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

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EXAMINATION REPORT N '(OL)

FACILITY DOCKET NO.- 50-354-

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l FACILITY. LICENSE N DPR-16

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LICENSEE: Public Service Electric and Gas Company P, O. Box 236 Hancocks Bridge, New Jersey 08038 FACILITY: Hope Creek Nuclear Generating Station

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EXAMINATION DATES: February 14 - 16, 1989

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EXAMINERS: C. Sisco, Operations Engineer, (Examiner Certification)

M. Daniels (Sonalyst)

CHIEF EXAMINER: -

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_ fren G. H#e,len115r Operations Engineer c//f/Ser Date APPROVED BY: h Rfchard J. Conte, f41ef, BWR Section .

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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 examinatio 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 roo .

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DETAILS-

' 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 belo RO l SR0 l l Pass / Fail l ' Pa ss/ Fail l I I i l I I I l Written l N/A . l 3 / 0 l l i I I I I I .I-l Operating -l N/A l 3 / 0 l 1 I I I I I l l Overal l N/A / 0 l l 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 require STRENGTHS Good use of plant procedures Good use of Emergency Plan Implementing Procedures DEFICIENCIES No general deficiencies were note .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 require ___-__=____-___-_-______--:-__-- . _ - _ _ _ _ _ _ _ _ _ - - - - _ - _ _ _ _-_ :

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l-STRENGTHS ji ' Knowledge of natural circulation - Question 5.01-

- Knowledge of recirculation pump isolation - Question 5.04 Use of.HCTL and HCLL curves.- Question 5.07 Immediate operator actions for loss of Instrument / Service Air -

Question 5.12 DEFICIENCIES HPCI valve operations on initiation / isolation - Question 6.08 b. . Knowledge of Safety Tagging program - Question 6.12 Knowledge of On-The-Spot procedure changes - Question 6.13 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 change 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 representative 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 roo 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 Generato ~

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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 practic ~

3.3 'An unauthorized person was discovered in the-simulator room during 1 the operating tests. His oresence was considered to be an

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I inadvertent intrusion. The examiner stated that the responsibility of examination security is the licensee' The facility acknowledged and' stated the simulator room will be verified to be clear of all non-involved personnel during future operating examination .

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

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

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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 meetin Access to the facility went smoothly with the excellent support from Health Physics and Securit The Operations staff was cooperative in maintaining a control room environment which was conducive to the administration of the 1 operating tes '

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5-Th'elstrengths of the operating test noted in Section'2 were discusse 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 day The Additional Findings, (Section 3) and the licensee's correctiv actions were discussed during the exit meeting. The examiner concluded the corrective actions taken by the licensee were satisfactor ~

Attachments: Senior Reactor Operator Written Examination and Answer Ke . Facility Comments on Written ~ Examination after Facility Review NRC Response to Facility' Comments Simulation Facility Report l

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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 onl Staple question sheet on top of the answer sheet 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 start f7pg (5)

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY

'33.00 43.42 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%)

43.00 56.58 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)

76.00 % TOTALS

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FINAL GRADE All work'done on this examination is my ow I have neither given nor received ai Candidate's Signature L

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. . NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules' apply: Cheating on the examination means an automatic denial of your application and could result in more severe: penalties.

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. Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . 'Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the

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

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' Use only the paper provided for answer .~ Print your name in the upper right-hand corner of the first page of each section of the answer shee . 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.

