ML20082P399

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Forwards Comment Summary of Reactor Operator & Senior Reactor Operator License Written Exam Administered on 910826
ML20082P399
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/03/1991
From: Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Conte
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
CCN-91-14142, NUDOCS 9109100315
Download: ML20082P399 (13)
v • d • e


Text

. 'r.M-91-14142 C

I'llit.ADl!I.I'llI A til.l!CIHIC COMl'ANY Pl.ACil Ilul"lONI AIOMIC I'04 t R bl AllON

h. D I,1104 20H Drlu, l'i nns) h anu 17314

% _ tM rau u soitou.4u, rov ,a or au tittw a pl7) 4$47ul4 D. IL Mitter, h, Yke PresiJent September 's, 1991 Regional Administrator U.S. Nuclear Regulatory Conunission Region 1 475 Allendale Road King of Prussia, PA 19406

SUBJECT:

facility Conunent on Written Licens! Examinations Administered at Peach Bottom Atomic Power Station. August 26, 1991.

Dear Mr. Conte:

The attachments to this letter document the couplete formal conunent sununary of the Reactor Operator and Senior Reactor Operator License Written Examinations administered on August 26, 1991. The i, jority of the referenced supporting documentation, of which portions are attached, can be found in materials forwarded to your of fice for exam preparation.

Sincerely, y

/

fG,0

(), h. lhs e CFL' N.  ?

DBM/ /JWL:cig  ;

Attachments  ;

cc R. A Burricelli, Public Service Electric & Gas T. M. Gerusky, Conanonwealth of Pennsylvania .

J. J. Lyash, USNRC Senior Resident inspector l T. T. Martin, Administrator, Region 1. USNRC R.1. McLean, State of Maryland H. C. Schwenun, Atlantic Electric C. Sisco,-NRC J. Urban, Delmarva Pcuer ti.S. - NRC, At tn: Document Control Desk .

i 9109100315 910903

{DR ADOCK 0500 7 g/J//.2.;

/// .

_ - . _ . _ _ _ _ _ _ _ _ . _ _. ._ _ _ . _ _ _ . _ _ _ . _ __. _ .. - . _ .~. _ ._

. ,REAC10R OPERATOR i 052 i QUESil0N: (1.00)

Which DNE of the following components cf the condensate pump receives cooling from 1BCCW7 l A. Journal bearing oil cooler t i

B. Ihrust bearing oil cooler [

C. Shaft seal oil cooler i t

D. Motor seal oil cooler l t

ANSWER: 052 (1.00) [

D.  !

REFERENCE:

L01-0520, Rev. 3, obj. 3, pgs 8 & 21  !

NUREG-1123, NRC BWR K/A Catalog, K/A 256000, K6.05, 2.9/2.9 (p.3.2-21) l l

256000K605- .,(KA's) [

SENIOR REAC10R OPERA 10R QUE5110N: 037 (l.00)

Which ONE of the following components of the condensate cump received cooling  !

from IBCCW7 i A. : Journal bearing oil cooler B.- 1hrust bearing oil _ cooler  !

t C. Shaft seal oil cooler f i

D. Motor seal oil cooler  !

ANSWER: 037 (1.00)  !

D.  !

REFERENCE:

L01-0520, Rev. 3, obj. 3, pgs 8 & 21 l

'NUREG-1123, NRC BWR K/A Catalog, K/A-256000, K6.05, 2.9/2.9 (p.3.2-21) j 256000K605 ..(KA's) l FAClll1Y COMMENT:

1

-R0 Question 052, SRO Question 037: Answer 8, "lbrust Bearing 011 Cooler" is  !

the correct answer in lieu of Answer D. P&l0 M-316, sht. 2 (attached)  !

indicates that 1BCCW cooling is provided to the thrust bearing cooler and *

. upper and lower motor bearing cooler.

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4

. SENIOR REACTOR OPERATOR QUEST 10N: 077 (2.00) ,

Hatch the responsibility in Column I with the person to whom it is assigned ,

during an emergency in Column 11. Assume that all emergency facilities are fully activated. Items in Column I have only one correct answer and items in  :

Column 11 may be used once, more than once or not at all. (0.50 pts,per '

response)

Column 1 Column 11 (Pesponsibility) (PersonAssignedTask)

1. Activated emergency response A. Emergency Director organization. *
8. Emergency Response
2. Directs initiation of Director accountability.

