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Exam Rept 50-277/89-18OL & 50-278/89-18OL During Wks of 890814 & 0918.Exam Results:Written Exams & Operating Tests Administered to Six Senior Reactor Operator Candidates.One Candidate Failed Operating Exam
	ML20011E065
Person / Time
Site:	Peach Bottom
Issue date:	01/23/1990
From:	Conte R, Sisco C; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20011E063	List: IR 05000277/1989018; ML20011E062;
References
	50-277-89-18OL, 50-278-89-18OL, NUDOCS 9002070215
	Download: ML20011E065 (84)
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~ . U.S. NUCLEAR REGULATORY COMMISSION REGION I h < OPERATOR LICENSING EXAMINATION REPORT

, EXAMINATION rep 0RT NO.: 89-18 (OL) w , .J . ' FACIO TY DOCKET NOS.: 50-277

~50-278 , .. i FACILITY LICENSE NOS.: DPR-44 a DPR-56

i LICENSEE: - Philadelphia Electric Company' i FACILITY: Peach Bottom Atomic Power Station o =j ' -EXAMINATION. DATES: August 14, and S.rptember 19, 20, 21, 22, 1989 ' EXAMINERS: .A. Howe, Senior Operations Engineer . G. Buckley, Pacific Northwest Lab ' D.jDraper,PacificNorthwestLab CHIEF. EXAMINER:. )Mt[/ M O Cai1 Sisco, Operations Engineer Date ' /!JJ!90 APPROVED BY: ichard Conte, Chief, BWR Section- ' Dat'e ~ perations Branch, DivisionJof Reactor Safety ! SUMMARY:. Written examinations and' operating tests were administered to six

(6) Senior Reactor Operator (SRO) candidates (Instant). All candi- ! dates passed the written examination..One (1) candidate failed the operating examination.

p Procedural errors were identified by the examiner in that all L information required to complete a Surveillance Procedure was not ~ Plant Operations Review Committee-(PORC) approved. The examiner' i identified that administrative controls of safety-related keys in ' ,~ , " the control room were weak.

A control room Trip _ Procedure table ' was.found stuck in an unusable position by the examiner.

The High y' ' Pressure Coolant Injection (HPCI) system mechanical overspeed trip ' automatic reset function did not operate properly _ during a i surveillance test and the system was declared to be operable by ,o 9002070215 900123 PDR ADOCK 05000277 'V PDC i , -- - - . - - -.. . - -. . - -. - - . '

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i .. O' g . plant staff.

The question of HPCI operability was resolved. based: - on a written. safety evaluation' performed by the licensee after s questioning by the NRC staff. The licensee's initial review of .this deficiency reflected a weak inquisitiveness on the part of plant management.

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DETAILS 1.

INTRODUCTION AND OVERVIEW The NRC examiners conducted this initial examination for six (6) Senior Reactor Operators (SRO) (Instant) canidates. The examinations were administered'in accordance with NUREG 1021, Rev. 5, dated January 1, - 1989, Examiner Standards (ES). The results are summarized below.

l SRO l l Pass / Fail l I I - l l Written l 6/0 l i-l l 10peratingl 5/1 l

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l l Overall l 5/1 l--

I I 2.0 EXAMINATION RELATED FINDINGS / CONCLUSIONS-The following is a summary of general strengths and deficiencies noted on the operating tests. This information is being provided to aid the licensee in upgrading license and requalification training programs.

No licensee response is required.

STRENGTHS Response to alarms

Recognition of entry into ON, OT, and TRIP procedures

Use of procedures

General administrative knowledge

Ability to identify safety-related keys

DEFICIENCIES Communications

Control Room command function

Of f-Gas system knowledge

There were no general strengths or deficiencies noted on the written examinations.

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t 3.01 ADDITIONAL'FigpiNGS I 3.1 On September 13, 1989, the licensee identified that the HPCI system mechanical overspeed trip automatic reset function did not operate properly during the performance of Surveillance Test 21.3 " Adjustment of HPCI- 'Overspeed Trip Reset Time."

The examiner became aware of this problem while providing inspection , support to the NRC's resident office during that week. After questioning by the examiner, plant personnel brought the question of HPCI operability to the Plant Operations Review Committee (PORC). The PORC meeting to review HPCI operability was attended by the examiner on September 13, 1989. The discussion by the PORC committee of HPCI operability was brief and appeared cursory. The determination of HPCI operability based on a written Safety Evaluation was not requested by plant management or the PORC. After further discussion with NRC Region I staff, plant management performed a written Safety Evaluation review of the HPCI operability.

The licensee's written Safety Evaluation concluded that HPCI was operable regardless of the above noted deficiency. The FSAR (page 6-4) states that the system is capable of automatic restart following a mechanical overspeed. Despite this statement, the licensee could find no safety design basis for-this function.

In light of this, the licensee concluded that HPCI could perform its intended safety function.

Subsequently, NRC Region I staff reviewed the licensee's Safety Evalua-tion report, dated September 17, 1989, and concurred that the HPCI system is operable with a failure of an automatic reset of the mechanical turbine overspeed trip.

Plant staff performance during the initial licensea review of HPCI opera-bility was considered weak in that there was a lack of inquisitiveness and detailed assessment of the consequences of the failed surveillance.

The licensee's subsequent written review was more thorough and detailed to adequately assess HPCI operability.

3.2 The examiner identified that the Radiation Release Trip Procedure (an Emergency Operating Procedure) table (in Unit 2 control room area) was stuck in place which made use of the procedure impossible.

The licensee was eventually able to operate the table mechanism and released the procedure. The table was subsequently repaired and returned to service.

3.3 The examiner identified that Surveillance Test procedures 7.6.1.J.

" Determination of Total Noble Gas Release Rate" required the use of graphs and pressure correction factors that were not PORC approved be utilized to complete the surveillance test procedure.

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. . . -! Theilicensee revised the surveillance procedure and acquired PORC '; approval.of all information necessary ~to complete the surveillance test procedure.

3.4 The examiner identified that the posted control room safety related key inventory did not accurately reflect the content of the locked safety related key repository. 'The examiner identified that a detailed ...* inventory of the safety related keys is not routinely performed.

' The licensee initiated corrective actions to revise the posted key inventory and drafted a Routine Surveillance procedure that inventories i safety'related keys on a monthly basis.

4,0 Management Meetings: 4.1 ATTENDEES NRC STAFF /NRC CONTRACTORS

C. Sisco, Operations Engineer, USNRC

'* T. Johnson, Senior Resident Inspector,USNRC

T. Cribbe, USNRC-F
D. Draper,-Pacific Northwest Lab

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G, Buckley, Pacific Northwest Lab Facility personnel

F. Polaski, Asst. Supt. Operations
J. Franz,. Plant Manager
J. Cotton, Superintendent Operations
K. Patek, Sr. Instructor E. Till, Training Superintendent
Denotes those present at the exit meeting.

4.2 SUMMARY COMMENTS On August 11, 1989, a pre-examination review was conducted at the NRC Regional office. The Facility was informed that, although a post-exam review was not conducted, comments on the written examination would be accepted.

These comments were received at the Regional Office on August 18, 1989.

The Operations staff was cooperative in maintaining a control room environ-ment which was conducive to the administration of the operating test.

i-The examination security for both the written and operating examinations '- was excellent.

l An exit meeting was conducted September 22, 1989.

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1.* : ... .:. ' . 6- , The results of the examinations were not discussed at the exit meeting.

Evory effort would be made to provide the applicant's results in approxi-mately 30 working days.

The Additional Findings (Section 3) and the licensee's corrective actions were discussed during the exit meeting.

Attachments: Examination Report No. 50-277/278/89-18 (OL) w/ Attachments Attachment 1 SRO Examination and answer keys Attachment 2 Facility Comments Attachment 3 Resolution of facility comments Attachment 4 Simulator Fidelity report

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. s & ? i Nuclear Regulatory Commission i Operator Licensing , 4 Examination \\ < l -\\ a j . - ! i ! j i This document in removed from j Official Use Only category on ( date of examination.

~ . . NRC Official Use Only , I t - - - - _ _ _....

' ' ' U..S. NUCl, EAR REGULATORY COMMISSION

L

' ' SENIOR REACTOR OPERATOR LICENSE EXAMINATION . ' ' - .1<EG I ON

, FACILITY: Eeach Bottom 2&3

REACTOR TYPE: BWR-GE4 DATE ADMINSTERED: 89/08/14 CANDIDATE: INSTRUCTIONS TO CANDIDATE: Use separate. paper.for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses af ter the question.

The passing grade 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 CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 33.00 __43.42 5.

EMERGENCY AND ABNORMAD. PLANT ' EVOLUTIONS (33%) , 43.00 56.58 6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%) 78.00 \\. % TOTALS FINAL GRADE 'All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature s e _ _ _ _ _ _ _ _ _.

_ . NRC RUhES" AND GUIDEh1HES FOf< h1 CENSE EXAMINATIONS Ibrjne;the: administration of thin examination the following rulen apply: ' . .

Cheating' on-the examination meann an automatic denial of your application .bnd.cou]d result in more nevere penaltien.

2. After the examination han been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received =or given assistance in completing the examination.

This must be

done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. ;You must avoid all contacts with anyone outside the examination a room to avoid even the appearance or possibility of cheating.

4.

Use black ink or dark pencil only to facilitate legible reproductions.

l S. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

. -1 6. Fill in the date on the cover sheet of the examination (if necessary).

i 7.-You may write your answers on the examination question page or on a-separate sheet of paper.

USE ONhY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

8. If you write your answers on the examination question page and'you need N-more space to answer a specific question, use a separate sheet of the

paper provided and insert it directly after the specific. question.

DO NOT l WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.

9.

Print your name in the upper right-hand corner of the first page of each sectioh of your answer sheets whether you use the examination question

~ i pages or separate sheets of paper.

Initial each page.

l .10. Before you turn in your examination, consecutively number each answer- -sheet, including any additional pages inserted when writing your answers on the examination question page.

