ML20247A070

Forwards Comments Re Senior Reactor Operator Written Exam Administered on 881220

ML20247A070
Person / Time
Site:	Oyster Creek
Issue date:	12/27/1988
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:	Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20247A029	List: IR 05000219/1988034 ML20247A021 ML20247A070
References
NUDOCS 8907210124
Download: ML20247A070 (13)

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GPU Nuclear Corporation i

Q g7 Post Office Box 388 I

f Route 9 South Forked River,New Jersey 08731-o388 j

609 971 4000 -

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Writer's Direct Dial Number:

December 27, 1988 Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Examination Report No. 88-34 As directed by a letter from Mr. David J. Lange of the NRC dated August 30, 1988, attached are our comments concerning the SR0 written examination administered at Oyster Creek on December 20, 1988. We appreciate your consideration of our comments for inclusion in the grading process.

Very truly yours, w

E. E. Fitz rick Vice President and Director Oyster Creek EEF/MH/smz (0268A:61)

Attachment cc:

T. Walker, Operations Engineer, BWR Section Operations Branch, Division of Reactor Safety Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 8907210124 890207 DR ALOCK 05000219 k

y PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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.. QUESTION _

5.05-

.(3.00) _

Certain plant.ovo'lutions could subject the reactor vessel t r

'C excessive stresses iffoperational. limits were not observed.

' LIST FIVEL(5) evolutions that are controlled by operational limits,that could subject the. reactor vessel to excessive

]

' stresses.

(3.0)

ANSWER-5.05 (3.00) 1.

, Vessel! head bo3t1 tensioned 2.

Pressurizing the reactor vessel 3.

vessel'heatup 4.

' Vessel cooldown

-5.

Recirculation pump start (all at o.6 each)

REFERENCE LP s,

THEMO.RT.and FF.

CH10 pg.10-15,10-16

'OBJ TCR'861.07 LO' C,D KA: 293010 KI.04-(2.9/3.2) i 293010K104 (KA's)

OYSTER CREEK COMMENT-Should accept evolutions other than listed which could result in

. excessive stress if limits were not observed.

Examples:

1) Maximum temperature for Rx vessel pressure testing is 250*F.

2)' Minimum reactor vessel temperature for power operation.

3) Maintain 6T between head and flange < 200*F.

4)

If all recirc pumps trip must depressurize prior to restart.

5)- During scram maintain 150 psig pressure band.

REFERENCES Tech Spec page 3.3-1 Gen Operating Procedure 201.2 ABN 3200.01 L

1 3700b

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hh l QUESTION 5.08-('2. 50) =

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Given the following information l'

APRM = 49.50V GAF.=

l'.02-I,.y

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MFLPD =-. 50 A.

Is the ratio FRP/MFLPD less than'1.07 SHOW ALL WORK..

B. 'WHAT action is: required if FRP/MFLPD is less.than 17'

( !.

. 5.08 (2.50)

' ANSWER

.A..;NO-(.5)'FRP=GAF*APRM (FRP=1.42*.495(=.5049'(.5)

.5049/.5=1.01 B.

Adjust the APRM gain-(ratio of FRP/MFLPD) (1.0)

REFERENCE-

'LP:..

Tech Spec pg 2'.3-2 OBJa.

TCR 850.90 LO. J KA:

293009K109-(3.3./3.7)

.-293009K109-

-(KA"r) i ',

OYSTER CREEK COMMENT.

Should' accept adjust APRM scram and rod block settings for part B.

.-REFERENCE Tech Spec page 223-4 paragraph 3.and 2.3-5 paragraph 3 T

d 3700b

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4 s.

QUESTION' 5.09 (2.50).

A.

STATE two (2) reasons that subcooling is required in the'downcomer 1 region of a BWR during power operations.

B.

Feedwater enters the reactor at'1000 psia and 400.deg.F.

DETERMINE the amount of subcooling of the feedwater in BTU /lbm.

ANSWER 5.09 (2.50)

A.

