Text

Exam Rept 50-354/89-04OL on 890214-16.Exam Results:All Three Senior Reactor Operator Candidates Passed Written & Operating Exams.Housekeeping Problems Noted in Diesel Generator Rooms
	ML20244B610
Person / Time
Site:	Hope Creek
Issue date:	04/05/1989
From:	Conte R, Howe A; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20244B599	List: IR 05000354/1989004; ML20244B596; ML20244B616;
References
	50-354-89-04OL, 50-354-89-4OL, NUDOCS 8904190288
	Download: ML20244B610 (58)
	v • d • e

C

,,

-

,

n.

'

>

,_

U.S. NUCLEAR' REGULATORY COMMISSION REGION I OPERATOR' LICENSING-EXAMINATION REPORT

,

EXAMINATION REPORT NO.

89-04 '(OL)

FACILITY DOCKET NO.-

50-354-

!

l FACILITY. LICENSE NO.

DPR-16

,

LICENSEE:

Public Service Electric and Gas Company P, O. Box 236 Hancocks Bridge, New Jersey 08038 FACILITY:

Hope Creek Nuclear Generating Station

'

EXAMINATION DATES:

February 14 - 16, 1989 EXAMINERS:

C. Sisco, Operations Engineer, (Examiner Certification)

'

M. Daniels (Sonalyst)

-

-[X)r]/ s c//f/Ser CHIEF EXAMINER:

_ fren G. H#e,len115r Operations Engineer Date h

'/ T f

APPROVED BY:

Rfchard J. Conte, f41ef, BWR Section

.

.Date Operations Branch, Division of Reactor Safety SUMMARY: Written examinations and operating tests were administered to three (3) senior reactor operator (SRO) candidates. All of the candidates-passed the written examination and the operating test. 0verall, the candidates were well prepared for the examination.

During the conduct of the operating test, an unauthorized worker was found in the simulator.

This was not a breach in the security of the test, however. Also, housekeeping problems were noted in the Diesel Generator room. A lesson plan and an Administrative Procedure were not updated to reflect current practice on a log no longer needed in the control room.

-.

V

/

I,'

h;

,

'

- >

i

'

DETAILS-

'1.

INTRODUCTION AND OVERVIEW The NRC examiners conducted this replacement examination for th'ree'(3)-

' Senior Reactor Operators (SRO) - two (2) SRO iristant-and 'one (1) SR0 upgrade. The examinations were administered in accordance with NUREG-1021,' Rev. 5, dated January 1,1989. Examiner Standards (ES). The results are summarized below.

l.

RO l

SR0 l

l Pass / Fail l ' Pa ss/ Fail l

I I

i l

I l Written l

N/A.

I I

l 3 / 0 l

l i

I I

I

.I-l Operating-l N/A l

3 / 0 l

I I

I l.

I I

l l Overall.

l N/A l.

3 / 0 l

l l

2.0 EXAMINATION RELATED FINDINGS / CONCLUSIONS 2.1.The.following. is a summary of general strengths and deficiencies noted on the operating tests.

This information is being provided to aid the li ensee in upgrading license and requalification training programs. No licensee response is required.

STRENGTHS a.

Good use of plant procedures b.

Good use of Emergency Plan Implementing Procedures DEFICIENCIES No general deficiencies were noted.

2.2 The following is a summary of general strengths and deficiencies noted from the grading of the Senior Reactor Operator written examination. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required.

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

-

- _ - _ _

_

_-_

_ - _ _ _ - _ _ - - - _ _.

--

{

p g-

3 L

i l-STRENGTHS ji '

a.

Knowledge of natural circulation - Question 5.01-

- b.

Knowledge of recirculation pump isolation - Question 5.04 c.

Use of.HCTL and HCLL curves.- Question 5.07 d.

Immediate operator actions for loss of Instrument / Service Air -

Question 5.12 DEFICIENCIES a.

HPCI valve operations on initiation / isolation - Question 6.08 b.. Knowledge of Safety Tagging program - Question 6.12 c.

Knowledge of On-The-Spot procedure changes - Question 6.13 d.

Knowledge of control room logs and entries - Question 6.15 2.3 TRAINING PROGRAM COMMENTS A review of lesson plan 301HC-000.00-APG1-00 (Generic Guide)

indicated training was weak in the area of on-the-spot procedure changes. T.he lesson plan did not include an in-depth review of the procedural requirements necessary to make on-the-spot procedurei changes.

Further, the lesson plan also contains the requirement.that the Senior Nuclear Shift Supervisor (SNSS) maintain a control room narrative' log.

The lesson plan and Administrative Procedure OP-AP.ZZ-110

"Use and Development of Operating Logs" did not reflect current practice. Simulator Fidelity problems as noted in attachment 4 were discussed with licensee representatives.

Overall, the applicants were well prepared for the licensing examina-tions.

Licensee provided reference material was adequate and in accordance with the NRC's "90 - day letter."

3.0 ADDITIONAL FINDINGS 3.1 The examiner noted various housekeeping problems in the Diesel Generator rooms. The problems were: 1) missing pipe caps, 2)

missing valve identification tags, and 3) unsecured locking wires. A 2 inch nut was also found in the "A" Diesel Generator room.

The facility stated corrective actions had been initiated to correct the pr:blems noted in the Diesel Generator rooms. All valves were verified to be properly labeled and lock wires firmly attached. The operating staff was reminded to re-install all pipe caps after valve manipulations. The origin of the 2 inch nut could not be determined i

following a visual inspection of the "A" Diesel Generator.

~

_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _. __ --___ - _ -_ ___-____-_ _ _- _ _____ _ __ _ _____

____ _ _ _ - _ - __

_ __

_-_

_-

,

-

..

_ _

_,

-

-f1

<

.

,

'l

,

-

3.2 The examiner noted the Control Room Logs are not maintained in accordance with Administrative Procedure OP-AP.ZZ-110 "Use and i

Development of Operating Logs".. The procedure requires that four (4) narrative logs be' maintained, including the Senior Nuclear Shift Supervisor's Log which was not used, The facility stated that Administrative Procedure OP-AP.ZZ-110 "Use

!

and Development of Operating Logs" would be revised.to clarify the

!

use of the Coiltrol Room logs to current practice.

~

3.3 'An unauthorized person was discovered in the-simulator room during

the operating tests. His oresence was considered to be an

{

I inadvertent intrusion. The examiner stated that the responsibility of examination security is the licensee's.

The facility acknowledged and' stated the simulator room will be verified to be clear of all non-involved personnel during future operating examinations.

.

4.0-Exit Meeting i

L-4.1-ATTENDEES-U. S. Nuclear Regulatory Commission A. Howe, Senior Operations Engineer C. Sisco, Operations Engineer D. Allsop, Resident Inspector Public Service Electric and Gas Company J._J. Hagan, General Manager

.

C. A. Vc.idra, Operations Engineer D. %nson, Manager, Nuclear Training D. Kabachinski, Training Instructor

,

i B. Gott, Principal Training Supervisor L. Catalfomo, Assistant Manager, Operations Training 4.2 SUMMARY COMMENTS On February 10, 1989 a pre-examination review was conducted at.the I

NRC Region I 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 exit meeting.

Access to the facility went smoothly with the excellent support from Health Physics and Security.

The Operations staff was cooperative in maintaining a control room environment which was conducive to the administration of the

operating test.

'

-!

i L

g

,

..

- - _ _

. - - - - -

- - - - _

-_.

_

-

-.

.

,.

.;

5-Th'elstrengths of the operating test noted in Section'2 were discussed.

The final results of.the examinations were not discussed'

at.the' exit meeting. Every effort would be made to provide the-applicant's results_in approximately 30 working days.

The Additional Findings, (Section 3) and the licensee's corrective.

actions were discussed during the exit meeting. The examiner concluded the corrective actions taken by the licensee were satisfactory.

Attachments:

~

1.

Senior Reactor Operator Written Examination and Answer Key.

2.

Facility Comments on Written ~ Examination after Facility Review 3.