11. If you-are using separate sheets, number each answer as to category and number (i.e. 1.04, 6.10) and skip at least 3 lines between answers.to ' allow space for grading.

I 12. Write "End of Category at the end of your answers to a category.

" 13. Start each category on a new page.

'14.

Write "hant Page" on the last answer sheet.

15. Use abbreviations only if they are commonly used in facility literature.

Avoid using nymbola nuch as < or > signs to avoid a simple transposition error resulting in an incorrect answer.

Write it out.

16. The point value for each quention is indicated in parenthesec after the quention.

The ainount of blank apace on an examination quection page in NOT an indication of the depth of answer require M _ " ., W11712how Lal.Fcalculationn:,Enstbods, tor; annun,ptionn--used t to.obtain.'an annwer ' y: {-y - E_

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hiQ'18 . , p:a.4 l.g Partinli credi t? mny:- bei civon. Thorofore.DANSWER'AhL PARTS-OFLTHE QUESTION

tag;p po noy. LEAVE ANY AttSWEREBLANK'.. NOTE: partia]7 credit will-NOT bel ([ - Egivenf ori'. multiple; choice questionn.

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, 119h Proportional'crading t wi11 be npplied.

Any additiona]: wrong:information r > that4 is.provided.may-count againct you.: For example. $f-a quection in [

worth one. point"and'aska"for'fourEresponses, each of'which is' worth'O.25

.! ' " _ points, and you:give=five responses, each of your; responses will-bel worth , -

0.20" points.

If one:of--your five responses is' incorrect, 0;20 will.be! .

F n deductedr and your total credit for 'that question will be': 0;80..instead: of -; - ' ' J1(00cevenithought you got the four: correct answers.

' i200: If the?intentLof a questiori is unclear, ask questions of ;the. examiner < . l only.

e _: > {: ..21.;When turning in your examination, assemble the: completed examination.with G .. .. . c -

g; . . examination questions, examination aids and,answerfsheetn.

In : addition, 'l turn in all: scrap paper.

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: 22G To pass the: examination. y'ou must achieve an overall' grade of-80% or:

> f' greater.and:at least 70%-in.each category.. ~ "23. There is'a time limit of (6) hours for completion of-the examination.

. (or.some other timeTif less that-thei. full-examination is taken.)

H s 24i When:you are'_done-and have turned in.your examination.. leave be examin - N L " , .ationLarea'asidefined:by the examiner.

If you are.found in this: area'

' 'while?.the' examination is still in progress, your.licenseLmay be-denied ors ' revoked.

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- JOilESTION 5.04 (1.00) Trip ProcedureLT-102, " Primary Co.itainmer.t Control,". prohibito - .use of the Standby Gas Treatment (SPG1) System if drywell'

temperature' exceeds 212 degreen F-. , SELECT,the ONE (1) renponse;that correctly describes the potential ' impact of initiating SBGT System with drywell temperature greater than<212.degreen F.s ' t

(a,)

Collapse-of SBGT Syctem piping if containment oprays are initiated._

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F , , .iU STIONi 5.06 (2 50) , , . "Af t.or receiving a ibomb threat,; the Shift Manager has decided ^.to immediately evacuate the control room per procedure SE-1-, " Plant Shutdown '. g ;from_the Emergency Shutdown Panel."
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x .( 1. 5 ) :- , b.' -EXPLAIN the' purpose for placing. instrument-transfer'awitchec ' , J' --in the "EMERG", position at-the Emergency Shutdown Panel.
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" ,:,m . ,, - , CU'ESTION 'biOG1 .(l',MI)- ,,,:-. - MATCil theLactions listed in Column A,with the reactor preauure t-at which the action should occur from Column;B.. (NOTE: each: pressure may. be used more than once or not at-alid

( 1, $ ).- m

, Column A Column B ' , ' ' , , a.
lthe initial 'four relief valves 1.
'1040 psig-
have ' actuated :on the Main Steam: System '- > 2; 1045-psig , b.- Reactor SCRAM: ' .. . . 3.
1055 psis- = ' - ) ,

c.
'! Reactor. Hit Press" alarm ~ 4, 1065 psig.
t - n Ed.- entry into T-101, "RPV Control"- < 5.
1105 peig Ej .e.f .two safety valves actuate on.the j < Hain-Steam-System-6.
1115 psig s cf4 Recirc MG drive motor breaker. trips 7.
'1120 psig m i 8.
"1230 paig 9.
'1325 psig " 10. - '1355 poig " . !

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"0"0 Accordirigito Ts103. -? Secondary '. Containment' Control,?? when. the! ' W e[/g:. 2 radiological:cotGesfor system'that-has been breached ist ' ,? identified Bit'mdst'be isolated unless'the system orJsource cis#requiredjfor;:anyL of-three (3) specific purposes.- ~ WNhg ' 3 ST6TE theDthrae:(3)' purposes for.which the system or source Yj$ g :pouldJNOTtbe=' isolated.
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w, < ,140ESTION- !5;08? ~ (1.00)-
E , .. ... 'd S c J:According-to T-200,-CPrimary. Containment' Venting":' M ,... -- . -.., , WHICH.ONEL(1)"of;the'following. primary containment vent:
paths?ishthe'MOST' preferred?
- 1..." , '
(12.0).
..a. - ... T ( l'J ) ' 2"drywell Lvent' to SBGT : ,. >< ' a'r ' /(2.). l18" torusfvent;to:SBGT ' . , _
- ' ' (, k, -, ' ', -(3(). .2" torusi vent: to SBGT i ,w r, . av ' (4'.),:6"cILRTsline from"torue O ' g.e + < y . , , 'y , , - s %# --- , y v p; i (b'$. . , " >
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la.
' STATE-the reas'en.a manual = scram'18 requireda ~ i(1TO)f e~ - . .., . ... __ - . , _. , M bv cA-plant (shutdown':is required.iffInstrument~ air header; pressure - ' y;'. cannot: be: stabilized:'above 75 psig. ~ STATE:the reasonla;plantL !? _ - x c shutdown is required' "
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,. . . . . - . . . s d SM The! transfer "of tho/;13 XV cystem from!the unit transformer ^ ,, Lto: thec startup' source occura automatically.on a' turbine. c - . ' 'generatorttrip..LAfter a' SCRAM, T-100, " SCRAM,"' instructs the t'
g%.,,!<peratorito manually transfer 13:KV if a turbine' trip.haalnot p]S!D yet occurred 4to gain a significant. major. advantage.. 4ep+> - c - ., >,,s };f*'*JSTATELthe MAJOR advhntageigainedtbyLaccomplishing1the: 13 KV C p f. transfer-manually.1 (1.0); o g:

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, .c, ' ' , , " - , , i4 .. CUR'STIO!E.. .. . ' S.11.L L(2.00) ,

-ic. ; Normal-- food in loot to ': the Unit #3 120. VAC uninterruptable ' ' ~ v.
'. Power supply.
This will result in the nystem automatically . . c , transferring from the: (1.0)~
, (1.). static invertor to E-134-T-B (120,VAC).
. ( 2 )-, E-134-T-B (120'VAC) to static invertor' w . . (3.)
x . E-134-T-D'(120 VAC) to selected RPS motor. generator.
, t ( 4 '. ) : static invertor to selected RPS motor generator J b;- ON-112 contsinn-a cautionistatement to. emphasize how . , -recorders;will fail'during a-loss of power.
WHICH.ONE-(1)? . . statement describeathow recorders will fail? u .(l a 0): t (l'. ) ' upscale _ (2.)
downscale y , ( 3. )' onacale ! ~ (4.)
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. n.W, :i n . . . . , . , %m%, 2 DurihajAlternate Shurtdown Cooling,tIDENTIFY;the:minimumi , d , 2fM N -~ differential: Pressure l allowed'between.thefreactor.and torus.
f ( 0,5 )' e,. .. Q'V {bb : .. M . . , .t .
l - r . _ STATE the reason for th'is min'imum differential pressu'e i H " . 6!,:/ / , requi remen, t..;, , . , $ ' ' e - _ . , - r: ( l 0 ) , , ,
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, ..w CUESTION 5.13 (3'.00)- For each of the_ plant conditions listed in Column'A. LIST ALL - '.of the appropriate' TRIP procedure (s) from. Column B that should ' be entered.. ASSUME the plant is initially at 100% power and consider each plant condition separately.
(Note: The procedures in Column D may be uned more than-once or not at all.
If none are applicable,, STATE lNONE.)
(3.0): , .
- Column A' Answer Column'B (Conditions) l(Procedures) . . . a.. , Reactor' pressure 825W 1.
-RPV Pressure- ' Mode switch.in RUN.
Control, T-101 b.
. Drywell pressure at 2.
Primary 1.6 psig.
Containment' Control, T-102-c.
Torua-leve11at 14.5 feet.
3.
Secondary < Containmenti LControl. T-103-d.
Unit 2 Vent' stack radiation 4.
. Radioactive level in 97,000 CPM.
Release Control.
T-104 o., Reactor water level at ' -\\50 inchea~.. i f.
- Refue1Liloor ventilation
exhaust radiation level of 25'mr/hr,
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L' 'S , ._ , I . L- - '
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. o3 . ,' - ib l~ QUESTION 5.14 =- (3.00): , e +$,.E: l . 4W iGiven=the initiating conditions in Column'A,1 SELECT the appropriate , j[ emergency classification from Column B.
Attachment 2 of EDP-101- , f: is providediforcreference.
(Note: Each classification may be used moreLthan once'orinot at all.
If the initiating condition doen NOT gl; -meetLthe entry level requirements, STATE NONE.)
(3.0) ,.> (Column A- $' Answer Column B.
(Condition) (Classification) - .a.- -An ATWS~ condition exists, l.: Unusual EventJ < Reactor-pourr ia-7% and c e torus temperature ~is1118-2.
Alert . degrees F.-

