passing grade of 25% \\ p \\ N !l.t. .o JnCT: Paul F. Collins, OLB [(. 49-27406 E p1 265 ,-v.- --r.e--. ---m-----~---.... - - - .;'..;1E.1 "~' ' ~ ' - ^ - ' -

4 ~ h p ~ ~ - Commissioner Gilinsky 2- !!e will provide you with copies of the Oconee examination, grading kev and sunnary of results per your memo by June 1,1979. 1 ~ Denwood F. Ross, Deputy Director Division of Project Management Office of Nuclear Reactor Regulation cc: Chairman Hendrie Corrissioner Kennedy Co.missioner Bradford Comissioner Ahearne {'p

Enclosures:

1. Examination 2. Examinaticn Grading Key 3. Sumary and Examination Results 4. Individual Answer Sheets (10) R. Boyd E H. Denton la E. Case ~ L.: h-D. Bunch . DeYoung ji:. n R. Mattson p M. Groff (NRR 2908) ((F V. Stello N. Hughes (NRR 2908) iW

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W,CL, ULLC. /L.1 p* **co e fg UNITED STATES >s, g NUCLEAR REGULATORY COMMISSION y e wAssiscion. o. c. 20sss 5 o %.... / + MEMORANDUM FOR: Commissioner Gilinsky FR0fL H. R. Denton, Director, Office of Nuclear Reactor Regulation THRU: Executive Director for Operations

SUBJECT:

EXAMINATION RESULTS - ARKANSAS NUCLEAR N0. ONE, UNIT 1 In accordance with our telephone conversation on May -27,1979 with D. F. Ross, we are furnishing you with the following information regarding examinations administered to licensed operators and senior operators at ANO-1. 1. Examination 2. Examination Grading Key 3. SunTnary of Examination Results 4. Individual Answer Sheets (10) These examinations were administered to evaluate the operators' understanding and knowledge regarding the THI-2 incident, new AN0-1 nomal and emergency operating procedures and new administrative procedures. We will provide you with copies of the Oconee examination, grading key and sumary of results per your meno by June 1,1979. Harold R. Denton, Director Office of Nuclear Reactor Regulation cc: Chaiman Hendrie Commissioner Kennedy Comissioner Bradford Comissioner Ahearne Enclosur.:s: 1. Exam nation 2. E.xanination Grading Key 3. Sumary and Examination Results 4 Individual Answer Sheets {10) CONTACT: Paul F. Collins, OLB 49-27486 yy 267

ATTACHMENT D PIQUAL EXAM TMI INCIDENT AND SMALL BPIAK f. ~ 1. List the major mechanical failures and operator errors that created or aggravated the TMI 2 incident (list min. of 4). 2. Within the first eight minutes of the TMI event the pressurizer level indications went off scale high. As you now understand it; a) Was the indication reading pressurizer l'evel? b) What was the cause of the increasing pressurizer level? (be spe.cific) 3. For ea:b of the given failures / errors in question 1 above, explain what is done or has been done at ANO to prevent this from occurring here? 4. List four (4) objectives of the emergency core cooling system after actt.ation and of operator action on a loss of coolant accident. 5. What things will cause the RCS to respond differently on a small break? 6. On a LOCA large enough to depressurize the RCS, the availability of auxiliary (emergency) feedwater and the operation of the RCF's, have little to do with the outceme of the event but in a small break where the RCS pressure stabilizes at approximately secondary side pressure, they plan an important role in the outcome. a) Explain why feedwatet and RCP operations have little effect in the LOCA but significant effect in the small break. 7. With no RCP's running, how 20 you as an operator verify that natural circulation is occurring? 8. On a small break without auxiliary (emergency) feedwater that reaches a semi-stabilized state the operator should open the ERV if feedwater esanot be obtained and the RCS pressure is increasing. He should a*. this time also provide all the HPI and makeup possible. a) What is the goal or reason behind taking these actions? b) What would be the consequences of not opening the ERV under these conditions? 9. List the' transients that have similar initial plant responses to the small break. 3)) .b