C. Emergency Support

3. Authorizes emergency exposure Officer limits-and administration of potassium lodide. D. Operations Support Center Coordinator
4. Serves as primary on-site contact for federal, state E. Technical Support  :

and local radiological Team Leader response agencies.-

ANSWER: 077 (2.00)

A D

A B

REFERENCE:

PBAPS ERP-200,-pg. 1 of 31 PtiAPS EPP-1100, objectives lla page 22 and 2d. page 21 -

K/A: 294001All6 2.9/4.7 294001All6 ..(KA's)

FACll.lTY COMMENf:

SR0 Question 077: Accept Answer A for item 2 in addition to Answer D.

ERP-510, Personnel Accountability (attached), Section 6.2, Criteria for Use, states.that-this procedure (Personnel Accountability).... "shall be used ...

, as directed by the Emergency Director (ED)." Additionally, ERP-200 L EmergencyDirector(attached),Section1.1.9listsasaresponsibi1Ityofthe l Emergency Director to "act as Accountability Coordinator for the Control Room (CR)," in accordance with ERP-510, Personnel Accountability, whereas ERP-220, -

Operations Support Center .(OSC) Operations Personnel, Item 1.1.3 lists

" Accountability Coordinator" as a responsibility of the OSC Coordinator.

i ERP-510 0 QUESTION 077 HEFERENCE Page 1 of 10, Rev. 7

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4 'j": y RRG:dik jff

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,' : . 644 W;"s (spn; W '.' .*

- l ly/3i. .. . : ' pH1'L'ADELPHIA E LECTRIC COMPANY t//4t?/

e PEACH B0110Fi UNilS 2 AND 3 l EHrRGENCY RESPONSE PROCEDURC ERP-510 PERSONNEL ACCOUNTABIL11Y l 1.0 RESPONS!BillTIES ,

t 1.1 All members of the PBAPS In-Plant Emergency Response Organization are responsible for reporting to their assigned Emergency Response facility, carding in and/or logging in for their facilitie's Accountability.

1.2 All non-emergency and TSC/ EOF Emergency Response personnel are I responsible for evacuating the protected area via the Guardhouse and reporting to their designated facilltv or assembly area.

1.3 Accountability Coordiriators are responsic e for providing Security with an Accountability list of personnel assigned to tnelr facility i or assembly area upon request.

1.4 The Accountability Group Leader is responsible for:

1.4.1 Directing and controlling of personnel leaving the Protected .

Area.

1.4.2 Coordinating Accouiitability Group efforts.  ;

1.4.3 Providing a roster of unaccounted-for personnel to the Security Te n Leader within 30 minutes of an Site Evacua. tion announcement.

1.5 The Access Control Group Leader is responsible for:  ;

1.5.1 Providing traffic control to the assembly areas.

1.5.2 Ensuring notification of non-PA system covered areas.

r 1.5.3 Providing aid to the Vehicle and Evacuee Control Group Leader, t 1.6 The Accountability Group and Access Control Group members are responsible for: l l

1.6.1 Providing direction and coritrol of personnel leaving the Protected Area.

1.6.2 Obtaining accountability data.

l 1.6.3 Notifying non-PA system covered areas.  ;

!!R0 QutST1011 077 REFERENCE ERP-510  !

Page 6 of 10 Rev. 7 5.0 ATTACHMENTS AND APPENDICES  !

5.1 Attachment 1 - Personnel Accountability flow Chart 5.2 Attachment 2 - In-Plant Huster Area Phone List 5.3 Attachment 3 - Accountability List i

6.0 SUPPORTING INFORMATION 1 6.1 PURPOSE To define the actions of the Security Team and plant personnel  !

during a Site Evacuation.necessary to provide accountability of Pro!

6.2 CRITERIA FOR USE as directed by the Emergency Director (ED).This , or pr

6.3 REFERENCES

6.3.1 Appendix E Section IV, Subsection A, Organi '

6.3.2 ERP-500,SecurityTeamLeader(STL) 6.3.3 ERP-520, Security Team 6.3.4 i NUREG-0654 Criteria for Preparation and Evaluation of >

Support of Nuclear Power PlantsRadiological Emerg .