, 3.
Site Emergency I T).- The reactor h'as' SCRAMMED lI unexpectedly.
Vessel 4.
General Emergency E level in -4811nches'and containment pressure is 1.8 psig.
y
c.
A truckJdelivering chlorine inside the ' ' protected area has - . developed la leak, l \\-

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~ , W ': Peach. Bottom;bnih2iis' operating'at90%' power:withtwot(2) ~ ' 6 g minoperable~ control rodsDisolated at position 36.,iAniair-D

ri ? 41eak results: iris isolation ~ of 'an-additional-control.- rod at : M fpositioni24, STATE whatiactions.are required tol permit conti uedi . w @' ; powerLoperation.. ,, . ..... , . .. - ' ' ' QT . b' , a(NOTEi" Fully reference all; applicable TechnicalLSpecifications: in>yourfanswer.)
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EMEIGNCY AlllL(tilliQhnli,J14BI'.Ju OLUTIGl.S PJga 59 Y U131 ' . - QUdTIO!4 - b. l fi t3.00) ' Column 2 Jiatet primary containment isolation groupn.
Column 1 lictn icolation parametern.
For EACH parameter listed in Column 1, SELECT the group (o) from Column 2 that use THIS parameter to generate an isolation signal.
(NOTE: Each parameter may have 1 ore than one group listed.
If the parameter generates no icolation
igna), STATE HONE, s
COLUMN 1 COLUMN 2 c.
Off Gas Stack Hi Hi Rad 1.
Group I-MSIV and MSL levels drains b.
Reactor Pressure 75 paig.
2.
Group Ila - RWCU c.
Drywell Preneure 1.6 psic, 3.
Group iib - Head Spray and SD cooling d.
Reactor Pronsure C00 psig.
4.
Group IIc - Long path c.
Reactor level 10 -160" recire ' 5.
Group III - DW vent and purge valves 6.
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. QtlCSTION f. 18 (1.00) 1mmediately after boron injection in initiated procedure T-101, "f1PV Power Control," requiren ADS to be inhibited.
WilICH ono (1) ntatement BEST describes the banis for inhibiting ADS at thin time.
(1.0) (n.)
To prevent a loss of boron from the vessel renulting in a reactivity increase.
(b.)
To prevent a rapid injection of cold, unborated water resulting in a rapid increase in power.
(c.)
To prevent void collapse during rapid depreneurization resulting in a reactivity excursion.
(d.)
To prevent an increase in natural circulation resulting in decreased voiding and an increase in power, i \\. , ,. (*4444 END OF CATEGOffY f. 4441*)
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, iQUESTION-G,01 (2.00) The following plant conditions apply to Uniit 2: ' ' Reactor' Power 4 5% - - c
Total core' flow 40%~
' . Loop recirculation: flow 35% , .(two (2) recirc loop ' ' cperation)
" ' l.q-,FRP/MFLPD : l' Reactor _ power'is being 1 CREASED to'75% with control' rod ' manipulation only. ;Using.the APRM flow-biased power formulas.- y.
DETERMINE if this power increase'will result--in a ROD WITHDRAWAL BLOCK, FLOW BIASED NEUTRON. FLU" SCRAM, or NO RESULT.
ASSUME total <, reciro flow' remains constant.
(Show work) '(2.0) ,

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.. a , ~. p ' - k I UkSTION_ _6.02- -(2.:f.0) EQ - k m . " The' reactorfic operating at 90% of rated. core. thermal power with
1
_ y i F
the main, generator..onfline.
The ?A" stator water cooling pump to p ! tagged out,(blocked).- ' ' % c, Q, d.
J. DESCRIBE th'e responso of the following equipment lto.a trip '
, '
of the TB" stator water'cooldng pump :given the transient i _doesDnot~readit.in a' turbine trip or RPS SCRAM. ' INCLUDE W time: delays'and setpointa.
ASSUME-no-operator' action ic-
, -- taken.
' ( 1 ~. 5 ) --; ,,e y > 1:." =EHC System-B.. 2.: ' Reactor ~ Recirculation Pumps
D .
"
b.
DESCRIBE.the two (2)' main. turbine. trips that are enabled '

- on a total.. loss of'ctator cooling water.
INCLUDE time - y delays and:setpoints.
(1.0)1- ,. \\'

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,y,gC1 ; PLANT SYSTEt1S_LME AND I;'IART_WJ.DlLGEEERLCL (Pig $ 24
_ 4. 7 j BESEGEE11GlJIl& Lim: . ' . yr., . : , ,,...,. ;
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t.- g,.7 < . . ;- -' - - ,. + , I . ' . .-(. ' c [1 QUESTION- . 6,03-(3;00) Cobcorning the Reactor: Water. Cleanup System: , , . ,
ia. : During: periods of blowdown to:the main ~ condenser, the...
i.)
1.
heat exchanger (a) will be under minimal load!while .: :; o the' 2, heat exchanger (s) will be under maximum load;. - (1,0)
b')
STATELthefF00R (4)--conditions, INCLUDING setpoints, which ^ 'will cause the RWCULSystem to isolate.
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c ,., , iUkSTION LG.04 '(1 00) - l ' t
Concerning 1 the <: Reactor Protection System: y

',... . e ,
cj-rc RFor each of'the events 1isted below. STATE'whether.the'RPS will-
, ' respond;in: t

, ,

, . 'a, -a full-scram & , _ 'W.
't b.
a;. half ~ scram - C.
no:BCram" 1.. - A if ast - transfer of the-4KV bus servirig ' the RPS. system' ; (0.5).. 3, . } 2. ' TheLRPS Power Supply Selector _ Switch for the "A"-RPS bus; g.
- is..turnied to the alternate power supply position.-
(0,5)-
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() r:. n i loring refuel ing opo ra d oor.. n you r shi f t.. you are in f c rt.:osi thu t!. r.w (,*t ) i nts t romo n t c h t.o r, ; : n for the isofueling F l oo r Ti s d i ri t i t,
cnitorn are inopernble ( f s i l ed c,$s l i bra t.i on ). You are tne St.O on ! tia l<ofueling Floor and want to proceed with fuel movement Ucing Technical Sp< ci fications.- STATE the actions required before fuel movement can continuo.
(NOTE: reference all app)icable Trahnical Specificm. ions in your answer.)
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ti I%lkllEYIJE11D ' 30E AND lliWl_dWlB._fiERElilC Paga 27 , FEEPD$fdittl41TJ1S_ll3X1.

. a QUEETiO11 6.06 (%.00) Concerning the Reactor Feedwater Pump Turbines: a-W}i1Cil 011E (1) of the follow 3 ng statements is correct? (1.0) (1.)
The Motor Speed Changer (MSC) of the feedpump turbine cau regulate turbine speed between 0 RPM and full cpeed.' (2.)
The Motor Speed Changer (MSC) receiven power from the uninterruptable power supply.
(3.)
The Motor Speed Changer (MSC) in tied to the Feedwater Control System via a function generator.
(4.)
The signal from the Motor Speed Changer (MSC) will override the signal from the Motor Gear Unit (MGU) when in manual, b.
WilAT in the purpose of the HYDRAULIC JACK 7 (1.0) g . \\ . . (***M CATEGORY 6 CONTI!10ED ON NEXT PAGE d444*)
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, < .. QUESTION G.07 (2.00) STATE the FOUR (4) conditionn which will auto initinte the Standby Gas Treatment Systera.
INCLUDE actpointa.
(2.0) $ \\ \\ . (***** CATEGol?Y U CONTINUED ON NEXT PAGE *1441)
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., - ,i,,.... .. . =. ..,,.. . - b qy .. , cw .:,, +,n .. - _ ' M During Trefue31ng uith;.the Reactor Mode, Switch.in REFUElban L x' W op6ratorsraisen?the-UNLOADED 5hoints and fue3cgrappleDtoft.ha:_.
' M :-MFULL'-UPaposition.: STATE 7the' INTERLOCK which sould :stop refueling 1 . e %. m ,., WGyDiatform ttrhvel motion <as it ' nears Lthe reactor vessel,7 a..L ( 14 0 )7 9G - .m - . . _s , _.
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'd D.< rg g, - , , ' , , . uw ' : !c4 , . . . ., . ' ~ - . PLANTO SYSTEMf ( *}flif ANii PLANT-WIDE GENERIC-Q: Ci I , 6,, .: eifREeEONSlHlLITIHu Lla n ' - Pcco ' 30': . . . , - .n.
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gir - m , , 7....., ((UEST]DN 0409:
( 1. 50 ):
t j Concerning the Core Spray" System: ' . v+- .. TheN>urpose'oftheLcore.sprayf leak det.ection system in-to - . . ' -o/ nV . detect:alloak'or. break.in core sprayfpiping outside the: ' - ' 1, - ~'and :inside' the 2.
' ' .(1.0) " - .. WHAT'is indicated by~a' NEGATIVE differential pressure of 5 i ' b ~. -
-
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. psid forl core spray toltop'of.: core plate;DP.
ASSUME fulleG . (O'5) Power' operation.
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'4 "e '11EST10H 16L11-
. nw, [' '- Tho ilich.Prensure C6olant: Injection-(HPCI) Pump' receives an ' fautoLinitiation signal.
The-Auxiliary Lube Oil: Pump fails to atart.
~ m' ., 1 DESCRIBE lthe-failure's effect on the. turbine STOP~ ~ - f,. - l4: . . . - Evalves and' CONTROL, valves.
.., '(1.0). > , ., - ,,. (' b.. <Using!TechnicaliSpecifications ' IDENTIFY your.
. ' , required actions.'- -(Rote: Fully reference.
' h.' .,all applicable'. Technical Specificationsiin'yourL - M ' - answer.)-

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' n-Core Probo2(TIP) n $DJ 4ecomes' etuck: in;the.1. core when the c TIP machine : drive; motor MatIs.. ~ ' . M .LI WaccordanceEwith Technical:Specificationsi'. STATE your required ..... . , 4.:tW; i etions n' ; (NOTE:: ! Fully J reference : a11 < applicableTTechi Specs. ).. . ((2.O M ' . e ;1 < ya.3 . - < - > g