NRC Response to Facility' Comments 4.

Simulation Facility Report l

!

l

'

l

_ _ - - _ -

_ - - - - - - - - - _ - _ _. - - - - - - - - - - - - - - - - - - - - - - - -

---. - - - - - - - -

. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

- - - - - -

i ATTACHMENT 1

,

.,

U.

S.

NUCLEAR REGULATORY COMMISSION'

SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

HOPE CREEK REACTOR TYPE:

BWR-GE4 DATE ADMINISTERED:

89/02/14 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 after 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 eir (6)

hours after the examination starts.

f7pg (5)

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY

'33.00 43.42 5.

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%)

43.00 56.58 6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)

76.00

%

TOTALS

"

FINAL GRADE All work'done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature L

i

-

-- - - - - - - -

- - - _ _ _ - _ _ - _ _ _ _ _ _ - _ _ _ - _ _

. _ - - _ _

_

P l-

.

l.

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules' apply:

1.

Cheating on the examination means an automatic denial of your application and could result in more severe: penalties.

i

.2.

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 room to avoid even the appearance or possibility of cheating.

3.

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

4.

Print your name in the blank provided on the cover sheet of the

' examination.

5.

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

I 6.

Use only the paper provided for answers.

'

7.~

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

!

9.

Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

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

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

_ _ _ _ = - _ _ _ _ _ _ _ _ - -

_ _ _

_ _ _ _ _ - _ -

_ _

-

_ _ _ _ - -_- _

.

->

.

V i

.18.

When you' complete'your examination, you shall:

~

a.-. Assemble your examination as follows:

(1). Exam questions on top.

- (2)

Exam aids - figures, tables, etc.

(3)

Answer'pages including figures which are part of the answer.

b.:

Turn in your copy of the examination and all pages used to answer-the examination questions, c.

Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d.

Leave the examination area, as defined by the examiner.

If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

tr i

'

!

-

- _ - -

_-

- - - _ - - _ - _ - -

_ - _ --- -

- _ -- _

- - - - - _ - -

A

.

_.

._

-. _ _ _ _ _.__-____-_- _

,

..

-%,

5. - EMERGENCY AND ABNORMAL PLANT EVOLUTIONS'

' Page' 4

l

_(33%).

.,

. QUESTION 5.01'

' (2. 00) -

'During a' plant' shutdown with Reactor Pressure.at 65;psig it is discovered the Shutdown Cooling System 'cannot be

- placed in service.Jun) the. Recirculation pumps are'not

,

cynilable..

In-accordance with " Shutdown'From Rated Power To Cold Shutdown" Procedure OP-IO.ZZ-004 (Q):

A.:WHAT Reactor. water: Level are.you directed to maintain?

(0.5)

B.WHYis'thislevelrequirbd?:

'(1.0)

,

C.

IDENTIFY the level instrumentation range required to

..

be used to indicate this level.

(0.5)

.

s:

,A

<

!'

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

'

.

.-.

__ _____ _ _______-___ _ _

,pf.

1 52 TEMERGENCY AND BNORMAL PLANT EVOLUTIONS Page. 5 (33%)

L QUESTION 5.02 (3.00)

When all the Remote Shutdown Panel (RSP) transfer switches are plcced.in the EMERGENCY position, trips;and automatic

'atorts'are bypassed on:

FILL IN THE BLANKS A.' Station Auxiliaries Cooling System (SACS) pumps __ and __.

(1.0)

B. Station Service Water Pumps (SSWS) __ and (1.0)

.

C.-Residual Heat Removal Pump __.

.(0.5)

D.

IS the Reactor Core Isolation Cooling Syrtem (RCIC)

turbine TRIP on overspeed. operable when controlled from the Remote Shutdown" Panel? EXPLAIN your answer.

(0.5)

e

.

l (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ -

-

i

.

._

-

_

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ -

r v-

'

U

.

5.

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-Page

'

(33%)

QUESTION 5.03 (3.00)-

.With the plant at 100% power,.the

"A"' Safety Relief Valve opens. HIn accordance with procedure OP-AB.ZZ-121.(Q)

8 Failed Open Safety / Relief Valve":

A. HOW would you' determine if the valve-is being held open electrically? (ie. What Indicator)

(0.75)

B. HOW would you re-close this valve if it.was being held open-electrically? (2' methods)

(0.75).

C. Assuming the valve CANNOT be closed, STATE the two (2)

conditions that REQUIRE the mode switch to be placed in Shutdown.

(1.5)

r

,

d (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- _ _ _ _ -. _ _, - _ _ _ _ _ _. _ _ - __

__

__ _. _ _ _ _

_ __

_ _. - - -. _

-,

.

'5.-

EMERGENCY ~AND ABNORMAL PLANT EVOLUTIONS Page-7 (33%)

QUESTION 5.04 (2.00)

With'the~ plant at power, you'have determined that a Recirculation pump multiple seal. failure has occurred end you order the-pump to be tripped.

In accordance with procedure OP-SO.BB-002 (Q) " Reactor Recirculation System Operation":

A. WHY is the suction valve shut =BEFORE the discharge valve?

(1.0)

B. HOW is overcooling of-the pump casing prevented while-

~

the pump is isolated?.-

(1.0)

e I

!

l i

I a

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

L_

___ _ _ _ _ _ _ _ _ _ _ _ _.

__

- _ - _ _ _..

. * -

.

5.-

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page

(33%)

-QUESTION 5.05 (3.00)

Concerning alarm response procedure OP-AR.ZZ-006 (Q)

"RCIC TURBINE TRIP":

.i A;

The procedure states: If the' turbine has tripped under-Mechanical overspeed, resetting must be done manually at the turbine.

HOW is.a mechanical overspeed trip condition determined from the Control Room?

(1.0)

B. IDENTIFY four (4) RCIC Turbine trip SIGNALS that are NOT a result of a system isolation and do not require manual reset at-the turbine.

(2.0)

(Setpoints NOT REQUIRED)

i'

I 3-i l

l

)

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- _ _ _

_ _ _ _ - _ _ - _ - - _ _ - _ _ _ _ - _ _ _ - - _ _ __-____-_- __ ___- _ _-_

_- - _ - _ - _ - _ _ _. _ ____ -_ __-__

- _

-.

_ _ _ -,

_ _ _ - - _ _ _

.

1.

5.

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page

(33%)

l l

QUESTION 5.06 (3.00)

.

'For.each PLANT CONDITION listed below, IDENTIFY the l

L appropriate PROCEDURE (s) to be utilized.

If none, STATE NONE.

(3.0)

Consider each plant condition separately.

,

!

NOTE: PROCEDURE may be used more than once or NOT at all.

PLANT.CONDITON PROCEDURE

!

A. Turbine trip from 10% power.

1.

OP-EO.ZZ-103 Reactor Building Control

.B. Reactor water level -40 inches 2.

OP-EO.ZZ-100 Reactor C. Suppression Pool Temperature 98 F Scram D.

Drywell Temperature 130 F 3.

OP-EO.ZZ-101 RPV Control E.' Reactor level + 10 inches and Reactor power 57%.

4.

OP-EO.ZZ-102 Containment Control F. Reactor Building Diff Press 0 inches water 5.

OP-EO.ZZ-202 Emergency

Depressurization 6.

OP-EO.ZZ-104 Radioactivity Release i

l l

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

!

- - _ -. - _ _ _ - - - _. _

.

-5.--' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 10

.(33%)

E QUESTION 5.07 (3.00)

Usin, Attachments #4.and #5 answer the following questions.

PLANT CONDITIONS Reactor Pressure 700 psig.

Drywell. Pressure 9 psig.

Drywell Temperature 175 F Suppression Pool Level 38 inches Suppression Pool

' Temperature 155 F-A '.~

WHAT is the VALUE of the Heat Capacity Temperature Limit?

(0.75)

'B.

Is the Heat Capacity Temperature Limit EXCEEDED?

EXPLAIN YOUR ANSWER.

(0.75)

C.

WHAT is the VALUE of the Heat Capacity' Level Limit?