6.3.5 Peach Bottom Atomic Power Station (PBAPS) Emergency Pla 6.3.6 .

PBAPS Security Plan and Contingency Procedores t

a

.j l

t l

9 U liOK ylfESTIOM 077 REFEREN R d /dm

/ PHILADELPHIA ELECTRIC COMPANY 7d PEACH ROTTOM UNITS 2 AND 3

( O EMERGE: ( RESPONSE PROCEDURE i

ERF-200 EMERGENCY DIRECTOR (ED) 1.0 RESPONSIBillTIES 1.1 The Emergency Director is responsible to:

1.1.1 Verify the event conditions and determine emergency classification.

1.1.2 Activate and direct the emergency response organizetion initial response phase.

1.1.3 Direct accident assessment and operations technical analysis.

1.1.4 Coordinate accident mitigation and plant operations stabilizing actions.

1.1.5 Authorize emergency exposure limits and administration of Potassium lodide (Kl). When the Energency Response Manager is not activated, authorize off site protective actions.

1.1.6 Be tne single source for plant operations ir. formation and

,e x data.

i s 1.1.7 IMorm the Emergency Respor. . Manager of plant status and the equences of response actions.

1.1.8 Provide final approval of emergency sptcill procedures.

1.1.9 Act as Accountability Coordinator for the Control Room (CR) in accordance with ERP-510 personnel accountability. When the ED shifts from the CR to the Technical Support Center (TSC), Shift Management will remain as Accountability Coordinator for the Centrol Room.

1 -

l l HOTE: THE EMERGENCY DIRECTOR TITLE IS CREATED UPON THE CLASS!FICATION OF 1 THE EMERGENCY AND 15 FILLED BY SHIFT MANAGEMENT. THE PLANT MANAGER l DESIGNEE ASSUMES THE DullES ON ARRlVAL AND WHEN KNOWLEDGEABLE OF l l PLANT CONDITIONS, AND SHIFT HANAGEMENT RETURNS TO CONTROL ROOM l ASSIGNMENT. l I I l L l

l NOTE: THE EMERGENCY DIRECTOR MAY ELECT TO ASSMN A PERSON AS AN ASSISTANT.

l THE EMERGENCY DIRECTOR SHALL DESIGNATE THOSE FUNC110NS FOR WHICH THE i ASSISTANT IS RESPONSIBLE. l l l t ,

t e

ERP.220

. Page 1 of 12 Rev. 4 cuo quest 1ou 077 RtrERENCE RRG:dmk/dik PHit ADELPill A ELECTRIC C0t1PANY bgt,q 2

... PEACil BOTTOM UN!TS 2 AND 3

(.

EMERGENCY RESPONSE PROCEDURE ERP-220 OPERATIONS SUPPORT CENTER (OSC) OPERATIONS PERSONN[L 1.0 RESPONSIBillTIES 1.1 Operation Support Center Coordinator 1.'l .1 ReportstoOperationSupportCenter(OSC).

1.1.2 Supports directives of Emergeacy Director / Shift Management.

i 1.3 functions as Accountability Coordinator of personnel reporting to OSC.

- 1.1.4 Supervises emergency response functions of operations personnel in OSC.

O 1.1.s Ceoro4netes accieent mit49 ation ect4ees Group Leader (PSCL) 4ta Piant Servey AND Damage Repair Group Leader (DRGL).

1.1.6 Coordinates AND ensures timely relief of OSC personnel.

1.1.7 Coordinates with supply personnel to ensure adequate provisions are available to support accident mitigation actions.

1.2 OSC Operations Personnel 1.2.1 Conducts investigations AND operations actions directed by OSC Coordinator. j 1.2.2 Responds as fire Brigade members.

+

2.0 INITIAL ACTIONS I

l -

~l l l 80TE: ATTACliMENT 1, OPERATIONS SUPPORT CENTER OPERATIONS I

, l PERSONNEL FLOW CilART, MAY BE USED AS A GUIDE FOR Tile l j l FOLLOWlHG ACTIONS. I 1 O i: -- I l h l l y 1 I

~ _ _ .- _ ._ _ _..-_._ - - _ . . . . _ . .

i l

SENIOR REACTOR OPERATOR ff QUESil0N: 097 (1.00) i Unit 2 has just scrammed. The following plant conditions exist: ]

Reactor Power 3%  !

- Reactor Water Levtl 17 inches Reactor Pressure 1057 psig brywell llydrogen Concentration 1.0%

Torus Level 14.6 feet  !