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in e, quipped with .3 nitroen accumu];stor-n i.ed to pei r f o rm.s m i n $ n.u n, <,f (1) olm r:4 t i on ( s ) or hold the vta lvc-open for (2) _ hou r( s ). Electrical control power to itetuate 1.he ADS visiven comes frc.m (3) i (1.5 . b.
Once ADS has con,menced blowdown, IDEt!TIFY three (3) I meanc to recione the ADS relief valve.c (1.5) t E I i, l . H i44i+. cATw;ni<y
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, - . 20:l' eft 10N 6.39-( 3. 00 ) According to A-31 " Notification of the NRC:" a.
WilICil ONE' (1) of the following conditiona requires a ONE hour notification. to the NRC por 10CFR50.72? (1.0).
, (1.)
An internally contaminated individual was transported to an offuite medical facility for treatment.
(2,) At full power an electrical fire occurred on the fuel bridge'and was extinguished.
(3.)
The RWCU~ayctom isolated on high ayatem flow.
~ (4.)
At full power a low preasure ECCS pump spuriously-started.
There was no actual injection, b.
After notifying the NRC of un UNUSUAb EVENT, STATE FOUR (4) of the six (6) conditions which require the Emergency Director to make an IMMEDIATE follou-up notification to the NRC.
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.Pl fdQ' SYSTEMf. Ll;10%) AtJJLL'L&NT-W1J)E CElill.lG Pcce.;h _.
.. ItEECD11FJJllhIT1 ES ( 1]iM ! -.: , , .. s,- fQUkST10N G.22-(2.00) .The Trip Procedures _ identify when the Emergency Director in REQUIRED to-activate cach'of the Emergency Recponce Organizations.
For each organization licted in Column A
CHOOSE-the lowest classification in Column B during which activation in REQUIRED.
(2.0) Column A
Answer Column B ... a.
Emergency Operations 1.
Unusual Event ' Facility (EOF) b.
Headquarters' Emergency 2.
Alert n Support Center'(HESC) c.
Operation Support Center 3.
Site Emergency ~ (OSC) d.
Technical Support Center 4.
General _ (TSC)- Emergency.
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GENERAL CONDITIONS NOTE l
This table'is-to be used as a guide for " big picture" emergency l classification assessment.
I IF conditions listed-are met 'I 53Q specific EALs of other tables do not address current emergency conditions.1 THEN classify using this table.
I-1
i . . l UNUSUAL 1) Situation threatens normal level of plant safety. No releases of radioactive material l l EVENT of8-site are expected.
' ll l l ALERT 1) Situation does QR could represent a substantial degradation in the level of plant safety I i ! I o_n I, _ 2) Conditions **tst that warrant precautionary activation of Technical Support Centec - l ANQ plating near-site Emergency Operations Factitty AND other key emergency I.
personsg1 en standby.
I na 3) Release of radioactive material warrants off-site rescense QR monitoring, out does not reoutre protective actions.
! SITE 1) The level of safety has QR could be degraded to the point of losing a plant function needed to l EMERGENCY protect the publiC
2) Conditions exist that warrants f I a.
Activation of EOF AND off-site emergency facilities l AND l b.
Activation of off-site monitoring teams I.
' OR Protective measures recommendations to public near the site OR l 3) A significant release of radioactive material has ocebrred QR could take place.
GENERAL 1) Substantial core damage l AND loss of. OR hign potential for. toss of primary' containment l ' EMERGENCY SE . 12) Conditions entst that warrant'all on-site and off-site emergency facilities being activated to I ~l aid'in implementation of protective actions.
OR \\ l ~~ l . 3) Large amounts of radioactive material have been OR could be released in a short period of time l
i OR
-- j . . . 14) Protective actions recommendations for off-site areas are made by.PBAPS ..r' -

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. - - . _ - ATT;CHMENT 2 ' EMERGENCY CLASS 1FICAT10N TrrtE . *, j (Page 5 of 15) . g c.
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RADIOACTIVE RELEASE _ .. I i
- SPECS.
l UNUSUAL l INSTANTANEOUS RELEASE EXCEEDING TECH.
EVENT .1 1) Licuid effluent release exceeding Tech.. Spec. 3.8.B.1
OR l L o2) Gaseous effluwnt release emceeding Tech. Spec. 3.8.C.1 detected by any of'the'follo=Ing: I ~ a.
From one release pointe l 1. Main stack spike greater then 1.8E04 cps on RR-0-17-051 I i OR l - 2. Ra~ Bldg vent spike greater than 3E05 com on RR-2979 or 3979 l D.
Release from more than one release points l 1 Main stack spike greater than 6E03 cps on AR-0-17-051
OR I 2. Ra~ Bldg vent spike greater than 1E05 cpm on RR-2979 or 3979
1 l
ALERT ACTUAL OR POTENTIAL RELEASE 0.01 REM WHOLE BODY OR O 05 REM THVROID l l 1) Uncontrollable release for more than 20 minutes from teen
a. Main stack vent greater than 2E08 cos on-RR-7127 CR o. Rm BI3g vent greater than 3.4E06 cpm on RR-2979 or 3979 OR 2) Continued particulate or iodine release such that analysis.cf particulate filter OR charcoat cartridge results in the following estimated release rates: a.
Main stack greater then 1.56E04 uC1/sec I OE
D.
Rs B1dg vent greater than 5.36E02 uC1/sec OR 13) Radiation levels OR airborne contamination increase by a factor of 1000 using direct radiation readings j within the facility.
SITE i ACTUAL OR POTENTIAL RELEASE 0.1 REM WHOLE BODY OR 0.5 REM THvROID EMERGENCY l1) Uncontrollable release for more than 20 minutes measured on RR-7127 from thes a. Main stack greater than 2EO9 cos OR b.
As BI3g vent greater than 8.75E08 cpm CR 2) Continue 3 particulate OR todine release such that-analysis of particulate filter OR charcoal cartridge results in the following estimated release rates: a.
Main stack greater than 1.56E05 uC1/see l Og l e.
Rm Bido vent greater than 5.36E03 uCl/sec.
l GENERAL. ACTUAL OR POTENTIAL RELEASE 1.0 REM WHOLE BODY OR 5.0 REM THVWOID l' EuERGENCY 1) Uncontrollable release for more than 20 minutes measured on RR-7127 from the:
a.
Main stack greater than 2E10 cos l OE l-b.
Rs Bldg vent Dreater than 8.75E09 cpm i OE l 2) Continued particulate OR iodine release at estimated rates based un analysis of particulate ll l filter OR charcoal cartridge with: , l a.
Main stack greater than 1.56E06 uC1/sec ' I i OR j
c. As Bido vent greater than 5.36E04 uCi/see
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SEVERE NATURAL PHENOMENA l UNUSUAL 1) Any earthquake felt in plant OR detected on station seismic instrumentation l' EVENT l SE I I , l 2) Any tornado QR hurricane (75 mph or greater) on site I 'j l i-OR I l 3) Conowingo pond level on LI-2/3270A.B.C greater than 113 feet SE 4) Conowingo Pond level on LI-2/3278A.B.C less then 98.5 feet without prior notification by L.D.
I s ALERT 1) OPERATING BASIS EARTHOUAME EXCEEDED alarm annunciates and felt in plant SE 2) Conowingo Pond levet on LI-2/3278A.B.C greater than 115 feet SE i3) Confirmation of an uncontrotted loss of pond elevation
93 4) A tornado strikes the Power Block with' identifiable plant damage I i oR i ! -~ ' .l.
. . . i5) Hurricane winos (75 mph or greater) strike the Power Block with identifiable plant damage-LSITE 1) Greater than maximo, credible earthquake as detected on seismic instruments-(0.129) as'per I EMERGENCY SE-5 EARTHOUAME precedure SE 2) Conowingo Pond level on LI-2/3278A.B.C greater than 116 feet

QR less than 87 feet ' GENERAL lEMERGENCY N/A
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SECONDARY CONTAINMENT' INTEGRITY- ' -..-.
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., l l l _: - Unusual :I l- 'i ' EVENT I . 1)' -Loss of. secondary Containment integrity for. greater than 12 hours when Secondary Con t a lfwent. l' '~' is required by. Tech Specs ~ ' -l -; I I ALERT l .
N/A . i l I i SITE EMERGENCY; - l N/A g E . GENERAL EMERGENCVl N/A
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FUEL DAMAGE UNU$UAL 1) Air ejector.' disCtarge rad monitor high alarm AND an increase of 500 mR/hr'witnin 30 minutes EVENT QR a' level of-2.5E03'mR/hr indicated on RR-2/3-17-152.
EE ' 2) High reactor coolant activity determined by sample analysis equal to or greater than 4 uC1/gm dose equivalent I-131
1 ALERT 1) Air ejector discharge red monitor greater than 2.5E04 mR/hr on RR-2/3-17-152
9E H2) High coolant activity of 300 uC1/gm dose equivalent 1-131-AND main steam line hi-hl rad alarm with resultent scram alarm [ SE 3) Spent fue: damage resulting in a refueling floor ARM alarm QR a high rad alarm on refuel floor exhaust rad monitor l - I l CR
4) 2 of the 4 containment rad monitor levels' greater than 4E02 R/hr on RI-8/9103A/C AND RI-8/9103S/D SITE 1) 2 of the 4 Containment red monitor levels greater than 4E03 R/hr on R1-8/9103A/C - EMERGENCY AND RI-8/91038/D QE I I 2) Major damage to spent fuel in fuel pool OR uncovering of spent fuel as confirmed oy 2 fuel pool ARM alarm AND EITHER a.
Refuel floor exhaust rad monitor high alarm OR Refuel Floor ARM a l a rms l 9E I l b.
Observed major camage to spent fuel levels 'reater than 4E04 A/hr on RI-8/9103A/C . GENERAL 1) 2 of 4 containment rao monitor g lEMERGEtJCY i ! -AND RI 8/9103B/D ! I AlLD I l l Containment pressure exceeds 10 psig on PR-2/3508 I l l l
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, . - . -., - ....a.T.
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a
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$'C . T"
hw