(0.75)

D.

Is the Heat Capacity Level Limit is~ EXCEEDED?

~

EXPLAIN YOUR ANSWER.

(0.75)

a (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _ _ _ - - _ - _ _ _ - _ - - _ _ _ - - -

. _ _ _ _ _. _ - _ - -. _ _ _ _.. _ - _ _ _ - - - _ _ _

l.

,

..

5.-

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS'

Page 11 (33%)

QUESTION 5.08 (2.00)

Using Attachment #6 answer the following questions.

With Suppression' Chamber Pressure at 20 psig

i A.

WHAT is the MAXIMUM Suppression Chamber Temperature that Drywell Spray is permissable.

(0.5)

B.

WHAT is/are the adverse effect(s) if the Drywell Spray

is initiated ABOVE the maximum Suppression Chamber

!

Temperature.

(1.5)

.

~

l

!

i I

l (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- -

_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _

- _ _ _ -

__

_ _.

.. - - _ _.

_ _ _ _ _ _.

.

5.-

EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page 12 Ll (33%)-

,

l (3.00)

QUESTION 5.09

Procedure OP-EO.ZZ-100 ~(Q) " Reactor Scram" contains an

Oparator. Caution that. prohibits placing an ECCS system in.the manual mode ~unless either of two (2) conditions

.cro met.

A.

, IDENTIFY the two.(2); CONDITIONS.

(1.5)

> FILL-IN'THE BLARKS-B.

The conditions may be verified by a check'of at l' east

' indications.- (2 blanks)

(1.5)

r I

d (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

____ - __-__

-_-__-______-__- -_ __ ____ _ _ _ _ _- _ __ -

__--

- - _ _ _. _ _ _,.

_. - _ _ _

'5,.

..

.

i 5.*

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-Paga-13 (33%)-

l l

.

' QUESTION 5.10 (2.00)

,

'Concerning Procedure OP-EO.ZZ.101 (Q) " Reactor / Pressure Vessel (RPV) Control".

Step RC/Q-45 directs 'When-SLC has.

injected the Cold Shutdown Boron Weight (Less than 1600

. Gallons - Remaining in the. SLC Tank) THEN Exit RC/Q.

PER this procedure step, should the operating SLC pump (s)

.bn secured at this time?

(2.0)

EXPLAIN YOUR ANSWER.-

-

l r

u

.

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- - _ - -. _ _ _ - _ _ _ _ _

-___-_-_-______-_________- - - - -

E

&

5.

EMERGENCY AND' ABNORMAL PLANT' EVOLUTIONS-Page'14 (33%)

-QUESTION 5.11 (2.00)

During 100% power operations ~,:the Off Gas Recombiner Train

' '!

automatically isolates.

In accordance with procedure.

OP-AB.ZZ-128 (R) "Off Gas System Malfunction":

. Assuming no scram condition;is reached,' IDENTIFY four (4)

Immediate Operator Actions required to be.taken.

(2.0)

l g.

\\

i i

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

i I

-__-________________-____________-___

_ _ _ - _.

. _ _ _.

_ _ _ _ _ -, _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ __ ___ __

--

_

. - - -

-- - -_

_ _ _ _ - _ _ - _ _ - - _ _ _ - _ _ _ _ - - _ _ _ _ _ - _ - _. _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _,_ _ _ _ _ - _ _ - - _ _ _. _.

l

,

.

- 5; EMERGENCY AND-ABNORMAL' PLANT EVOLUTIONS

'- Page-15 (33%)

.p.

?

QUESTION

'. 5.12 '

(2. 00)^

-'

.During.100%' power operations, the' plant experiences

'

decreasing Instrument Air header pressure.

In accordance-with procedure.OP-AB.ZZ-131 (Q)'" Loss of Instrument

'f Lair and/or' Service. Air" A4' IDENTIFY the condition (s) in which you would order the Reactor to'be scrammed.

(1.0)

.B.l.WHY should the. reactor be scrammed?

(1.0)-

>

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

-_-Km---___--_---- - - _ _ - -. _ _ _ - - - - - - - _ - - - -. -

--_ - - - _.-

- - - -.

.N,

.

, 5.-

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 16 (33%)

QUESTION 5.13 (3.00)

,Using Attachment #7:-

The plant is operating at power when a. Recirculation Pump trips.

Power is 1600 MWT and Total Jet Pump Flow indication is 38 million'1b/hr.

WHAT ACTIONS are required per procedure OP-AB.ZZ-112

" Recirculation Pump Trip" and WHY are these actions rcquired? SHOW ALL WORK.

.(3.0)

lu

,

.

l L

(***** END OF CATEGORY 5 *****)

._

_ _ -.

.

,6.

PLANT CYSTEMS (30%) AND PLANT-WIDE GENERIC Page 17

,

RESPONSIBILITIES (13%)

{

I l

.

(

Al TE M T/osu Al L,v

&cgg

!

h

'a (*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _

_ _ _ _ - _ _

___

_ _ _

- _ _ _ _ _ _ _ _

. _ -

. - _ _ _ -

.__

_

. _ _ _ _

o (.

..

6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 18-

-RESPONSIBILITIES (13%)

. QUESTION 6.01 (3.00).

.USING Attachment #1, answer the following questions concerning the Residual. Heat Removal System (RHR).

RHR Loop

"A" is in-Shutdown cooling mode.

The other RHR loops are in standby per OP-SO.BC-001 "RHR System Operation":

A. Reactor water level' decreases to the auto scram setpoint.

(Assume no operator action)

L IDENTIFY ALL valves (By number) that receive a SIGNAL to CLOSE.

(1.0)

(NOTE: Consider all'RHR loops)

B. Assume Reactor water level decreases below the auto scram setpoint and continues to decrease.

(Assume-no operator action)

1. At WHAT Reactor water level will the LPCI Mode of the RHR system initiate?

(0.5)

2.

WILL the RHR loop "A" inject in the LPCI mode?

If so WHY, if NOT, WHY NOT.

(1.5)

u

.

l

.

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

i

_-

.

. - -

. _ -

L

'

.. '

.

6.

' PLANT SYSTEMS ' (30%). AND PLANT-WIDE GENERIC Page 19 RESPONSIBILITIES (13%)

l QUESTION

<6. 0 2 -

(2.00)

l-Concerning the High Pressure Coolant' Injection (HPCI) system:

"

A.-IDENTIFY the two (2) indications'that Flow Indicating

' Controller FIC-R6000 provides when in the Automatic Mode.

(1.0)

l B.' IDENTIFY the signal (s) and setpoint(s) that initiates an AUTOMATIC start of the system.

(1.0)

,

c

.

!

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.i

_ _ - _ _

.

..

l-6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 20 RESPONSIBILITIES (13%)

'

,

QUESTION-6.03 (1.50)

l A. IDENTIFY the signal (s) and setpoint(s) that AUTOMATI(: ALLY start the Core Spray pumps.

(1.0)

-

:B. IDENTIFY the. signal and setpoint that' OPENS the

,

injection valve (F005A) when the MANUAL INITIATION pushbutton is armed and depressed for Core Spray yump

"A".

(0.5).

s.

e (*****

CATEGORY 6 CONTINUED ON NEXT PAGE * * * * *)

, - - - _ _ _ - _ - _ _ _ _ _ _ _ _

_

.

,

6.-

PLANT SISTEMS (30%) AND PLANT-WIDE GENERIC Page 21:

RESPONSIBILITIES-(13%)

.

l

'

QUESTION 6.04 (2.50)

Concerning the Automatic Depressurization System (ADS):

A. WHAT initiates the High Drywell Pressure signal bypass timer?

(0.75)

.

f B. WHY is.the High Drywell Pressure signal bypassed?

(1.0)

From WHAT accident (, ark

.

does the bypassing of the High Drywell C.

Pressure signal afford protection.

(0.75)

i L

!

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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

_ _ _ _

. _ _ _ _ _ _ _ _ _ _ ___

_.

_

._

_ _ _ _. - __

_

-,_

'

.g 6.