Steam !unnr,1 Hi Area Temperature Alarm enunciated  !

Which ONE of the following sets of procedures must be entered?  ;

RC - "RPV Control" PC - " Primary Containment Control"  !

SC " Secondary Containment Control"  ;

A. RC and PC l B. RC and SC i

C. PC and SC f D. RC, PC and SC  !

I r

ANSWER: 097 (1.00) .}

D i t

REFERENCE:

PBAPS T-101, T-102, and 1-103 -

PBAPS LOT-1550, objective 2.  ;

K/A: 295032G011 4.1/4.2 l i  !

295032G011 ..(KA's) l FACILITY COMMEjiT:

SR0 Question 097: Accept Answer A in addition to Answer D since all Steam Tunnel Hi Area Temperature Alarms are not necessurily located in the Reactor .

Building and as such are not necessarily T-103 entry conditions.

Specifically, T-102 is entered on "Rx. Bldg. Area Temperature above an alarm level" for areas listed in Table SC/T-3 (attached). For the steam tunnel, .

only Points 1 and 16 to TR 2(3)-13-139 bring up the "High Area Temp" alarm i (see ARC 20C205L J-3 attached) whereas other Steam Tunnel High Temperature ,

Alarms may be received which are not T-103 entry condiMons due to their  ;

w ation outside the Reactor Building (see ARC 20C203BF \-Z).

.i I

i 4

a ----~ - y ~n w-y---y r ,4r- -a , r w.n e ,w u- nr-e._w- ee so w -+--e < e-m. me as --

SRO QUEST 1011 097 REFERENCE k

TABLE SC/T-3 TEMPERATURE-AL ARM AND ACTION LEVELS AL ARM LEVEL (*F) ACTIDg INSTRUWENT i AREA 1R-7( 31-13-13S PT #

LEVEL gjA]yg

[

UNIT 2 UH11 3 ('F) 'c't a t a'vi s b" 105 105 135 P T 9,14, OR 2 4 10RUS R00u 105 115 135 P1 0.15. OR 20 RCIC ROOM 105 105 135 Pi 2 OR HPCI ROOM 105 105 135 Pi 3 A RHR R00M 105 105 135 PT 17 OR C RHR ROOM 105 105 135 P1 29 8 RHR ROOM 105 105 135 PT 23 OR 0 RHR ROOM 105 105 135 P1 5 101 ) L A CS ROOM 105 105 135 11 -2( 31501 P T 151 0C*' OR C CS ROOM 105 105 135 11 -2( 31501 P t 152 B CS ROOM 10d 105 135 OR 11 -2( 31501 Pt 153

O CS RODu 105 105 135 T I -2( 3)S 01 PT 154 31EAM 155 175 ISO P1 1 1UNNEL 155 1G5 190 PT 16 ROOM (SOU f 155 155 100 Pt 12 1 15 00 NORTHf 190 M 10 OR 21 I SOL V ALVE 125 125 PI T 155' EL 150 P1 30 i 0 125 13C P1 11 DR A NON RECEN HX ROOM ;25 130 OR NO PT 28 HX R00M 125 125 ACTION E PT 5 OR LEVEL

'iiD L A OR 0 RWCU FLTR 105 105 P1 10 OR 27 DEMI N ROOM Jto-1 DR C

BgASH 105 105 PT 4 EA fN.ER EL L 105 105 135 P1 22 (ukY AFFECT RPY LEVEL INST) j i

,n

  • . j SHO QUESTIO!4 097 HEFERENCE

. r r

PDAPS ALARM HESPONSE CARD I t

AIAHM M dig WUTCCW IDCATICri f Page 1 of 2  :

A B C D E F G 11 J i 1 I i

TEMP  ;

3 X 4

l 5

~

AUIORTIC ACTICt4S  !

uctrE  ;

i OPERATOR ACTICt4S .

1. Read the alarminJ points temperature on 7ES-2-13-139 by cpaninJ the l t

panel to the Recoxxter and pressing the " Print Data" push button.

7hese points printed in Red on the chart are in Alanu. 'Iha description  ;

t for these points are given on the plate below tha recorder.