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. . ,,',,,.[p.
% .4* , .g'- "'* p' ,i.,S ' , . _ ~ , .x - "' Y ^F W + + .. -. .;

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_ -
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~~- - - _ . _ -6 y~~

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'-
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"
d _'.. y . . . 'L.,.-y_ _. ;~ , :.g . w _.y- ,, ,. - w ,- _ _%,.e , - ,-.~4 , ,v.
v-.,# -, 'p.y"' m.
A2.,, _ - d.
,,es.
, ,, 7a.
.,Q

~~- g.,.: %,.- 29.,, _,. . .~~

~~' ' ~ - . . ,....,. . ,, C ' ,% , f~~

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~~'x 5% ~~~

~~I ^~~
~~.g,m f,+l ,. ,.. n* .d,., -,,. ~.,,. _,,,e~~

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, ,.,..e -:' 1*.,.r', '. a t 1:: - . 'r.
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M
+ 4-. , ,..e .s.._ 7.~*, _ g,..',,%._,.,,m, ,,. _. , ,,,m._.., , ,_
- -.y ~.,...- # ,.. _,_ ...,.y,,,...,.M.'..',l'J[_%.,m.,.a.
. e.%,.,9 . m r ,.u..na,",,,,r.,...,.;. $ ,,,,,, ,, T %.;- ,,,.y,f,,.[,.l,.",.%,y,e _,r-,e - w.e , 75.i.
,,,,,, y, .r t... ,..y n.
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. m y., n.,._.
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~~=s.~~
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.
, '4ME RGENCY CL^551FICtT10N TABLE - -P- , d . CTTLCHMENT 2- _.
. .(Page 15 of.15) .. -..,.... '

- _ 15.
PLANT SYSTEMS /EOUTPMENT CPERATIONS FAILURE' '] '

l l .. . 'l l IUNU$UAL 1) ECC$ initiated due'to a valid signal AND injecting into vessel (Core Spray, RHR. or HPCI).
' EVENT ' .l " on 1 -. I J-2) Reactor Coolant System leak rate greater than the limits-listed below as re au ho:' cy I l Tech Specs 3.6.C.1: I a.
Unidentified Leakage - increase of 2 som in a 24 tsour period i OR l ~ ~- I 'l - 5 gom I i i i ! M I b.
Total Leakage - 25 gpm averaged over any 24 hour period M 3) Stuck open SRV OR Safety Valve _ l E I 4) Turbine rotating component failure causing rapid plant shutcown.
.I ALERT 1) Reactor Coolant System leak rate greater than 50 gem l
1
2) Cold shutoown unattainable
1 3) Failure of reactor protection system to initiate E cong>1ete a scram (ATwS) M 4) Turbine failure causing casing penetration.
I'l' i
l SITE 1) Not shutdown unattainable ! EMERGENCY E 2) Fatture to complete a scram-(#TwS) . g Reactor is not shutcown I g Torus temperature above.110 degrees F requiring initiation of SLC as per T-101 GENERAL i EMERGENCY l N/A I I -[ w.. __ _ , w--.,-._.._, - . - ~m-smam mu m -- - n.mm _ - m4
' . SMERGENCY ' At1D ABNORMAL-PIANT' EV01sDTIONS-
2 ' 1Pe ~;;; 4 4 , f.1131.1.

PV , ,
, .. %? ' .- ' i;83 ' . i 'i
~~ANSWER 5.01~~

~~(1.50). By at leant two ' indications [40.5] that'either: - 1 )f misoperation in the automatic mode is confirmed [+0.5] d t2) adequate core. cooling in' assured (40.5] ., REFERENCE~~

1.
Peach Bottom: LOT:1560, pp. 8 and 9, 2.
Peach Bottom: L'. 0, 7.
3 ', TRIP Procedures, Note 20 Bases, P. 19, 295031A204 295031A101 ..(KA's).
s, ANSWER 15.02-(1.50) 0.. 1.
APRM oscillations greater than 10% peak to peak.
[+0.5] 2.
Periodic LPRM upscale or LPRM downscale alarms.
[40,5) b.- Manually SCRAM (and enter T-100).
[+0.5] REFERENCEp
~~1'..~~
Peach Bottom: LOT-1540,.p.
3, L.O. 2.
~ 2.
Peach Bottom: OT-112, p.
1, Basia 295001K206 ..(KA's) . ANSWER 5.03 (2.00) . I 1.
Could result in an excessive off-gas release rate (since the' holdup pipe.wi.11 be bypassed).
(+1.0] 2.
'Significant amounts of hydrogen and oxygen are present [+0.5) in the main condenser which could result-in a detonable concentration [40.5] (at atmospheric pressure in the pump or its associated water separator).
[ ' !
' .(4**** CATEGORY 5 CONTINUED ON NEXT PAGE
3)
! ,s
_. -., - [[ ' Q.
-n 4 , . EMERGENCY"AND'ABNORMALLPLANT EVOLFTIONS
~~Pego 45-~~
~~' ' g' -J,1.33%) , q ji o .- If REFERENCE I N b.~~
~~Peach-Bhttom:~~
LOT-1540, L.O 5.
] . '2; Peach Bottom: 0T-106, p.
Basis.
a > ,-- < t '* 295002K20'7: 2950020007 ..(KA's) t i L ~ , e I ANSWER 5.04-(1s00)- '" m ~ ( bi. ) ! [+1.0]. o - < b . REFERENCE ' .1. ; Peach Bottom: LOT-1560, L;0. 6.
$ g 2.
Peach ~ Bottom: T-102, p.
16, Basis.
.' r

i 295010K305 295028G007 295028A102 295028K204- ..(KA's).
' L
~~ANSWER 5.05 (2,50)~~
c.
1.
runback recire flow to minimum - 2, transfer house loads

-3, manually scram and execute T-100 4t place _the drywell' instrument air in service . 5.' close.MSIVa- -o 6.' establish torus cooling-7.
obtain master keys 8.
~open the. emergency-shutdown panel.
, Any~six.(6)-[+0.25] each- , <b.
Transfers indication [+0.5] from the control room to the Emergency _ Shutoown Panel indicators [+0.5]. -? ' REFERENCE-1.
Peach Bottom: LOT _1555, L.O.
3, 4.
12.
Peach Bottom: SE-1, " Plant' Shutdown from the Emergency ' Shutdown Panel," pp.
1-3, Basis.
[ '295016A201-295016G010 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) i rN-M ;$ 970 ' i
gwj.. ,r: -r Ns " ' ',,f.
."EliE]IGENCYLAND AHtLQFEAL PLANT EVOLUTIONS ~ - PegsL46- 'f33%)' f .,-.z o-ll[ i m " y fr -..

., - b .. . . ' t TANSWER .5.06l (1.50)-- p,. TI ' n a.
5-b.
- -3 ' lc -
t.
2d.
, 7:1.
k- ,-f,

.-
o s 1: [+0.25].cach.
' ' REFERENCE
,
F;/ 1.
PeachiBottom: OT-102, " Reactor Hi Pressure," Basis.
j' '2.
Peach Bottom: -LOT-120', pp. 7 and 11, L.O.
12.
'3. L.'1 . Peach Bottom: LOT-0050, p.
18, L.O. 5.
,.. (i ic 295025K205-295025A103 ..(KA's) > , LN'NSWER.
5,07 (1.50) 1.
Assure adequate core cooling.
[+0.5) ! < ,, i' .2.
Sb,utdown1the reactor.
[+0.5) <-3,- Suppress aLfire.
[+0.5] r P I b REFERENCEL 'l O .- 'm' '
1.
Peach' Bottom: LOT-1560, L.O. 3 and 6.
u J ti.. Peach Bottom: T-103, " Secondary Containment Control," pp. 12 i ' ' and:13, Basis.
J-1 U-i l295036A201 ..(KA's) 'l Y' ,

^0 U - n ANSWER 5.08 . (1.00) ' } < (3.)
[+1.0] ! o.. ,i ) . (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) J i II't . . _
peet c - - F' ,f 5.
~~EMERGENCY ~AND ABNORMAL PLANT EVOLUTIONS Pcs3147_~~
~~g, n-r,;:, L l E L L ' p:J w E' REFERENCE < .~~
'
' P 1 '. Peach' Bottom: LOT-1560, pp. 22-and 23, L.O.
1.
[ 2.
Peach Bottom: T-200, pp. 4 and 5, Basin.
p " 295010A101- ..(KA's) . ., iv*ll h 1 = ANSWER; 5.09 (2.00) c.
(Th'e scram air header is supplied by instrument air.
y Decreasing pressure will result in scram. inlet and outlet valves and' random' rod insertion.)
SCRAM-to avo a random a.c a m i, ~ e.
. AI. e rff rect,^ re c */'* 4 : ~UR A dtdf rod pattern.dg[+1. 0]a.s esa ns unewn &k hMMh~ w i%k infi s<X din. m.
" b,
~~Reactor building' ventilation dampers have. failed closed [+0.5]~~
~~t and will result in elevated main steamline tunnel y ~ temperatures [+0.25] and a Group 1 isolation-[+0.25]. ,~~

R V ' , L-1 REFERENCE r w . 1.
Peach Bottomi LOT-1550,'L.O.
2.
2.
Peach Bottom: OH-119, " Loss of Instrument Air," pp. 1 and 5, Basis.
295019K201 295019G007 295019A202 295019K208 ..(KA's).
k n, \\ . ANSWER 5.10 (1.00) Prevents the automatic tripping of the recirculation pumps which-cccompanies an auto transfer.
[+1.0] (This in' turn prevents ctatification within the vessel by promoting good mixing.)
REFERENCE.
'1.
Peach Bottom: T-100 Bases, p.
2.
'2.
Peach Bottom: LOT-1560, L.O.
3.
295006A104 ..(KA's) . (444** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
n . . '
c
-. v . fi,J 5..l> EMERGENCY AND' ABNGRMAL PLANT-EVOLUTIONS Pago 48i ' 'c,jj-(33%)- , ri:M, '
l d