PLANT SYSTEMS (30%)'AND PLANT-WIDE' GENERIC Page'22'

<

. RESPONSIBILITIES (13%):

'

,

i

QUESTION-6.05 (2.00)

'A. IDE'NTIFY'the signal (s) that initiate (s) the End-of-Cyle Recirc Pump Trip.

(1.0)

- B.

IDENTIFY the SYSTEM.that supplies.the signal (s).

(0. 5).

C. WHEN is this trip AUTOMATICALLY BYPASSED.

(0.5)

.

I e

<

!

l a

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _

_ _ _ _ _ _ _ _

_ _ _ _

_

. - _ _

_

__ ;

--

- - - -.

.

-

_

-_

.

...

6.

PLANT SYSTEMS - (30%). AND ~ PLANT-WIDE GENERIC '

Page'23 RESPONSIBILITIES (13%)

)

QUESTION, 6.06 (2.5d)

Tha. Redundant Reactivity Control System-(RRCS) has

' initiated AUTOMATICALLY.

(NO OPERATOR ACTION)

A. WHY is the AUTOMATIC start of the Standby Liquid Control System delayed.for.,3.9 minutes?-

.(1.0)

-B.

IDENTIFY the signal (s) that MUST be present after the,3.9 minute time delay to permit.'the AUTOMATIC start of the Standby Liquid Control System.

(1.5)

,

b.

.

'a (*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

- - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ - _ _ _ _ _ - - _ _ _ _ _ _.

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

-. _.

__

_

_ _

__

-.

_

____ _

_ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ - _.

-_

- _ ___

' '.

.

'

6.

PLANT" SYSTEMS-(30%) AND PLANT-WIDE GENERIC Page 24 l

RESPONSIBILITIES (13%)

l-QUESTION 6.07 (3.00)

Concerning the Recirculation Flow Control System:

A. Recirculation pump speed is limited - (Runback)

to 30 % when:-

1. Total feedwater. flow is less than (0.33)

2. Reactor water level is less than (0.33)

3. Condenser. vacuum is less than 5.8" Hga, and'two (2)

or less Circulating Water pumps running with a

trip signal present.

(0.33)

B. Recirculation pump speed is limited (Runback)

to 45% when:

1. Reactor water level is less than concurrent with a trip signal.

(0.5)

2. Total'feedwater flow greater than concurrent with a trip signal.

(0.5)

C. IDENTIFY the signal (s) that must be matched (" nulled") prior to RESETTING the runback (s).

WHY is matching the signal (s)

necessary?

(1.0)

>

.

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

.-_-.______ __ _ _

_ -

A

___

.

6.

PLANT' SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 25 RESPONSIBILITIES (13%)

i

. QUESTION 6.08 (3.00)

-

Using Attachment #2 and Attachment #3, answer the following questions concerning the High Pressure Coolant Injection System (HPCI).

A.

The system valve alignment is in NORMAL STANDBY with the plant at power when' Reactor water level decreases to-below the auto start setpoint.

(Assume NO OPERATOR ACTION)

1.

IDENTIFY all the valve (s) that receive an open signal as a part of the initiation sequence.

(1.0)

2.

IDENTIFY all the valve (s) that receive a close signal as a part of the initiation sequence.

(1.0)

B. - The HPCI system is injecting into the reactor when level reaches + 55 inches and Drywell pressure is 2.0 psig.

(Assume NO OPERATOR ACTION)

IDENTIFY any valve (s) that CLOSE.

(1.0)

!

i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

!

. - _ _ _ _ _ _ _ _ - _ _ _ _ _ _

_ - _ _ _ _ _

- __

_.

-____. _-.

_ __

-

_ _ _ _ _ _

-

_ _ _.

_ _ _ _ _ _ - - _ _

$

i.

..

6.

4 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 26 RESPONSIBILITIES (13%)

b l-

,. QUESTION

~6 09 (2.50)

.

During power operations you are informed a 4.16 KV Emergency Bus (Loss of Voltage) channel TRIP SETPOINT was found to be set at 3257 volts.

i NOTE: FULLY REFERENCE ALL TECHNICAL SPECIFICATIONS IN YOUR-L.

ANSWER..

l A.

WHY is the channel inoperable?

(1.25)

B.

WHAT ACTION (s) are required per Technical Specifications?

(1.25)

r:

a (*****

CATEGORY 6 CONTINUED ON NM T PAGE *****)

_

_ -_. -_- _

_ _. _ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _, _ - - _ _ - - - - - - -

-

..

_. - _ _ _ _

- _ _ _ _ _ _ _ _ _ _ _ _ -

'

.

n

.

6.:

' PLANT SYSTEMS'(30%) AND PLANT-WIDE' GENERIC Page 27'

[-

-RESPONSIBILITIES (13%)

j; I

QUESTION 6.10 (2.00)

l 4 The plant is in STARTUP.

ALL prerequisites have b3en met for taking the Reactor Mode switch'to RUN whnn you receive a report that the HPCI Outboard Steam Supply Valve.(HV-F003) is inoperable.

l

' NOTE:

FULLY. REFERENCE ALL APPLICABLE TECIINICAL SPECIFICATIONS'

-l IN YOUR ANSWER.

l MAY the Mode switch be placed in the RUN position with.

the valve inoperable? BRIEFLY EXPLAIN your answer.

(2.0)

'

i

!

l l'

l

?

'

l

!

I (*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

I

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.

_ _ _ - _ _

_ _ _ _ _ -

..

_ _ _ - _ _ _ _ _ _ _ _

)

..

,

6..

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 28-

j.'

RESPONSIBILITIES (13%)

!

l

\\

QUESTION 6.11 (3.00)

Concerning the Diesel. Generators:

A.

The Diesel Engine controls arc in the " EMERGENCY TAKEOVER" Position:

IDENTIFY the signal (s) that will Automatically START the Diesel Generator.

Setpoint(s) NOT REQUIRED (0.5)

(Assume NO OPERATOR ACTION)

B.

The Diesel Generator is controlled from the Control Room and has automatically started following a loss of voltage on.the emergency bus concurrent with and ECCS actuation signal.

IDENTIFY All Diesel Generator Trips that are OPERABLE.

Setpoints NOT REQUIRED.

(Assume NO OPERATOR ACTION)

(2.5)

e l

l I

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ -

, _ _ _ _ _ _ _ _ _ _

_

- _ _ _ _ _ _

_ _ _ _

-. _ _ _ _ _. _ _ _. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _. _ _ _ _ _ _. -. _ _ _ _ _

i

,:

.

6.-

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC-Page 29-RESPONSIBILITIES-(13%)

QUESTION 6.12 (2.50)

Concerning Procedure SA-AP.ZZ-015 (Q) " Station Safety-Tcgging Program".:

.A. WHO is the ONLY person authorized to request a tag or Group Tag to be removed?

(0.5)

.. B. IF this person is unavailable and the tagged equipment is urgently needed in' service, IDENTIFY the individual (s)

required to authorize the tagging release.

(1.0)

C. MAY equipment be operated that.is YELLOW tagged for more than one (1).. individual?

EXPLAIN your answer.

(1.0)

I

!

L I

.

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

_-_______-____ _ ___

a

- - _ _ _ _ _ - - _ _

- - _

,

.

6.

' PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC:

-Page-30 RESPONSIBILITIES (13%)

l QUESTION 6.~ 13.

.(2.50)

Concerning. Procedure SA-AP.ZZ-032-(Q) " Review and Approval of L

' Station Procedures and Procedure Revisions":

A.'

IThreel(3) types of procedures in which revisions

.SHALL'NOT be implemented as On-the-Spot Changes are

, and

.(1.5)

,

.

B..

On-the-Spot Changes must.be implemented within of approval..by the SNSS/NSS.

.(0.5)

C.

On-the-Spot Changes shall undergo the same review and approval as a permanent. revision within (0.5)

.

e

..

l (*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l

. - - - _ - - - - - _ - - - - _ - _ - - - _ _ _ _ - - _ _ _ _ _ _ - _ _ _ -

-

- - - - _ _ _ _ _.