1. To prevent cavitation of'the recirculation pumps (0.5)

2. To prevent excessive steam formation in the 3ovar portion of the core which;could. lead to inadequate cooling of the y

upper. core..

(0.5)

B.

h of sat. 11guld at 1000 psia is 542.6. BTU /1hr. (from steam table) h of liquid at 400 deg F and 1000 psia is 375.81' BTU /lbm (0.5) 542.6 - 375.81 = 166.79 BTU /lbm (+ or - 5 BTU /lbm)

.(0.5)

REFERENCE LP:

THMO. HT. and FF. CH4 pg. 4-23,4-24 3

Hot Lic.Op Annual Exam Bank Item Code I-74 OBJ TCR 852.04 LO. C,H KA:

293003 K1.23 (2.8/3.1) 293008 K1.19 (2.6/2.0),

293008K19 293003K123 (KA's)

OYSTER CREEK COMMENT

-For part A Should accept further away from OTB

[ Critical Power Increases]

REFERENCE GE Thermo, HT and FF page 9-85

>.-3700b

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QUESTION 6'.02 (2.50)

Concerning the reactor recirculation flow control system:

~

A.

.During your shift you notice the loop Cz Individual Controller manual-auto switch is in the "BAL" position.

WHICH controller is controlling loop C7 B.

If the loop B individual Controller switch is in " MANUAL" WHAT two (2)' signals are compared by the controller circuit to produce the signal that is sent to the Bailey (scoop tube) positioner?

C.

WHAT device provides a position signal to the scoop tube during the M.G. Set start sequence?

D.

WHAT is the input to the Master Controller when the Master Controller is in " MANUAL"?

ANSWER 6.02 (2.50)

A.

the Master Controller (0.5)

B.

Speed signal (set by the operator) (0.5) and the feedback speed ~

signal (from the M.G. Set (Generator) tachometer).

(0.5)

C.

The low limiter portion of the dual limiter.

(0.5).

D.

The speed feedback signal from the M.G. Set.

(0.5)

REFERENCE LP OPM Mod 38B pg 38B-10 thru 19 Fig 38B-5B OBJ:

TCR 828.40 LO. E KA: 202002 K4.02 (3.0/3.0) 202002 GO.07 (3.6/3.6) 202002G007 202002K402 (KA's)'

OYSTER CREEK COMMENT.

For Part B:

The Master Controller's only input is from rheostat, not from speed signal. Answer should reflect this fact.

REFERENCE OPM 38B - Figure SB and Figure 8 L 3700b

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QUESTION 6.04

.(3.00) l:

+

For the below listed Reactor. Protection system trip signals.

EXPLAIN WHY each is bypassed as shown.

~

'Peactor Protection

~ Trip System Bypassed 1.-

Low Condenser Vacuum (600 psig and not in RUN i

. Turbine Trip; Turbine steam flow (40%~

-2.

3.

Mode Switch to Shutdown

'After a 20 second time delay ANSWER 6.04 (3.00) 1.- Permits, plant operation to generate adequate steam and pressure to establish turbine seals and condenser ~ vacuum at relative low power.

2.

Sufficient protection is provided by other scrams below 45%

(As detailed' analysis have shoun) 3.

Provides the ability to reset the scram (0.5) thereby. relieving scram pressure from the control rod drives which will increase their expected lifetime. (0.5)

REFERENCE, LP:

Tech Spec 3.1-3 3.1-4 OBJ TCR 828.37 LO. A KA:

212000 Kv.12 (3.9/4.1) 212000K412 (KA's)

OYSTER CREEK COMMENT For part'2:

Should accept bypass valve capacity as basis for bypass.

REFERENCE Tech Spec. page 2.3-5 paragraph 4 and page 3.1-4 paragraph 7 d

e 3700b

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QUESTION 6.06 (2.00) e Concerning the Containment Spray System:

A.

LIST the signal (s) required for an automatic initiation of the Containment Spray System.

(Include set points)

B.

EXPLAIN the purpose of the 20 second, flow dependent, time delay associated with the 5% valve.