! Number each answer as to category and number, for example, 1.4, . 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 tabl . Use. abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . 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 complete _ _ _ _ = - _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ - _ _ -

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.1 When you' complete'your examination, you shall:

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a.-. Assemble your examination as follows:

(1). Exam questions on to (2) Exam aids - figures, tables, et (3) Answer'pages including figures which are part of the answe b.: Turn in your copy of the examination and all pages used to answer-the examination questions, Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke tr i

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1 5. - EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' ' Page' 4

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. 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?: ,

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C. IDENTIFY the level instrumentation range required to . .

be used to indicate this leve (0.5)

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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 answe (0.5)

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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 Shutdow (1.5)

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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)

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B. HOW is overcooling of-the pump casing prevented while-the pump is isolated?.- (1.0)

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(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 turbin 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 turbin (2.0)

(Setpoints NOT REQUIRED)

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QUESTION 5.06 (3.00)

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'For.each PLANT CONDITION listed below, IDENTIFY the l L appropriate PROCEDURE (s) to be utilized. If none, STATE NON (3.0)

Consider each plant condition separatel ,

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NOTE: PROCEDURE may be used more than once or NOT at al PLANT.CONDITON PROCEDURE

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A. Turbine trip from 10% powe . OP-EO.ZZ-103 Reactor Building Control

. Reactor water level -40 inches OP-EO.ZZ-100 Reactor C. Suppression Pool Temperature 98 F Scram D. Drywell Temperature 130 F OP-EO.ZZ-101 RPV Control E.' Reactor level + 10 inches and Reactor power 57%. OP-EO.ZZ-102 Containment Control F. Reactor Building Diff Press 0 inches water OP-EO.ZZ-202 Emergency

Depressurization OP-EO.ZZ-104 Radioactivity Release i

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E QUESTION 5.07 (3.00)

Usin, Attachments #4.and #5 answer the following question PLANT CONDITIONS Reactor Pressure 700 psi Drywell. Pressure 9 psi 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)

' Is the Heat Capacity Temperature Limit EXCEEDED?

EXPLAIN YOUR ANSWE (0.75) WHAT is the VALUE of the Heat Capacity' Level Limit? (0.75) ~

Is the Heat Capacity Level Limit is~ EXCEEDED?

EXPLAIN YOUR ANSWE (0.75)

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QUESTION 5.08 (2.00)

Using Attachment #6 answer the following question With Suppression' Chamber Pressure at 20 psig ;

i WHAT is the MAXIMUM Suppression Chamber Temperature that Drywell Spray is permissabl (0.5) WHAT is/are the adverse effect(s) if the Drywell Spray ;

is initiated ABOVE the maximum Suppression Chamber !

Temperatur (1.5)

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QUESTION 5.09 :

(3.00)

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 me , IDENTIFY the two.(2); CONDITION (1.5)

> FILL-IN'THE BLARKS- The conditions may be verified by a check'of at l' east

' indications.- (2 blanks) (1.5)

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(2.00)

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' QUESTION 5.10

'Concerning Procedure OP-EO.ZZ.101 (Q) " Reactor / Pressure Vessel (RPV) Control". Step RC/Q-45 directs 'When-SLC ha injected the Cold Shutdown Boron Weight (Less than 1600

. Gallons - Remaining in the . SLC Tank) THEN Exit RC/ PER this procedure step, should the operating SLC pump (s)

.bn secured at this time? (2.0)

EXPLAIN YOUR ANSWER.-

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

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

Immediate Operator Actions required to be.take (2.0)

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QUESTION '. 5 .12 ' (2. 00)^

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

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decreasing Instrument Air header pressure. In accordance-with procedure.OP-AB.ZZ-131 (Q)'" Loss of Instrument Lair and/or' Service. Air" 'f A4' IDENTIFY the condition (s) in which you would order the Reactor to'be scramme (1.0)

.B.l.WHY should the. reactor be scrammed? (1.0)-

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QUESTION 5.13 (3.00)

,Using Attachment #7:-

The plant is operating at power when a. Recirculation Pump trip Power is 1600 MWT and Total Jet Pump Flow indication is 38 million'1b/h WHAT ACTIONS are required per procedure OP-AB.ZZ-112

" Recirculation Pump Trip" and WHY are these actions rcquired? SHOW ALL WOR .(3.0)