+ y .. e ' ANSWER 5.11 (2.00)- ra,. (1;) [41.0) .,,W b.
(3.') -[+1.-0) REFERENCE , 1.
Peach Bottom: LOT-0050, p.
8, L.O.
2.
c 2,- Peach: Bottom <.ON-112 " Loss of Uninterruptable.A.C. Power," p.
1.
w.. w . 295003G005 ..(KA's) ANSWER 5.12 (1.50) c.
[+0.5]. .m.
. b.- Less'than 50 paid is insufficient prespure to open)the SRVs.
[+1,0] Ale. ace ry + -lo adep <-{ 4 eree e <.eltf. ars v e.
> REFERENCE 1.
Peach Bottom: LOT-'1560, L.O.
4.
. l 2.
. Peach Bottom: T-115, " Alternate Shutdown Cooling," p.
2, Basis.
' , \\,- 295021A104 ..(KA's) { q ANSWER / 5,13 (3.00) l a.
d.
b-b.
None e.
l c.
12 d.
f. 3 i REFERENCE 1. - Peach Bottom: Trip Procedures 101, 102, 103, and 104.
L 2.
Peach Bottom: LOT-1560, pp.
9, 13, 14, and'16, L.O.
2.
295031G011 295030G011 295024G011 295034G011 ..(KA's) i .(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ' . . d
ff' w ~ ' ' , , N.li [5.
EMERGEtiCY ' AND AlltiQRMAL PLANT ' EVOLUTU!11E,' Pcg3-: 49 j( n 7,.qmn p - C j *- . F> h'. ~ LANSWER~ 5.14 (3.00) , c '- - .3' i b..
2' - c.
2' n, .' ['+ 1. 0 ]. ea ch t 3. w \\ ' f ' . hREFERENCE ";
1.
Peach Bottom: EPP-0020.
d 2.
-Peach Bottom: ERP-101.
B '295023G011 295006G011 295037G011 295017G011 ..(KA's) i.
t ' l? t ' ' ANSWER 5.15-(3.00) Adequate' shutdown margin' verified [+0.5], Tech Spec 3.3.A.1 [+0.5]. -, .All partially-or fully withdrawn operable control rods shall-be c axercised-one notch [+0.25] every 24 houra [+0,25], Tech Spee?4.3.A'2.a. [+0.5]. No more than one control rod in any . g_ -5;x-5-array may be-inoperable [+0.5], Tech Spec-3.3.A.2.f ' [+0.5]. \\ REFERENCE ' 1.
Peach Bottom: Technical Specifications 3.3.A.1, -4.3..A.2.a.
and 3.3.A.2.f.
295019K201.
..(KA's) . ~ ANSWER-5.16 (3.00) l o. 5 b. 3.and-6- ' c.
NONE sd.
4- .e.
(0.5 each) . (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) -
F W;,' I" _ $. %+7,,,7' = j ' Ge + #....AND' ABNORMAL PLANT' EVOLUTIONS t-
/
~~f:PagaL50T ' m J ' ' '~~

~~.,. . - , .u ,~~

~~jf!?' ji 8C ' LEMERGENCY# .. . . " ' , . f nL,gp;123%F " ' ' ' m fdw : - - - c , , , e~~
p
..: n , ' , . pq%,. r g cA 2 -- w ' 3 ; .- . ..,
, y::1 NJREFERENCE' ..
n,
' cm, . r
P,: ._E.
, _ , . fPeachI:Bott'om: (LOT-0180,.p. 8-11 % / ild M ~; (2!. Peach -TBo'ttom : LO-2 - y=', , dei J223001'K403I . f(KA's); hl: ' ' ' , g?_^ _.
' >sm.
, - e.* ANSWER .5./17? (1.00)- + ' ^ > g;, , ' , ,, _. ( f ~-' g#tO10'.5 " fee'tL torusiIevel, incomplete steam condensation. [or lor $%vs8"'c s*f"' ' - Q, results. [+0i S]( due - to downcomera ' uncovering-- [ +0'. 5],:(in ~,the" . e cventtof a primary.= system bre.ak), w ,- -._ c;
L RREFERENCE- >

IN.s 1.. LPeachiBottom: T-102, " Primary Containment. Control," p.-8,- l '". Basis.
c; " 2.
-PeachLBottom: SLOT-1560, L.O.
3.
g ', . ' g , 294001A116 !295030K301 ~ 295030K207 ..(KA's) Y idNSWER' 5f18 .( ll 00).
' "(bE)- [[$1. 0']: ~ - , , h, REFERENCE
. 1. ; 1Peachl. Bottom: LOT-1560, L.O. 3.
K2.
. -Peach = Bottom: T-101, "RPV Power Control," pi.13; Banis.
1294001A116-295031G007.
'295031K103 ..' (K A 's) : .e , , , - s
i ' ' I , ,
~~.ic :~~
' ' ,
7 (***** END OF CATEGORY 5 *****) < l t l'.' .N~ y ?

~~s_.~~
~~. i~~
~~..,~~
\\;! ' Y, ,. ] ! -- s ),k :. h -. .?, 1' t g y ,
~~sr_r -~~
~~cw - , >~~
~~61 [ PLANT S'YSTEMS~ (30%) ~ AND PLANT-WIDE GENERLt;~~
'~ ~ Page bi- ' _,:y RESPONSIBILITIES (13%) , ['1 '4 . - , , b' ' ANSWER 6.' 01 : (2.00)- Rod Block = 0.58W 4-'50% [40.2G] .. ' M = 0.58(35) + 50 = 70.3% [40.5] (+/- 1%) - Scram = 0.58W-+ 62% [+0.25] . = 'O.58(35) + 62% = 82.3% [40.5] (+/ 1%) would result in a Rod Withdrawal-Block [40.5] t ' REFERENCE I 1.
Peach' Bottom: LOT-270; pp,lLO and 11, L.O.
2.
' -.- '215005A104 ..(KA's); i ' l ANSWER 16.~ 02 (2.50).
p;) (,r 7724 a-/8)) - 'f o **/ , . a-1.
The EHC load' set'will run back [+0.25] to,25% [+0.25] ' t.
2.
Both' recirculation pumps will trip [+0.5]. Pump "A"

in-one.secondi[+0.25] and Pump "B" in ten (10) seconds- [+0.25]. \\ . ' bJ StatorDamps. greater'than 26,530 [+0.25] in two (2) minutes I [+0.25]- , -StatorLamps greater-than 7,726 [+0.25] in 3.5 minutes [+0.25] , REFERENCE ' '1.
Peach Bottom: LOT-630, p.
14, L.0, 5 and 6.
2.
Peach Bottom: OT-113.
-t t 241000K406 241000K125 241000K123 202001K407 ..(KA's) . . (***** CATEGORY G CONTINUED ON NEXT PAGE * * * * * ) ^ +2--
gpsw ,% . , ' . _ _ - - _ _ _. _ -. , y M Sg... 9; - .$1 y

-i pj Q.PLANTbSYSTEMS-(30%i AND PLANT-HIDE GENERIC - ~x.ee a-jDESPONSIDILIT1ES ( 13%d.
_ 'Pcgo 52 ~ jpJW -. f - %9h] ~: c ! g. ',',_ , ,i- , g-- - . 6m . , a? ..,~ "., '. ANSWER.
. 6.03-i(3.00)-

~~. . w< .~~

~~fg Ja,~~
1.
regenerative. (+0.5]~ .j u' 2.
non-recenerative- [40.5] .-

i c r>b, E b.- 1 :.' low reactor water level [+0'.25), O [+0.25]: . .! ' I 2.. high-temperature on outlet.of non-regen'Hx [+0.25), 200.' - h[l5: ! degrees F- [+0.25]'. . I 3.
Standby Liquid Control-System [+0.25).. initiation (+0.'25] ! +t 4; RWCU suction line high flow-[+0~.25], 300%'[+0.253-p .u , [ Nl REFER 5NCE' \\ L1,: Peach Bottom: LOT-110, pp. 7 and;10, L.O.
3, 9B,-~and SC.
,,gn is + t

~~R 204000K504 20'4000K404 ..(KA's) h t , > ni~~

hn! ANSWER 6.04-(l.00)
,1.
c-

~~7 '~~
2.
b' - ! ,.

~~i " 7[+0'.5]'each ! < _(. , .~~

- W . - . REFERENCE , f '.1; Peach Bottom: LOT-300, pp: 8'and 9. L.O.
4, 5,.and 6.
[ k '- , p0

n, 212000A101 212000K601-212000K403 ..(KA's) - k,n A- , F ,.JANSWER 6.05.
(1.50) e - - .. - l.IsolatejSec'ondary Containment-[+0.5] and start SBGTS [+0.5]. , .
~~j71 1 Technical; Specification Table 3.2.D. action B [+0.5].~~
- n < %ge ' _O i p,; .; - _.
q; - i r : (*****: CATEGORY 6 CONTINUED ON NEXT PAGE *****)
$ {} -b, .. '1[d f

~~.. r[.TLANTSYSTFMS(30%) AND' PlaANT-_ WIDE GENEBE P::g153~~
~~." d '. c6 EE5f01131RILITIES ( QU.~~
ew p.g.t:. . ? REFERENCE .; s . + Ii; Peach Bottom: LOT-760, L.O.
8.
... t; 2.
Peach Bottom: Technical Specification 3.2.D.
( y.
V P L272000G010 ..(KA*c) r

Lj k '; n ANSWER.
6.06 (24.00) , r s's ,c. ( 1. ) ' ~ [+1.0] .e h b.
Removes the MGU control feature (to allow control at higher RPM.with the MSC).
[+1.0] ' iL ',

> REFERENCE ' ' 1.
Peach Bottom: LOT-550,.pp. 9, 10, 17,'and 18, L.O. 2, 3, and 8.- ' . d 259001K105 ..(KA's)- , r' ANSWER 6.07 '? 30) l'. Spactor.w Le evel [+0.25] 0" [+0.25] 2.- drywell pra e [+0.25] 2 paig [+0.25] , >f . 3.
reactor-bu14aing. exhaust [+0.25] 16 mr/hr [+0.25]- " 4.
refuel floor exhaust [+0.25] 16 mr/hr [+0.25] , ( ' [+0.5]-each x.
iv > REFERENCE' 'L L o's 1.
Peach Bottom: LOT-210, p.
6, L.O.
2.
w L b 261000K401 ..(KA's) ,
i
~~, ' ^, < ANSWER 6.08 (1.00) more than one control rod withdrawn [+1.0] ' , (***** CATEGORY G CONTINUED ON NEXT PAGE *****) s~~
~~\\.~~
n... .; .... - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - g . . , L C.
. PLANT SYSTEMS (30%F AND Pl. ART-WIDE GENERIC Pcco 54 o ,4 - . g EEEEQ14S1BILITIES ()3X).