INCLUDE in your explanation the results of not having this time delay.

ANSWER 6.06 (2.00) j A.

1. High Drywe31 pressure (0.25) 3.5 psig (0.25)

2. LO-Low reactor water level (0.25) 86" TAF (0.25)

B.

To prevent short cycle of the blow down flow path upon initiation of containment spray. (0.5) If it were to open immediately upon containment spray initiation a flow path would exist from the drywell through the 5% valve to the air space of the torus, since flow had not yet developed. (.25) This would pressurize the torus and could prevent complete blow down. (0.25)

REFERENCE LP:

OPM Mod 09 pg. 09-12, 09-24 OBJ:

TRC 828.09 LO. E, F KA:

226001 KV.09 (3.2/3/4) 226001 G007 (3.5/3.5) 226001K409 226001G007 (KA's)

OYSTER CREEK COMMENT For Part A.1:

Should accept 3 psig as setpoint.

REFERENCE Standing Order #1

. 3700b

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QUESTION 7.04 (2.50) 1 0

Concerning "RPV Control", Procedure EMG-3200.013-A.

IDENTIFY three (3) systems utilized to augment RPV level control.

(Alternate Injection Subsystems)

B.

BRIEFLY EXPLAIN when these systems are required to be utilized.

ANSWER 7.04 (2.50)-

A.

1. Fire Water

2. Core Spray Keep Fill (Condensate Transfer)

3. SLC B.

If RPV water level cannot be restored and maintained in the normal

'~

band. (1.0)

REFERENCE LP EMG 3200.01 step RC/L-4 OBJ:

. KA:

295031EA108 (3.9) 295931A108 (KA's)

OYSTER CREEK COMMENT For part B:

Should accept if no injection subsystem is lined up for injection with at least one pump running.

REFERENCE EMG-3200.03 Step LR-4.1 L

I 3700b L

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QUESTION 7.07 (2.00) l The " Reactor Scram", Procedure ABN-3200.01, atates that RPV water level should be maintained between 138" abd 174" TAF.

A caution in that procedure provides guidance to the operator if RPV water level exceeds 180" TAF.

i A.

vnD6T immediate action must be taken if this water level is exceeded?

J B.

EXPLAIN the concern with water level greater than 180" TAF ANSWER 7.07 (2.00)

A.

Place the control stches for the Condensate Return Isolation valves (V-14-34 and 35) in the closed position (0.5) until reactor water level is below 180" TAF. (0.5)

B.

(Severe) Water hammer of the isolation condenser may occur.

REFERENCE LP: ABN-3200.01 pg. 4 OBJ:

TCR 80-1.01 LO.A.1, C KA:

20700 A1.06 (3.5/3.7) 295006 A2.03 (4.0/4.2) 295018K101 (KA's) 1 OYSTER CREEK COMMENT For part A

..oUntil reactor water level is below 180" TAF," should not be required as part of answer since question only asks what operator should do if this level is exceeded.

REFERENCE None l

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- 3700b

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i' QUESTION-8 04L (3.00)

DEFINE cr EXPLAIN the following terms as they appear in Technical Specifications.

A.

Core Alteration B.

COLD Shutdown C.

Identified Leakage D.

Power operations ANSWER 8.04 (3.00)

A. - A core alteration is the addition, removal, relocation or other manual movement of fuel or controls in the reactor core.. (.75)

B.

The reactor is at cold shutdown when the mode switch is in the shutdown mode position (.25) (there is. fuel.in the reactor vessel) all operable control rods are fully inserted (.25) and the reactor coolant system maintained at less than 212 F and vented. (.25)'

C.

Identified Leakage'is that leakage which is. collected in the primary containment equipment drain tank (.5) and eventually transferred to radwaste for processing.

(.25)

D.

Power operations is any operation when the teactor is in startup mode

(.25) or run mode (.25) except when primary containment integrity is not required.

(.25).