2. -Dispatch Operator to sensor location to determine the cause of the ,

alarm. F

3. If any.of the astarisked points on the following page is alarminJ,  !

315 ontar T-103 Secondary Containunt Control.  ;

4. Verify that SW QB ESW is available to the operating zuzn coolers, that [

ccolar valve alignment is proper and the fans started.1 LD.'ll 1he Stardby Cooler aM Fan in each of the ECCS rooms has bean isolated  ;

due to low flow on the ESW system. DO NOT start the Standby Cooler  ;

aM Pan in any of the ECCS turns, this would p2t the ESW and ECCS  !

systems in an untested configuration, t

CAUSE: I

1. Steam Isak
2. Fire ,
3. Loss of area cooling [
4. Icss of ventilation l i

ALARM SEITODft: 3 AUS( RESET;; y .

[

See next page.

MANUAL  !

ACIW.TD43 DEVICE (S) *

.IBS-2-13-139-REFERDiCES: ABC HlHEER 210  !-

M-351 Sh I h 2 E-242 Sh 2 20C205L J-3 I M-1-s-32 sh 1 & 2 M-354 Sh 1 p >

1. therick IER 1-89-47 R8V. 3 '[#

0

b SRO. QUESTION 097 REFERENCE i Page 2 of 2 20C205L J-3 ,

Pav. 'J -

t ALMN SETPOIl(T!

Q{A!MEL TIEMDCCUPIE SET FOIITF

10. DD~REES F l
  • 1. TE-2-02-126A 165
  • 2. TE-2-13-077A 105 t
  • 3. TE-2-23-105A 105 l
  • 4. TE-2-12-117B 105
  • 5. TE-2-12-117G 125  :
  • 6. TE-2-10-0980 105
7. TE-2-02-126B 160 j
  • 8. TE-2-13 -077B 105
  • 9. TE-2-23-105B 105 ,
  • 11. TE-2-12-117H 125 [
  • 12. TE-2-10-098E 165 l
13. TE-2-02-126C 160
  • 14. TE-243-077C 105 {
  • 15. TE-2-23-10$C 105
  • 16. TE-2-12-117D 165 ,;..
  • 17. TE-2-10-098A 105 '
  • 18. TE-2-10-098F 165
19. TE-2-02-126D 160 >
  • 21. TE-2-23-1050 165
  • 22. TE-2-12-117E 105
  • 23. TE-2-10-0988 105 [
  • 2: TE-2-10-098G 105  !

21, . lOfE j

26.  ! DIE l
  • 27. TE-2-12-117A 105 j
  • 28. TE-2-12-117F 125
  • 29. TE-2-10-098C 105
  • 30. TE-2-10-098H 125  ;

i

  • T-103 Entry Condition i

-. _ - _ . _ . - - - - . - - . - - - . . - . . . - - - . . - . ~ . _ _ . . - . . - - ~ _ . - .

i SRo, QUES'IIO!1097 REFERENCE j l

f

.s ,

g'

~ ~

(s f PBAPS ALARM RESPONSE CARD WINDLM II)CATICH AIAHH WORDIN3 i A B-C D E 1

SYS'IU4 II  ;

2 X S'IEAM t

= - - .

TueEL l 3 HI TV4P l l i 4  !

5 -j Al110% TIC ACTIONSI j

1. Group I' Isolation if in conjunctlic with System I Steam 'Ibnnel liigh ,

M.  !

OPERAT TPIONS t

1. Check corresporriing Systm I alarm to see Group I isolation condition }

! exists.  ;

2. Notify Shif t Managment.
3. JI Group I Isolation has E occurred, 31g confim at Panel 20C017.
a. By indication light #16A-D6257B/D NZr illuminated which "OiANNEL" j brought up alarm (B (E D). i
b. By continuity check:

o Relay Coil H2r defective (16A-K2B/D) {

c. Cmpare tmperature ir:11 cation for consistency on 2AC270 QB 2BC270 i in Control Room. ,.

CAUSE:

Steam leak -

i AINN SE?IPOINrt AINN RESET: ,

192.5 F increasing MAtCAL ,

ACIUATItG DEVICE (S): . i l TS-4931B & D, 4932B & D, 4933B & D, 4934B & D l I

REFERDCES: . ARC IU4BER: 228  :

_t E-238 20C203BB A-2 H-351 r); ,

M-1-S-23 -

Hev. 2

'( l

. ,_ , -_ _m ._ -._ . . _ . . . . _ , _ . . - _ . .- ___..._...._. . _ . _ -

_ - , - - - ~ . .

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