. _ _

_

..

.

6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 31 RESPONSIBILITIES (13%)

QUESTION 6.14 (2.50)

In accordance with SA-AP.ZZ-049 (Q) " Conduct of Fuel Hnndling and Core Alteration", IDENTIFY the MINIMUM R fuel Floor Crew.

(2.5)

}

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

- _ _ _ _ _ -.

_ _ _ _ _ _

.

6.

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 32 RESPONSIBILITIES (134)

QUESTION 6.15 (3.00)

In accordance with procedure OP-AP.ZZ-110 (Q) "Use and Development of Operating Logs":

A.

The overall status of the Radwaste systems is recorded in

'the Log.

(0.75)

B.

ALL Operations Logs in use during a shift shall be reviewed i

by (TITLE).

(0.75)

-C.

Calls to the NRC concerning significant events shall be l

recorded in the Log.

(0.75)

D.

Implementation of the Emergency Plan is recorded in the Log.

(0.75)

a

!

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

__

_ ___ _ _,

_.__.__ _ _

_

,

.'

.

'6.

PLANT SYSTEMS'(30%) AND PLANT-WIDE GENERIC Page 33 RESPONSIBILITIES (13%)

.l l

QUESTION 6.16 (2.50)

l Using the furnished Event Clast.ification Guide, CLASSIFY cach of the following events.

Consider each cuent separately A.

Reactor water level is -129 inches and decreasing.

(0.5)

B.-

Loss of Alternate Shutdown Cooling and reactor pressure 150 psig.

(0.5)

C.

.The SNSS/EDO judgement indicates probable fuel failure based on Off Gas readings with the plant at power.

(0.5)

D.

Reactor water level is - 10 inches and decreasing, Drywell pressure is 6.8 psig and decreasing, Reactor Building radiation level is 2.7 rem / hour and increasing.

(0.5)

E.

Control of the plant has not been established at the Remote Shutdown Panel within 15 minutes of Control Room Evacuation.

(0.5)

a

!

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

- _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _

_. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _

'

.

6.

-PLANT SYSTEMS (30%)-AND' PLANT-WIDE GENERIC-Page 34 RESPONSIBILITIES (13%)

-QUESTION 6.17 (3.00)

Using.the furnished Event Classification Guide,' IDENTIFY'

tho gRe orting requirements for each of the following sysnts.) If NONE are required, STATE NONE.

8 40 A.

.An accidental criticality during refueling.

(0.75)

B.

Inadvertent start and injection of th.'. HPCI system

,

during plant operations.

(0.75)

C.

Presence'of loose parts discovered in-the reactor.

(0.75)

D.

A Reactor Scram caused by low reactor level during a plant startup.

(0.75)

-l

'

-

d (***** END OF CATEGORY 6 *****)

(********** END OF EXAMINATION **********)

m-

-.

.

,

L Sh ' EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS

_Page-35 (33%)-

p-

-

,

' ANSWER-5.01 (2.00)

'A.J+80 inches

.

_(0.5)

iB.ETol provide natural circulation (1.0)

.C;EShutdown Range'(LI-R605-B21)

(0.5)

L

. REFERENCE

IJ?

302HC:19 (112G-00) book 13 page 15'

OBJ 7.

KA1 295001K011,(3.5/3.6) 295001G007-(3.3/3.6)

295001K101 295001G007

..(KA's)

' ANSWER 5.02 (3.00)

A. B and D (0.5 each)

B. B and D (0.5 each)

C..B (0.5)

D.?YES (.25) (Backup) Mechanical overspeed trip 1(125%) is still provided..(.25)

'

REFERENCE LP-302HC/2:25 112H book 13 page 8 OBJ

-KA 295016AK201 (4.4/4.5)-

295016K201

..(KA's)

ANSWER 5.03-(3.00)

,

A. The "SV ENRGZ" light is lit (.75)

'B. Cycle the OPEN/CLOSE pushbuttons (.375) Remove the fuse (s) (.375)

Reduce pressure set (.375) (Any 2 0.375 each)

C. AFTER 2 minutes (.75)

OR'

Suppression Pool Temp. 110 F (.75)

<

(*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

-

- _ _ - -

_ - - _ _ _ _ _ - _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _ - - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ -

__ _

-,

.

5.-

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 36 (33%)

. REFERENCE LP 302HC/2:25 (029-04) book 4 page 37 OBJ

KA 239002A203 (4.1/4.2) 295026EK3.05 (3.9/4.1)

239002A203 295026K305

..(KA's)

i

- ANSWER 5.04'

(2.00)

A. The discharge valve is designed to operate under high differential-pressure (1.0)

OR The suction valve is not designed to operate under high differential pressure (and may not operate) (1.0)

B. By isolating the seal water purge for the pump seals-

"(1.0)

REFERENCE LP 320HC:19 (019-04) book 3 OBJ

KA 202001A210 (3.5/3.9) 202001G010 (3.5/3.7) 295001G007 (3. 3/3. 6).

202001A210-202001G010 295001G007

..(KA's)

ANSWER 5.05 (3.00)

f A.

When the OPEN-ACTUATOR motion is inhibited (1.0)

B. Reactor High level Manual High'Turb Exhaust q

Pump suction pressure low Electrical 'overspeed (ANY 4 0 0.5 each)

REFERENCE LP 302HC:25 (030-05) book 4 page 27,28 (procedure referenced)

OBJ 5&9 L

KA 217000A402 (3.9/3.9) 217000G008 (3.8/3.6) 295031A105 (4.3/4.3)

295031G006 (4.1/3.9) 295031G009 (4.1/3.9)

g 217000A402 217000G008 295031A105 295031G006 295031G009

..(KA's)

(*****

CATEGORY 5-CONTINUED ON NEXT PAGE *****)

_ - _ _ _ _ _ - - - - _ _ _ _ _ _ _. _.

_ _ - - _ _ _ _ _ _ _ _

-

.,:

.f

-?:

.

'

<

5. - EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 37;

-(33%)

,

e

" ANSWER 5.06 (3.00)

L

/A. NONE-B.

C.

'D.

NONE.

E.

3'

F.

(6:at'O.5 each)

' REFERENCE.

LP EOP lesson plans book 14 OBJ State entry conditions.

KA_ L295026G011 (4.4/4.6) 295028G011 (4.2/4.4)'295031G011 (4.2/4.6)

295026G011

' (4.4/4.7)'295009G011 (4.3/4.5)

295037G011 295028G011 295031G011 295037G011-295009G011

..(KA's)

ANSWER 5.07 (3.00)

A '.

170:F(+2/-2.F) (0.75)

- B.'

NOf (0.375), The actual temperature (155 F) is less than the limit - (0.375) - (of 170 F)

C.. 40(+2/-2)Linches (0.75),

-D.

YES (0.375) The' actual level is less than the limit (0.375)

REFERENCE

,

.LP 302HC/2:25 (125B-03) book 14 page 7,8

'OBJ

KA'

_295030EK103 (3.8/4.1)

295030EA201 (4.1/4.2) 295030G012 (3.7/4.4)

295030K103 295030A201 295030G012

..(KA's)

t ANSWER 5.08 (2.00)

1..

170 F(+2/-5 F)

(0.5)

2.

May exceed the design negative pressure (0.75) of the suppression chamber (.75)

OR j

(A containment depressurization rate that) exceeds the relief

!

capacity of the drywell (0.5) and reactor building (0.5)

. vacuum' breakers (0.5).

(may lead to exceeding design negative pressure of suppression chamber)

j (*****

CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ - _

_

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _

<-

..

5.

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS'

Page 3"8

^

(33%)

>

..

REFERENCE LP 302HC/2:25 (126A-03)~ book 14 page.9,10 OBJ

KA-295024EA111 (4.2/4.2)'295024EA204 (3.9/3.9) 294001A108 (3.1/3.6)

295024G007'(3.6/3.9)

295024A111.