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

RESPONSIBILITIES (13%) {

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-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": Reactor water level' decreases to the auto scram setpoin (Assume no operator action)

L IDENTIFY ALL valves (By number) that receive a SIGNAL to CLOS (1.0)

(NOTE: Consider all'RHR loops)

B. Assume Reactor water level decreases below the auto scram setpoint and continues to decreas (Assume-no operator action)

1. At WHAT Reactor water level will the LPCI Mode of the RHR system initiate? (0.5) WILL the RHR loop "A" inject in the LPCI mode? If so WHY, if NOT, WHY NO (1.5)

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l QUESTION <6 . 0 2 - (2.00)

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

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

' Controller FIC-R6000 provides when in the Automatic Mod (1.0)

l B.' IDENTIFY the signal (s) and setpoint(s) that initiates an AUTOMATIC start of the syste (1.0)

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QUESTION- 6.03 (1.50)

l A. IDENTIFY the signal (s) and setpoint(s) that AUTOMATI(: ALLY start the Core Spray pump (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). e (***** CATEGORY 6 CONTINUED ON NEXT PAGE * * * * *)

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RESPONSIBILITIES-(13%) .

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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)

C. From WHAT accident (, ark the bypassing of the High Drywell

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does Pressure signal afford protectio (0.75)

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QUESTION- 6.05 (2.00)

' IDE'NTIFY'the signal (s) that initiate (s) the End-of-Cyle Recirc Pump Tri (1.0)

- IDENTIFY the SYSTEM.that supplies.the signal (s). (0. 5) .

C. WHEN is this trip AUTOMATICALLY BYPASSE (0.5)

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QUESTION, 6.06 (2.5d)

Tha. Redundant Reactivity Control System-(RRCS) has

' initiated AUTOMATICALL (NO OPERATOR ACTION)

A. WHY is the AUTOMATIC start of the Standby Liquid Control System delayed.for.,3.9 minutes?- .(1.0)

- IDENTIFY the signal (s) that MUST be present after the, minute time delay to permit.'the AUTOMATIC start of the Standby Liquid Control Syste (1.5) , .

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

or less Circulating Water pumps running with a trip signal presen (0.33)

B. Recirculation pump speed is limited (Runback)

to 45% when:

1. Reactor water level is less than concurrent with a trip signa (0.5) Total'feedwater flow greater than concurrent with a trip signa (0.5) IDENTIFY the signal (s) that must be matched (" nulled") prior to RESETTING the runback (s). WHY is matching the signal (s)

necessary? (1.0)

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. QUESTION 6.08 (3.00) -

Using Attachment #2 and Attachment #3, answer the following questions concerning the High Pressure Coolant Injection System (HPCI). The system valve alignment is in NORMAL STANDBY with the plant at power when' Reactor water level

decreases to-below the auto start setpoin (Assume NO OPERATOR ACTION) IDENTIFY all the valve (s) that receive an open signal as a part of the initiation sequenc (1.0) IDENTIFY all the valve (s) that receive a close signal as a part of the initiation sequenc (1.0)

B. - The HPCI system is injecting into the reactor when level reaches + 55 inches and Drywell pressure is 2.0 psi (Assume NO OPERATOR ACTION)

IDENTIFY any valve (s) that CLOS (1.0)

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, . 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- ANSWER..

l WHY is the channel inoperable? (1.25) WHAT ACTION (s) are required per Technical Specifications? (1.25)

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QUESTION 6.10 (2.00)

l 4 The plant is in STARTU 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.

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' NOTE: FULLY. REFERENCE ALL APPLICABLE TECIINICAL SPECIFICATIONS' -l l IN YOUR ANSWE MAY the Mode switch be placed in the RUN position wit the valve inoperable? BRIEFLY EXPLAIN your answer.