e ATTAClCIENT D (CONT'D) 10. What plant indications or conditions would alert you as an operator to whether a transient is an overcooling situation of the RCS or a small break? o. 11. Whst are the control room indications of the RCS temperature margin to saturation? 12. A number of operating procedures contain the statement " verify emergency feedwater flow". What indications do you as an operator have with which you can verify this flow? 13. Explain the two additional conditions which trip the reactor auto-matically. (trips installed during the recent shutdown) 14, The phrase " verify >50 F margin to saturation in RCS" occurs in a number of procedures. What parameters of the RCS are varied to obtain the >50 F margin? 15. What are the conditions that cause " auto start" of the electric emergency feedwater pump? 15. Refer to the attached figure. In which region would you operate at full power, steady state operations?. In which region would result in void formation in the reactor and RCS piping? e e N \\\\

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~ Requalification Exam - Key TMI Incident and Small Breah (28 pts.) a) EFW valves isolated

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b) ERV stock open c) Containment sump not isolated d) HPI stopped e) RCP's stopped f) Pressurizer level used as indication of RCS inventory to the ex-clusion of other indications. I'linimum of 4 required at 0.5 pt. each) 2.0 2. a) Yes 0.5 b) Void formation in RCS forced water into pressurizer and level increased. 1.5 3. ' a) Emergency procedures changed to make re-verification of status, EFW flow indication added. b) Lowered RCS High Press. trip sp, raised ERV sp, procedures changed requiring ERV closure verification or isolation of ERV in certain conditions. c) RB Sump normally isolated, no auto transfer at fluid. d) Not secured until >50 marg'in to saturation. e) Procedure revised to give guidance as to when RCP's can be stopped. f) Procerlure changes direct the operator not to rely on pressurizer ~ level alone, use redundant or independent indications such as mar-gin f.o saturation. (Minimum of 4 required at 0.5 pt. each) 2.0 4. a) Remove D.H. 0.5 g b) Cover core. 0.5 c) Transfer heat to heat sink. 0.5 d) Establish long term cooling. 0.5 5. a) Size of break b) Location of break ( c) Availability of RC flow d) Availability of EFW flow ( e) Amount o' ECCS provided (Minimum of 4 required at 0.5 each) 2.0 g L 6. In large LOCA, the DH is removed by the boil off through the break. In small break, the boil off will no-remove enough heat and the f OTSG's must remove this heat. 2.0 t I 7. Converging T and T with indicated RC flow and 'T with no circu-h t lation T rapidly 1.5 h ( 3y} 2.7 S

S. a) Provide for incr.ase 3 boil off to remove DE so systen pressure can be controlled for depressurization and cooldo n using ECCS, ER'.', a n d t h e b r e a k. . 1.5 b) Increase RCS press-re and temperature, reducing HPI flow, insufficient DH removal. 1.5 Overfeed OTSG or High OTSG 1evel. 0. 5 b) Steam Line Break 0.5 ~ c) Rx Trip 0.5 10. Overcooling: HPI repressurizes RCS and RCS will remain or return to subcooled condition. 1.0 Small Break: Converge to saturated condition..Repressurization will follow saturated condition. 1.0 OR RCS Temperature, RCS. Pressure, Pressurizer Level, Margin to Satu- .ratica, and RB Sump, Rad Monitors. 2.0 11. a) Computer indication of margin to saturation. b) Tsat - 50* indicator on RCS Press. recorders. c) Saturation curves on p.nel. (Minimum of 2 required at 0.5 pt. each) 1.0 17 a) EFW flow indication on panel. 0.5 b) EFW pump discharge press. and OTSG level t. 0.5 11 a) Rx trip on turbine trip if >20%FP. 1.0 b) Ex trip on trip of both MFP's if >10%FP. 1.0 14. RCS Temperature and RCS Pressure. 1.0 \\

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a) Loss of all 4 RCP's 1.0 b) Loss of feedwater fisw 1.0 le. a) B 0.5 b) A 0.5 331 272

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