295024A204 295024G007 294001A108

...(KA's)

ANSWER'

5.09 (3.00)

A.1, Misoperation in the automatic mode.is confirmed (0.75)

'A.2.-

Adequate core cooling is assured.

(0.75)-

B.

(By at least) two (2) -(0.5), independent (1.0)

REFERENCE LP 302HC/2:25L(122-03) book 14 page 11 OBJ-4 KA 295006G007 (3.8/4.1)

295006G007

..(KA's)

ANSWER 5.10 (2.00)

NO (0.5) The contents of the tank are injected until the operator is_ DIRECTED to terminate boron injection. (1.5)

(Manually at 325' gallons in the tank or confirm automatic trip' of the SLC pumps at 325 gallons.) (NOTE 19)

' REFERENCE LP 302HC/2:10 (124B-03) book 14 page 24 OBJ.9 KA 295037A104 (4.5/4.5) 295037K305 (3.2/3.7) 295037G012 (3.9/4.6)

295037A104 295037K305 295037G012

..(KA's)

' ANSWER 5.1 (2.00)

)

1. Reduce reactor power (maintain condenser vacuum >7.5 Hg A.)

.

2. Maximize circulating water flow to main condenser 3.

Place standby steam jet air ejector in service 4.. Ensure all appropriate automatic actions are complete.

(4 0 0.5 each)

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - - - - -

_. - - - - _

_J

.,_

"

.

5.

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 39 (33%)

REFERENCE LP 303HC-000.00-114, Procedure OP-AB.ZZ-128 OBJ

KA 295002G010 (3.8/3.7)

295002G010

..(KA's)

ANSWER 5.12 (2.00)

A.

If more than one control rod drift occurs (1.0)

B. To ensure rods will insert uniformly (1.0)

REFERENCE LP 302HC-000.00-114 Procedure OP-AB.ZZ-131 OBJ 1,3 KA 295019AK201 (3.8/3.9) 295019G010 (3.7/3.4)

295019K201 295019G010

..(KA's)

i l

ANSWER 5.13 (3.00)

1600MWT/3293 MWT =

%

wer (0.5)

38 million 1b/hr/100.0 mlb/hr = 38% core flow (0.5)

MUST drive rods in to reduce power to less than 40% (0.5)

and Monitor for power oscillations (0.5)

because Ensures the reactor is not operating in a region of the high power / low flow instability. (1.0) (40% power limit is based on the instability regions defined in the Hope Creek Power to flow Map)

REFERENCE i

LP 302HC-000.00-114 Procedure OP-AB.ZZ-112 OBJ

KA 295001K104 (2.5/3.3) 295001A201 (3.5/3.8)

295001K104 295001A201

..(KA's)

(***** END OF CATEGORY 5 *****)

_ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ - _ -.

_ _. -.. - _ - - _ - _ - - _

.-

v.

i l6.

' PLANT 1 SYSTEMS-(30%)-AND PLANT-WIDE GENERIC Page 40 RESPONSIBILITIES-(13%)

ANSWER 6.01 (3.00).

"A.

(Eight valves) l F022, FO23, F040, FO49, F015A, FO15B, FOO8, F009

.(EIGHT e 0.125 EACH) (F079A,B,80A,80B also close but are not on the attachment)

-

B. l'-129' inches.(0.5)-

'

2. NO (0.25) - Pump will not start (or operate) without a-suction flow path (1.25)

(Valves FOO4A,8,9 are all closed)

REFERENCE LP 302HC:351(028-05) book 4 page 59,68,69 OBJ 9 & 9b KA 203000K114 (3.6/3.7) 203000K401 (4.2/4.2) 295031EK205 (4.2/4.3)

205000K604 (3.6/3.6) 205000A310 ( 3. 2/3.1)

203000K114 203000K401 295031E25 205000A301 205000K604

..(KA's)

ANSWER 6.02'

(2.00)

A. FLOW (x100)-Indicates actual HPCI pump discharge flow (0.5).

.%STPT (x10)-Indicates desired flow rate (0.5)

B. Reactor water low level (Level 2)

-38 inches (0.5)

.Drywell pressure equal to/ greater than 1.68 psig.

(0.5)

REFERENCE LP 302HC/2:10(026-05) book 4 page 29,32 OBJ 3,8 KA 206000K407 (4.3/4.3) 206000A106 (3.8/3.7)

206000K407 206000A106

..(KA's)

ANSWER 6.03 (1.50)

e A. High drywell press >1.68 psig (0.5)

Low-Low reactor level (Level 1) -129 inches (0,5)

B. Reactor pressure (0.25) less than 461 psig.(0.25)

}

!

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

,1 l'

- _ _ _ -

-_

- _ _ - - _ - - _ _

, -

a(

>

...

aO6.- ^ PLANT SYSTEMS (30%):AND PLANT-WIDE GENERIC:

Page 41'

y_

. RESPONSIBILITIES (13%)

,

K

.

p. REFERENCE LP-302HC/2:25L(027-04) book'4 page-30,34 OBJ-3,4 KA 209001K408.(3.8/4.0) 209001A403..(3.7/3.6)

209001K408

.209001A403f

..(KA's)

I. ANSWER

'6.04 (2.50)

A. ReactorLvessel: low level (-129 inches)'

(0.75).

B." Allows the ADS to actuate (.50).without1the High Drywell'

pressure 1. signal present.(.50).

C. Steam line-break.(.375) outside of.the drywell (.375).

REFERENCE

,LP'

302HC:35(025-03) book 4 page 12 (029-04) book 4 page 18,19 OBJ. 4.-(029-04)

KA 218000K501 (3.8/3.8) 218000K103 (3.7/3.8)

218000K501 218000K103

..(KA's)

' ANSWER 6.05

. (2.00)

-l A. :

1. Turbine stop valve closure f

2. LOW EHC oil pressure (TCV' closure <530psig)(ICV l-OICLOk"E)

-

~B.:

Reactor. Protection System lo,0*E He D8f4- (o.5)

C.,

<30% as sensed by 1st stage turbine pressure-1(0.5 each)

REFEREr0E

)

T *-

302HC:19 (019-04) book 3 page 57 OBJ

-KA.

212000K103 (3.6) 202001K413 (3.7/4.0)

212000K103 202001K413

..(KA's)

,

L ANSWER 6.06 (2.50)

l

A. Provides sufficient time to attempt other methods of power reduction prior to injection SLC.

(1.0)

B. APRM's NOT Downscale (or INOP) (0.5) AND High Reactor Pressure

. (Sealed in) (0.5) OR Low Reactor Level (NOT sealed in) (0.5)

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

- _ _ _ -

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. :

-_

. _ _. - _

.. - _

_

-.

.

__

__ -. -_,

if

.ti ns.

I s

06.

-PLANT SYSTEMS'(30%).AND' PLANT-WIDE GENERIC'

Page-42 RESPONSIBILITIES (13%)

l

>

REFERENCE q

LP'

302Hc:24 (024-03)' book _3 page.18.'&l9:

'OBJ

'S &-3b.

KAL 211000A308-(4.2/4.2).

'211000A308

..(KA's)'

ANSWER i6.07 (3.00)

A.

1.

20%

2.

12.5. inches 3. Circulating' water pump (3.9.0.333 each)

B.

1.

30 inches (0.25) feedwater pump (0.25)

2.

85% (0.25) Secondary condensate pump-(02.5)

. C. ' (Speed) Demand - (0.25) and ' Actual (Speed) (0.25)

' Prevent an uncontrolled increase in recirculation pump speed (0.50)

REFERENCE-LP-302HC:24 (-020-05) book 3 page 15,17,18 OBJ 3b & 9.