. , NEFERENCE , 1.
Peach Bottom: LOT-7GO, p.
38.
2.
Peach Bottom: L.O. 2.
' ,, 234000A302 234000K401 ..(KA's) ANSWER 6.09 (1150) i e.
1.
chrcud [+0.5) 2.
RPV wall [+0.5] , b.
Core spray piping is intact, normal reading.
[+0.5] RE7KRENCE 1.
Peach Bottom: LOT-350, pp. 9 and 10, L.O. 6.
209001A306 209001K404 ..(KA*n) ' ANSWER 6.10 (3.00) 1.
fhesh air supply fans trip .2.
A/C supply fans trip 3.
return air fans trip 4.
dampero to the high efficiency filter open F 5.
.the selected Emergency Supply Fan starte 6.
the Control Room office cooling unit tripc.
7.
the cample point for the rad monitoring system switches to the emergency supply fan discharge .Any six (6) [+0.5) each REFERENCE 1.
Peach Bottom: LOT-450, pp. 9 and 10. L.O. 2.
288000A301 288000K402 288000K105 ..(KA's) . (*****- CATEGORY 6 CONTINUED ON NEXT PAGE * * * * *)
, g-I >

., ,4 [hkfj.
bANT SYSTidS~ f 30irl._ANILfLANT-WIDE GE}1ERIC Paga 55 ' < k* _i* J.REff0NSIBILITIES_L13X1 - , u 3 -; , i V '.. ' D l.Oc un ~ 4k

' n n t!. ANSWER 6.11 (2.50) ' [ do.
.The valves fail'to open. (1.0) ' ( bi. ; . Operation allowed.ior seven (7) days provided successful '
.
testing of RCIC, LPCI, core sprays and ADS immediately AND y tl' RCIC and ADS daily'thereafter (+1.0).
Technical Specification 3.5.C.-(+0.5)s M.# 3 1 1 REFERENCE e lv 11.
Peach Bottom: LOT-340, pp. 7 and 18, LO. 100, 10E, and 15.
O 206000G005 206000K414 ..(KA's) ' sH b> p , .. .. L lANSWER 6.12-(2.00) !t C.14-# I ' Close1the ball valve (+0.5) or be in Hot Shutdown.[40.5) in 24 hours t [+0.5).
Technical Specification 3.7.D [+0.5) m .Vi ' REFERENCE ~ , ,, LJ 1.. Phach Bottom: 'Ecx inical -Specification 3. 7 - D.
' Ppach Bottom: Ta?-180,'p. 9, L.O. 7 and 8.
,. 2.
' . W 3.
Peach Bottom: LOY-290, p.
6, L.O. 3.
G-> f 71; 223002G005 ...(KA's).
'
' , b
, y R.
, ,
~~'V'~~
~~F)y a: l' ,~~

,.
.. ' --. \\; ' . Q p.i [? (***** CATEGORY 6' CONTINUED ON NEXT PAGE
~~.:t)~~
' E'
1 . , _ ~- k l. _
3 yx _;,., - , . -

! ~_ 'm' i' ^,) t >
,-. -. '. - _ _ . .
s
~~o..6i'. PLANT _SYSTElifu[1Q%)._ MJ_ELANT-W1DE GERERIC:~~
~~Pcga 50- . '~~

PASPONSIB] LIIILLLI.3Al - ' ,ff[.. s , > * a: ' , . , - s, ' , ,._' ANSWER-6.33-(3.00) 'E
c.
' 1.
fivo (S)- - ' > t - o 2.- one-ha3f-3.
unit-batterien ' -
[40 53_.each ., w t _' b.
1.
' Depress both.the "A" and "B" timer reset pushbuttons to
. break"the_ceal in.
[40.53 j _ 2, Shutdown the _ RHR and core spr'ay pumps.. '(4 0.5] ' ' . .. . > - < 3.
Place the "A" ande"B" keylock switches in " Inhibit."
' [40.5) ! .m 4.. Allow reactor pressure to decay.below 50 poig.
i ' - [0.5).
-F-(Any three'e 0.5.each) t .!
' REFERENCE ' .. i 1.. Peach Bottom: LOT-330, pp. 13 and 14, L.O. SB.
l . ~ 23900 K201' 218000G007_ 218000K606 218000K201 ..(KA's) - >

), ' ANSWER 6.14 .(2.00) i ' -l _ _
< 'c.. - ( 1. )- -[+1.0) i ?i , ' ! b.7 1.- acoustical monitoring (4 0.5) _ ii-2' indicates power applied to solenoids (40.5) .
& REFERENCE' ! 1.. Peach. Bottom:' LOT-320, p.
L.O. 6.
, 2.- Peach Bottom: LOT-330, p. 9. L.O. 60.
q'

~~239002A407 239002A308 239002K405~~
~~..(KA'c) , . -.{ i .) . (***** CATEGORY G CONTINUED ON NEXT PAGE $4441) i i .$ , ,~~
l
f 6; e U .. . ., t +LANT SYSTEM U J r h {D: PLANT-WIEE CENERIC Pagl 57 v-cRESPONSIDILITI E_,L1,311 < i . si.
I c.
. - ANSWER 6.15 (1.50) r; .' a.
less than 25% (40.1) reactor feedwater flow (40.1) OR [40.1) ' ' . less than 25% [+0.1)' reactor steam flow [40.1) ' .b.' less than 21% [0.25). power (40.25] (as measured by main turbine first stage'shell pressure)

+ 'o, greater than 30% [0.25) power'[+0.25] (as measured by APRM)-
c ' REFERENCE N 1.- -Peach Bottom: LOT-90, p.
5, L.O. 4.
2.
Peach Bottom:. LOT-100, p.
15,.L.O. 3.
3.- -Peach. Bottom: LOT-280, p. 4. L.O. 5.
[ '
~~215002K403 201006K404 201004K404~~
..(KA's) , h i; ANSWER 6.10 (1.00)- I (d,) [+1'.0]' \\ JREFERENCE.
, q, 1.
Peach Bottom: LOT-280, p.
4, L.O.
1.
215002G006 ..(KA's)
s 19i-s, f

-ANSWER-6.17.
(1.50) .1.
' Movement of material greater than 100 mr/hr on contact.
E';. -2.
Work in airborne, contaminated, or high radiation areas.
3.- Opening-known or cuspected contaminated systems, 4.- Work on contaminated or activated material.
s ' (Any-three(3) @ 0.5 each)

p' + '6 . p-(4**** CATEGORY 6 CONTINUED ON NEXT PAGE *444t)
"l - h
'
ppv - - , , .~6.
I'LANT SYSTEMS ' ( 3pO AND PLANT-WIDE GEEE.ElG Pcca 58- > dtKSLTEli1FI1,1T1EE.113%1 a
' :. ' , REFERENCE ,- 1.
Peach Bottom: LOT-1760 pg. 4 2.
LO -11 F-204001K103 ..(KA's) b.
ANSWER 6.18 (1150) ' ? c.. One-(1) member shall be.either the on-duty Shift Manager or - j the on-duty Shift Supervisor [4 0.5]- and one (1) member shall [[ not~be the'on-duty Shift-Manager or the en-duty Shift: Supervisor [+0.5).
.b.
Plant' Operations Reviek Committee (PORC) [40.5) h ao-REFERENCE ..gy F 1.
Peach Bottom: LOT-1570, L.O. 2A and 3.
2.- Peach Bottom: 'A-3, " Temporary Changes to Procedures," p.
8.
,p
~~294001A101~~
,.(KA's) D V \\- c - ANSWER-6.19.
(3.00) -c.
- ( 1.' ) [ + 1 '. 0 ). s E b.
1.. Any further-degradation in the leve1Lof plant safety ^[ (or other worsening plant conditions).
2.
Any-change from one emergency classification to another.
3.
Termination of a classification.
!L 4.
Results of ensuing evaluation orLassessments of plant " conditions,; p S t.
Effectiveness of response or protective measures taken, f-G.
Information related to plant behavior that is not W understood; Any four (4) [+0.5] each - p, , (4**** CATEGORY G CONTINUED ON NEXT PAGE ** * * * ) .. L' _"'
. 6.
PLANT SYSTEMS f30%) 41iD PLANT-WIDE GEJ4 FRIG Pag; 69 'EESZORSJIl&ITJEF E 11 + . , REFERENCE , 1.
Peach Bottom: A-31, "Notificat$on of the NRC," pp.
4, 7-22.
2.
Peach Bottom: LOT-1570, L.O.
4.
SC.
294001A116 ..(KA's) ANSWER 6.20 (2?00) a.
75 Rem b.
25 Rem a.
5 Rem d.
10CFR20 limits [+0.5) each REFERENCE 1.
Peach Bottom: LOT-1730, p.
II, L.O. S.
2.
Peach Bottom: ERP-670, Appendix 1.
294001A116 ..(KA's) \\ ' ~ ANSWER 6.21 (1.50) c.
16 houra [+0.S] b.
24 houra [+0.5] o.
8' hours (40.5) REFERENCE , 1.
Peach Bottom: A-40, " Work Hour Rentrictionc," Step 7.1.1-3.
2.
Peach Bottom: LOT-1570, L.O. 2G.
' 294001A103 ..(KA's) . (***** CATEGORY G CONTINUED ON NEXT PAGE * * * * * )
tymW n , >: ' .6 ASLhl!.LE.Yf2TEMS f SQt) AND PLANT-Q].DE,DElERIG Peg ) 60 ES1'L1! Ell 31Ll.T1 ES (13%) M . , , ANSWER G.22 (2.00)
' .. b.-
c.
d.
[00.5) each ,
REFEREllCE - 1_ Peach Bottom: EPP-0030, pp. 25, 27, 29, and 32, L.O. 7, 294001A116 2G4001A110 ..(KA*s) - \\. i . (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) / - =