REFERENCE LP2-T/S pg 1.0-1.2.4 OBJ:

TCR 850.90 LO B KA:

212000A216(4.0/4.1) 212000A216 (KA's)

OYSTER CREEK COMMENT For part C" Should not' require "...and eventually transferred to radwaste for processing."

REFERENCE Tech Spec page 3.3.-6 paragraph 4 9-3700b L _ _ __

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' QUESTION 8.05

'(2.50).

A.--WHAT is a Non-Substantive change to a procedure in accordance with "Pr'cedure Control", Procedure #107?

B.

WHO can temporarily approve a NON-Substantive change 7 C.

-A temporary change (other than temporary Non-Substantive change) that cannot be delayed-for normal review and approval.'can be approved by two (2) members of the'GPUN management staff.. STATE two (2) requirements these staff members must meet.

D..

TRUE or FALSE All' outstanding temporary changes,in a procedure shall automatically l:

expire 60 days after the most recent temporary change entered in a procedure.

- ANSWER 8.05 (2.50)

A.

. clerical changes, typographical error and other similar items B.

A person holding an RO or SRO license for OCNGS C.

.1. Qualified responsible Technical Reviewer

2. At least one of-these individuals shall be the on-shift GSS or $40 licensed GOS

3. Must be knowledgeable in the area or category affected by the -

. procedure.

(ANY two'(2) at.5 each)

D. - TRUE. (o.5)

' REFERENCE LP Procedure 107 pg 24,26,27

'OBJs TCR 850.05 LO. MM,NN KA:

294001A103(3.7) 294001A103 (KA's)

OYSTER CREEK COMMENT For part Ds should accept true or false bec6use it depends on how you interpret the question.

If you interpret the question that all temp changes expire 60 days from most recent change then it is false.

REFERENCE Admin Procedure 107 5.3.5.5 3700b'

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QUESTION, 8,08~

(2.00)

A.

. DESCRIBE the difference.,between Category I and Category II events as

. defined in " Notification of a Station Event", Procedure #126.

B.: WHO is responsible,for determining the category of an event in accordance with Procedure #126.

ANSWER 8.08' (2.00)

A.

Cat-I includes all events which result in declaration of an unusual event, alert, site area emergency or a general emergency undet the-emergency plan.

(.75)

Cat II includes events not classified a cat I which require notification of the NRC and others within one (1) hour of occurrence.

(.75)

B.

. Group Shift Supervisor (0.5)

REFERENCE LP Procefure 126 pg 4,8 OBJ TCR 830.05 -LO. XX,YY

' KAs.

294001A103 (3.7) 294001A103

-(KA's)

OYSTER CREEK COMMENT For part At.

Should accept Cat I requires 15 minute notifications where Cat II only requires I hour notifications.-

REFERENCES 9473-IMP-1300.02 Admin Proc. 126

. 3700b

==-_:__.-._-._--__-___-_-______._______-___---__---- -_. -

f 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. Only those comments resulting in significant changes to the master answer key, or those that were "not accepted" by the NRC, are listed and explained below. Comments made that were insignificant in nature and resolved to the satisfaction 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).

Question 5.05: Comment partially accepted. The question asked for five (5) evolutions, not to state operational limits. Examples 4 and 5 will be added to the ansver key.

Question 5.08: Comment accepted. Additional answer for part B is acceptable.

Question 5.09: Comment ettepted. Additional answer in part A is acceptable.

Question 6.02: Comment accepted. Answer key revised per DMB 38B-13.

Question 6.04: Comment not accepted. The setpoint is only coincident with Bypass Valve capacity and is not the reason for it being bypassed.

Question 6.06: Comment accepted. Additional answer for part A.1. is acceptable.

Question 7.04: Comment accepted. Additional answer for part B is acceptable.

Question 7.07: Comment accepted. Answer key revised to reflect immediate action only.

Question 8.04: Comment accepted. Answer key revised to give full credit if second part of part C. is omitted in the answer.

Question 8.05: Comment not accepted. Statement taken verbatim from procedure.

Question 8.08: Comment partially accepted. Partial credit will be given if only the time limits for notification are stated.

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