KA

.-202001K416 (3.3/3.6)

202001K416

..(KA's)

ANSWER 6.10 8 (3.00)

,

.:

A.1 Eight (8) valves: HV-F001, HV-8278, FV-4880, FV-4879, (OPEN)

HV-F004, HV-F007, HV-F006,.HV-F059 (Eight 0 0.125 each)

A.2 Five (5) valves: HV-4922, HV-F008, HV-F011,HV-F028,HV-F029-(CICSE)

(Five @ 0.2 each)

-

B.1 Four (4) valves: FV-4880, HV-F006, HV-8278, HV-F012 (Fo r 9 -Ov2 each)

-y 0.16'dACW REFERENCE LP 302HC/2:10 (026-05) book 4 page 98,99,101 OBJ 2 ', 1 1, 1 3 J KA 206000K407 (4.3/4.3) 206000A101 (4.3/4.4) 206000A404 (3.7/3.7)

206000K407 206000A101 206000A404

..(KA's)

,

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

.

I

m

.-

.

- 6.

' PLANT' SYSTEMS (30%)cAND-PLANT-WIDE GENERIC Page 43 RESPONSIBILITIES (13%)

' ANSWER ~

6.09 (2.50)

A.

TRIP Setting is greater than allowable (.75)

per TS Table 3.3.3-2 (0.5)

B. Table 3.3.3-1 (ACTION 36) (0.5) requires t!.c inoperable channel placed in the tripped condition within one (1) hour (0.75)

REFERENCE LP 302HC:35(110-02) book 13 TS pg 3/4 3-32,34,35,37 OBJ 3,

6,

KA 262001G011 (3.1/3.9) 262001G005 (2.9/3.9)

262001G011 262001G005

..(KA's)

ANSWER 6.10 (2.00)

NO (0.5) Specification 3.0.4 prohibits entry into an operational conditon unless the LCO is met without reliance on provisions contained in the ACTION requirements. (1.5)

REFERENCE LP 302HC:35 (110-02) book 13 TS pg 3/4 0-1 OBJ

KA 206000G011 (3.7/4.4) 206000G005 (3.6/4.3)

206000G011 206000G005

..(KA's)

ANSWER 6.11 (3.00)

A.

Loss of Power to (Emergency) Bus (0.5)

B.

1. Engine Overspeed 2.

Generator differential current 3. Generator Overcurrent 4.

Bus differential current 5.

Low lube oil pressure (5 0 0.5 each)

l (*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

'

_ _ _ _ _ _ _

_ _ _ _

- _ - - - - _ _

'

i 2;

s.

-

.

&

6.

PLANT SYSTEMS-(30%)'AND PLANT-WIDE GENERIC Page 44

. d RESPONSIBILITIES (13%)

,

.l

' REFERENCE

~l

'i LP:

~302HC:2:25_(068-03) book.9 (T.S. page 3/4 8-7)

f

,

OBJ-

3,7

'

- KA -

264000K402 (4.0/4.2) 264000K408 (3.8/3.7)

j 264000K402 264000K400

..(KA's)

j-ANSWERL 6.12 (2.50)

A. The person named'on the tag or Group tag (0.5)

B. The. named. person's immediate supervisor -(0.5)

.AND Gnneral Manager OR Operations Manager OR Operating Engineer (1 of the 3 for 0.5)

(1.0 total)

'C. LYES (0.5) With permission secured from all persons named on the tags (0.5)

OR YES'(0.5)~With written assurance (0.25) from the person requesting'

the equipment beLoperated attesting that all persons named on the tags have given their permission (0.25)

REFERENCE LP 301HC/2:25-(APG1-00) book 13 page 7,12,13 OBJ

= H1, G3 -

KA 294001K102 (3.9/4.5)

=294001K102

..(KA's)

7 ANSWER 6.13 (2.50)

A. Station Admin Department Admin Emergency Plan Implementing Security Plan Implementing Fire Protection Implementing (any 3 @ 0.5 each)

~B. 24. hours (0.5)

lC. 14 days

- (0. 5).

1'

l l

l

1-(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

El___ ____

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _ _ _ _ _

-.

, - _

d

t.

[6. IPLANT SYSTEMS (30%)'AND PLANT-WIDE GENERIC Page 45 RESPONSIBILITIES (13%)

REFERENCE LP Procedure- (Attachment'1, page 11and 3 of.16) and page 6 OBJ Licensee did not. train on this procedure

' KA 294001A103 (2.7/3.7)-

294001A103

..(KA's)

' ANSWER-6.14 (2.50)

1. Refuel Floor Supervisor 2. Refueling SRO 3.. Refueling platform ~ operator 4. Reactor Engineer 5. (Qualified) Radiation Protection Personnel (5 0 0.5 each)

REFERENCE LP 302Hc:36 (113B) book 13 page 8 OBJ 1c KA 294001A103 (3.7)

294001A103

..(KA's)

.

ANSWER 6.15-(3.00)

A. Shift. Support' Supervisor B. Senior Nuclear Shift Supervisor i

'

C. Control Room (Narrative)

D. Senior Nuclear Shift Supervisor (,7d oA Coo 1xot, Room (pggggqffgg (o,7f} ~

(4 0.75.each)

REFERENCE

- LP 301HC/2:25 (113-01) book 3 3 page 6 OBJ El KA 294001A106 (3.4/3.6)

294001A106

..(KA's)

L f

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

-

a

. - _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ -

..

.-

6.-

PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC

' Page 46 RESPONSIBILITIES,(13%)

n.

ANSWER.

6.16 (2.50)

A'.

Site Area Emergency B.

Alert C.

Unusual Event D.

. General Emergency

'

E.-

Site Area-Emergency (5 0 0.5 each)

REFERENCE-LP-Section 2,4,5,6,8'of guide (book 30)

.OBJ Lessons plans not provided KA 294001A116-(2.9/4.7)

294001A116

..(KA's)

ANSWER 6.17 (3.00)

A.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months report B.

4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report o A-l Host kdfdVI C.

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months report D.

4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report REFERENCE LP Guide Section 18

.,

OBJ KA 294001A116 (2.9/4.7) 295006G002 (3.0/4.5) 206000G003 (3.1/4.4)

294001A116 295006G002 206000G003

..(KA's)

I

'

s (*****

END OF CATEGORY 6 *****)

(********** END OF EXAMINATION **********)

I

!

_

. _ _ _

_ _ - _ - _ - _ _ _ -

.

Cff L-/

.1

.

O o

.

t

==*' W 5E N

o

-

o e

'

-

.j

e

.

3:

-

-(

_.

o c

-

m o

a

_ei

..

o a.

();

(

==

o

t a

l

,.-

'

O un oustts roose Ix is

..

=E

"

.:t

g

.

-

.

e.

,.

i ee

-

=

,

.o..

"2.h a.,

-

.

u o

o

-

o s-

.e q u

-

-: f n:

a o

z u

2 2,-

z

d

.o

.o i

i g

"

_.

!

Ej5E!

3f55a!

h.! j-

=

.__

s

-

e_

=

.

e mee:g e..g(J)E a

.

1 2:e

'

n

-

W 4 et

" "

t

.

...

Os

.!!

=

H 15! agoyg, g!

CO

=

.

E:c*

5 5 3CH 3t!5 h<l;C

"

s

,'.

99g

'"E

-

t

"

I

>-

.

si E /yiB-mE=t ( jPC E85 sat g

Q

o.

---

.

r

-..

-

o

." * s is4_3n s=

s

_; ~

-

.

E

. css

!

m!.

- !

"

(i m

i

'G

.

n n

-

e

-

.

"M Si.

/

,2=

.

u.

-5! !

$$

[hh

$3t

h

/

x

':

__ _

%5

.

I, C g

]~

t >85

~~ I E

'

yyC

-

st3

.u a

g

'3'3gijj,

-

.

E b,

'b y

E85

2

<=

E t

's ag,)(v)

9"

[

(r g

e-

=

as a

gggs t: n 5o

.

~F

.u l-C L

o um--

=

n o

n

, t--

a

d a

p

=

d

'

i o

e

--

W

'

e s I n

.

-

.

e=:2:

[..:_:

e n3--

53 u:

-

--

.

a E

g

=

l

'

)

De

~

~C

<

.

ei EiI E

~3

-

is

'

Q

ex R"

=

_

O2 (

=;

uj

,,

_

e x

=

r._

g

._

E., 5

. = =

.