~~C O g~~

. c . ATTACHMENT 2 FACILITY COMMENTS , 5.01: FACILITY COMMENT ! The question does not directly ask for the Bases for TRIP Note #20.
There are other correct responses to this question as stated.
Credit should be given for other reasonable answers based on System Operating Procedures (e.g. $.3.3.H and S.3.3.B) or general operating philosophy.
5.09: FACILITY COMMENT Random rod insertion or patterns have a high probability of produc-ing high local powers (hot spots), flux peaks, etc., which in turn-may produce fuel failure or violations of thermal limits.
5.12: FACILITY COMMENT Concerning the answer to Part b., T-115 goes on to state "... or sufficient pressure is being developed by the pumps to push enouch - water through the core to remove the decay heat being produced."
5.14: FACILITY COMMENT . Concerning Part b. of this question; ' unplanned shutdown' is listed on ERP-101 Attachment 2 as an unusual event making an answer of '1' totally valid.
However, the supervisor is directed not to initiate " ERP-101 (Emergency Notifications) and to refer to A-31.
This can easily prompt an answer of 'none' to the question.
The A-31 notifi-cation would be made pursuant to A-31:14 (ESFIRPS Actuations) not ! A-31:1 (Declaring Emergency Classification) further supporting an answer of 'none'. 5.16: FACILITY COMMENT The' question wording "..,use this parameter to generate an isolation signal," can easily be misinterpreted if the candidate places more emphasis on the word generate vice use.
He could answer based on the signal listed, in itself, must cause an isolation. With this in mind, an answer of "none" to Part a could apply since other signals must be present to actually initiate a Group III isolation.
5.17 FACILITY COMMENT The phrase " Loss of pressure suppression capability" and " incomplete steam condensation" are synonymous when discussing drywell downcomer uncovery.

,-, -e
-

~~e; o~~

O (, ., ' F*
l 6.02: FACILITY COMME-NT Concerning Part a.1; EHC runback completion is sensed by actual stator amps of 7726 amps (not load set percent meter position).
This value corresponds to 23% of rated stator amps (33591).
6.12: FACILIT) COMMENT , , Technical Specification 3.7.D.2 allows four (4) hours to either: i , " Restore the inoperable valve to operable status" (this is done when the drive is fixed and probe is retraced). - or - Isolate the affected penetration by use of at least one closed manual valve or blind flange.
(This can be accompolished by shear valve firing).
6.17: FACILITY COMMENT The point value associated with this question's answer is inconsis-tent witt, the level of responsibility for this knowledge.
. . [ C i=
~

< ' . o o- , . ATTACHMENT 3 NRC RESPONSE TO FACILITY COMMENTS The following represents the NRC resolution to the facility comments (listed in Attachment 2) made as a result of the current examination review policy.
Comments made that were insignificant in nature and resolved to the satisfac-tion of both the examiner and the licensee during the pre-examination review are not listed (i.e.: typographical errors, relative acceptable terms, minor ' set point changes).
SENIOR REACTOR OPERATOR EXAMINATION Question 5.01: Comment not incorporated. The basis for making such a decision is outlined in Note 20 of the TRIP Procedure.
Question 5.09(a): Comment accepted.
The answer key was changed to reflect facility comment.
> Question 5.12(b): Comment accepted.
The answer key was changed to reflect facility comment.
- Question 5.14(b): Comment not incorporated.
ERP-101 was the directed source to be used.
. Question 5.16(a): Comment not incorporated. Question is clearly stated.
Question 5.17: Comment accepted.
The answer key was changed to reflect facility comment.
Question 6.02(a): Comment accepted.
The answer key was changed to reflect facility comment.
Question 6.12: Comment not incorporated. Question asked in accordance with Technical Specifications.
Question 6.17: Comments noted. Assignment of point values are consistent with Region I practice.
, . .
i ! -. o

O o . . ATTACHMENT 4 SIMULATION FIDELITY REPORT Facility License: Facility Docket No.: 50-277/278 Operating Test Administered on: 9/19,20/89 This attachment reports examiner observations for information only. These observations do not constitute audit or inspection findings and are not, with-out further verification and review, indicative of non-compliance with 10 CFR 55.45(b). The observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the follow-ing items were observed.
ITEM DESCRIPTION LPRM LPRM High trip causes APRM Channel "F" to go inop.
Drywell The drywell temperature response to a LOCA is not modeled Temp, correctly Full Core Miscellaneous rod position lights were out Display ! l i !
. i
, , ,. o a-.e o . L

!

ATTACHMENT 2 FACILITY COMMENTS 5.01: FACILITY COMMENT The question does not directly ask for the Bases for TRIP Note #20.
There are other correct responses to this question as stated.
Credit should be given for other reasonable answers based on System Operating Procedures (e.g. S.3.3.H and S.3.3.8) or general operating philosophy.
5.09: FACILITY COMMENT Random rod insertion or patterns have a high probability of produc-ing high local powers (hot spots), flux peaks, etc., which in turn may produce fuel failure or violations of thermal limits.
5.12: FACILITY COMMENT Concerning the answer to Part b., T-115 goes on to state "... or sufficiant pressure is being developed by the pumps to push enouch water through the core to remove the decay heat being produced."
.f 5.14: FACILITY COMMENT Concerning Part b, of this question; ' unplanned shutdown' is listed on ERP-101 Attachment 2 as an unusual event making an answer of '1' totally valid. Howeve - he supervisor is directed not to initiate , ERP-101 (Emergency Not u q 4tions) and to refer to A-31.
This can easily prompt an answer et 'none' to the question.
The A-31 notifi-cation would be made pursuant to A-31:14 (ESF1RPS Actuations) not A-31:1 (Declaring Emergency Classification) further supporting an answer of 'none'. , 5.16: FACILITY COMMENT The question wording "...use this parameter to generate an isolation

signal," can easily be misinterpreted if the candidate places more emphasis on the word generate vice use. He could answer based on the signal listed, in itself, must cause an isolation. With this in mind, an answer of "none" to Part a. could apply since other signals must be present to actually initiata a Group III isolation.
5.17 FACILITY COMMENT , The phrase " Loss of pressure suppression capability" and " incomplete steam condensation" are synonymous when discussing drywell downcomer uncovery.

-. -
( ,

!-

c' . s~ o . f o.
' , + g .. !' 6.02: FACILITY COMMENT ' Concerning Part a.1; EHC runback completion is sensed by actual stator amps of 7726 amps (not load set percent meter position).
This value corresponds to 23% of rated stator amps (33591).
6.12: FACILITY COMMENT Technical Specification 3.7.D.2 allows four (4) hours to either: H f " Restore the inoperable valve to operable status" (this is done when the drive is fixed and probe is retraced). - or - ' Isolate the affected penetration by use of at least one closed manual valve or blind flange.
(This can be accompolished by shear valve firing).

6.17: FACILITY COMMENT , The point value associated with this question's answer is inconsis-tent with the level of responsibility for this knowledge.
, &

..
T ' f % y - , - e , ( ,o . i ATTACHMENT 3 L NRC RESPONSE TO FACILITY COMMENTS The following represents the NRC resolution to the facility comments (listed in Attachment 2) made as a result of the current examination review policy.
Comments made that were insignificant in nature and resolved to the satisfac- ' tion of both the examiner and the licensee during the pre-examination review are not listed (i.e.: typographical errors, relative acceptable terms, minor - - set point changes).
SENIOR REACTOR OPERATOR EXAMINATION Question 5.01: Comment not incorporated. The basis for making such a decision is outlined in Note 20 of the TRIP Procedure.
Question 5.09(a): Comment accepted.
The answer key was changed to reficct facility comment.
Question 5.12(b): Comment accepted.
The answer key was changed to reflect facility comment.
Question 5.14(b): Comment not incorporated.
ERP-101 was the directed source to be used.
Question 5.16(a): Comment not incorporated. Question is clearly stated.
Question 5.17: Comment accepted.
The answer key was changed to reflect facility comment.
. Question 6.02(a): Comment accepted.
The answer key was changed to reflect facility comment.
Question 6.12: Comment not incorporated.
Question asked in accordance with Technical Specifications.
Question 6.17: Comments noted. Assignment of point values are consistent with Region I practic E '

{
e [
.. ,

~~ATTACHMENT 4 , SIMULATION FIDELITY REPORT Facility License: Facility Docket No.: 50-277/278 Operating Test Administered on: 9/19,20/89~~

This attachment reports examiner observations for information only. These observations do not constitute audit or inspection findings and are not, with-out further verification and review, indicative of non-compliance with 10 CFR 55.45(b).
The observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the follow-ing items were observed.
ITEM DESCRIPTION LPRM LPRM High trip causes APRM Channel "F" to go inop.
Drywell The drywell temperature response to a LOCA is not modeled Temp.
correctly Full Core Miscellaneous rod position lights were out Display . Y }}

v t e Inspection Report - Peach Bottom - 1989018
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1989 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 20(0) 21(0) 22(0) 23(0) 24(0) 25(0) 26(0) 27(0) 28(0) 29(0) 80(0) 81(0) 82(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000277/1989018

Text

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