___m_ _ _ _ _ _ _. _. _. _ _ _ _ _ _ _ -.

_

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

..

.

-

!

Yh

c&

.

CST

_

. Combined Full Flow

.

HPCI RCIC

/ Test Line

' pump gueggo, CS soy

. )NUN F004 From CST

"

.

4 From RCIC

_ V006

.

GHMMfulf Ftow Une

'

V026 V025 V014 V023 V013 M 003 x

x r+N x

.

,

HV F008] @To CSTTest Bypass

.f Jockey 3P U

ump HV

.

g8278

.

XV024

,,5

,,'j,

in U

HPCL V003

reco..tce unc a

,,

Pump

'5""'-

,,

Bo ster

.

eso$lio".#l

^

E~@F00{

HV Pump

"". uu rto eccac. un

'

i-d'u F059 *inffon.'R,.fPSV

.psV

,Q,,,,,,,3,,,,

-

Om PCV F050 G1and F018 coacstaara' Soc.vtv

"

LTJ

,F035 Seal Cond

~

u.9am l

!

is's' *?t,"-

HPCI HPCI Gland

'

"

n Cho er Vacuum Tank Seal Cond act5 orto e m s:

'o'oau5

'

Cond Pump Vacuum 2 f Vh U V 8 F01 @ ][

p V027 g F026incanoHV.Et,"5,8,'Eg"'

[

n.

,,u.,

.

atuu n'

HVh[

25$5*khkNtE"'

MVacuum Pump

,,

F042 n

Pump Suetion

-

it if Hy Discharge To

.

4922 Maincondenser

-

Frem Torus To CRW To Reactor Isol. Viv.

Suppression Pool (Torus)

Building Exhaust

'

Control

-

.

"N

_

LP NO.: 302HC-000.00-026 TITLE HPCI WATER SYSTEM r-

-

'

.

FIG. NO.: 7 lREV.: 3

,

.

AT FACliMENT 2

-

- - - - - -

- - _

. _ _ _ _ _ _ _ _ _ _ _ _ _

.

b bN n

~'

hO

.

p

"C" Main Steam Line

.

Reactor

.

,o plow Primary Containment

""2 Element HV

Detehtion

.4%

hER Toy

]

l

"

D INot Used)'

$

Vents to Torus Room

.

,

.

rV

F100 gi, a apture py.

yy

,

gsc 4879 4880 s

.

1" 16" hQ

,

y

"

Rupgrg ga3 guSa,c

--

%

g

..

Tur

_f7,L

,

)(V012

-

HV HV HV

/O F079 Vacuum F075 F071 FD

'

V004-

][V011 MHV F028

\\.

r.,

Breakers

=

-

/

Fmm Mo'o"u4". '

m n PSV PSV

,N Anviliary b

.

=

-

= F077 F076 g g g,,

Steam J?2.L MHV F029 sg

_soug souron a

.

g$m4w

-

,

_

V008 ourmo j

-

Strainer'

.

l Torus

.r.

e

,:

.

.,

..

-

,.

'

V009

'

..,.. -

..:. r -

.. :c.

.?.. n

+

.

LV JEOFOs4

l O.;.6).a

7.uc;y;.

Condenser

'"'

Gland Seal.

(sn p

.%

.. y

.

g*

-

.., 3 o

.,

\\

.

-

l

.

FROM

'-

i From RCIC-*O HPCI

-

VAC PUMP

.

To Main Condenser LP NO.: 302HC-000.00-026 rh

. ;x -

'

n+

...

.

TITLE

"

-

- - -

-

HPCI STEAM SYSTEM s..

[

ATTACHMENT 3j I

'

FIG. NO.: 1 lREV.: 3

'

"-

,-

.

,

-

..

\\

k N GC%

'

~

O g

-

'

-

,

AA5 HH P

WW5 M

)

E

2 AA C

/

T

-

///

H

0 W

TL W

.

'

0 A

O T

AA4 O

-

(

fH I

/

C M

/

)

H VW5 FP

I n

L (

3 P

.

L AA

.

/

LP O

/f E TU R

NE

/

E VW CS PI V

L T E

AA3 H L

-

L wW

/f OA

/

Ef TU L

-

Y V5 T

-

T P

I

C k /4A E C S f/

R

/

A Aff A

'

VV O

V0 U P

-

T

-

A A/A2 AP A

T

<

m C

ff/

ffK RM VVW5 E E A

AA P T

&mWWWf K f4 1 M E

fKf E L H

0 T TC AA4AA1 AH

.AWWVWV 5 ff/H/

f/

fff f

,

T =

L C E H gWMVwW/f h

fA/AAAA DT f

A f Hff A

WV

0 0 0 0 0

O 0, 0,,

,,

7

5

3

'

0 9 8

,,

',,^*

1

' i

.

O

.

$lO O ~ z 0 m w E g-aD J

.

i s

-

'

O

o l

=eD'Jbnt%

i

&

o

.

e

.

e

/s meg/

/

r

.

m r

_

E

,.

V a

MMg=

R v

,

U t

_

,

C a

e

,

L l

,

T e

,

C

_

MMg=

e H

,

i

,

o.

,

n T

,

MMg

.

I M

on IL ee)

E eG MMg R

IS U

P

. T (

A MMg E

,

R R

E eeU

..

P n

eS M

MM

$

.

. o

.

S

.

E a

E T_

T N-s R

E.

Y P

M.

MM'

T H-V C

IC e

A P

T A

eR T

MU P

A AC T

WN A

E e

H ez

.

,

_

e

.

o e

e e

e g

" "

5

2 l

'

,

'

1

'

1

-

E :tEsN 85

-_-

<

_ o

_

L l1I I

I l

l

. _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _.

e b

'

DRYWELL SPRAY INITIATION PRESSURE LIMIT MMMMMMMMMS m

3o 340 e MMMMMMV 6,00MMMMWV s

,,,mmner s

MMMV W

MMr

.

m

ggy D

220

MW

<(

200 180

' :; ?'

f

'

g '14es j

g g

l O~

120 1oo j.

g g

i N

<

k

0

40

80 100 120 140 160 180 200 SUPPRESSION CHAMBER PRESSURE (PSIG)

s

-

J LP NO.:302HC 000.00126A

'

O/W SPRAY INITIATION PRESS UMf7 FIG. NO.: 4 l REV.: 2

.

r --

ATTACHt1ENT 6

- _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _

i li

)l

!

l;

.

-

,

-

~.

6 $a9OYmO

-

.

.i e.

'

-

h h{(3 tN

_

,

~

-

y t

.

/

.

1

9

jl.;{-.

.

!

'

{'

l

0 1.

g g

.

n it

..

oo

E f'

-

p N

,

E

,

I

,

L NN

,

n

,

IL R_

n iR E

"

i W

-

t

.,

w P

k ORE O

,

'8 R

P

',',

A N %O M

O 0C

M J

I

7_W E

,

G

%

M N

'

E N5 I

R A4 N

'

I O

L K

,

I H

M D

L WE n T N E

7 A

\\

E

F i

H

,

OE

,'

R lET P

T

,

N m M8 S

E E.

LR j,

'

M E8 M

R H

- V 8 RE U

F

-

,

C N GL C

5 O l

I A

l g

'

,;

C T

i

N T

O E

-

I

.

M A

S EW jH N NO T P O

%

I.

L IL t

F

-

R O C

D E

,

O R I

I R R O

'

EH T

y'

S

% C

0 E

W I

C

3/

5

L

.

O L

N

.

A

,

R N

A O

E P

O R

I W

U T

A I

/

M O

L

R P

N Vc E

%

n R

P 0 i

O

c

E

,

W

"OP

%

0

-

0

8

4

1

.

-

.

_

..

.

_

.

.d ii" Pi i -

L i!l\\

ll'

v t e Inspection Report - Hope Creek - 1989004
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 24(0) 81(0) 8(0) 9(0) 11(0) 12(0) 13(0) 14(0) 16(0) 17(0) 18(0) 20(0) 21(0) 80(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000354/1989004

Text

=

=

Navigation menu

Search