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(2.0)

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7 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 28-j .' RESPONSIBILITIES (13%)

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QUESTION 6.11 (3.00)

Concerning the Diesel. Generators: 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) 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 signa IDENTIFY All Diesel Generator Trips that are OPERABL Setpoints NOT REQUIRE (Assume NO OPERATOR ACTION) (2.5)

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QUESTION 6.12 (2.50)

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

. 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 releas (1.0)

C. MAY equipment be operated that.is YELLOW tagged for more than one (1) . . individual? EXPLAIN your answe (1.0)

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l QUESTION 6 .~ 1 .(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) On-the-Spot Changes must.be implemented within of approval..by the SNSS/NS .(0.5) On-the-Spot Changes shall undergo the same review and approval as a permanent. revision within .

(0.5)

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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 Cre (2.5)

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QUESTION 6.15 (3.00)

In accordance with procedure OP-AP.ZZ-110 (Q) "Use and Development of Operating Logs": 1 The overall status of the Radwaste systems is recorded in

'the Lo (0.75) ALL Operations Logs in use during a shift shall be reviewed i by (TITLE). (0.75)

- Calls to the NRC concerning significant events shall be l recorded in the Lo (0.75) Implementation of the Emergency Plan is recorded in the Lo (0.75)

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QUESTION 6.16 (2.50) l Using the furnished Event Clast.ification Guide, CLASSIFY cach of the following event Consider each cuent separately Reactor water level is -129 inches and decreasin (0.5)

B.- Loss of Alternate Shutdown Cooling and reactor pressure 150 psi (0.5) .The SNSS/EDO judgement indicates probable fuel failure based on Off Gas readings with the plant at powe (0.5) 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 increasin (0.5) Control of the plant has not been established at the Remote Shutdown Panel within 15 minutes of Control Room Evacuatio (0.5)

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-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 NON .An accidental criticality during refuelin (0.75)

, Inadvertent start and injection of th.'. HPCI system during plant operation (0.75) Presence'of loose parts discovered in-the reacto (0.75) A Reactor Scram caused by low reactor level during a plant startu (0.75)

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L Sh ' EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS _Page-35 (33%)-

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' 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 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)

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REFERENCE LP- 302HC/2:25 112H book 13 page 8 OBJ 6-KA 295016AK201 (4.4/4.5)-

295016K201 ..(KA's)

ANSWER 5.03- (3.00) ,

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

' 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)

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5.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 36 (33%)

. REFERENCE LP 302HC/2:25 (029-04) book 4 page 37 OBJ 13 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 9 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 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)

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5. - EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 37;

-(33%)

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" ANSWER 5.06 (3.00)

L /A. NONE- C. 4

' NON ' (6:at'O.5 each)

' REFERENC LP EOP lesson plans book 14 OBJ State entry condition KA_ L295026G011 (4.4/4.6) 295028G011 (4.2/4.4)'295031G011 (4.2/4.6)

295037G011 ' (4.4/4.7)'295009G011 (4.3/4.5)

295026G011 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) ,

- 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 4 KA' _295030EK103 (3.8/4.1) 295030EA201 (4.1/4.2) 295030G012 (3.7/4.4)

t 295030K103 295030A201 295030G012 ..(KA's)

ANSWER 5.08 (2.00)

1. . 170 F(+2/-5 F) (0.5) 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 *****)

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^ EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' Page 3"8 (33%)

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REFERENCE LP 302HC/2:25 (126A-03)~ book 14 page.9,10 OBJ 6 KA- 295024EA111 (4.2/4.2)'295024EA204 (3.9/3.9) 294001A108 (3.1/3.6)

295024G007'(3.6/3.9)

295024A11 A204 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 assure (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 OB KA 295037A104 (4.5/4.5) 295037K305 (3.2/3.7) 295037G012 (3.9/4.6)

295037A104 295037K305 295037G012 ..(KA's)

' ANSWER (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 l

4.. Ensure all appropriate automatic actions are complet (4 0 0.5 each)

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. . EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 39 (33%)

REFERENCE LP 303HC-000.00-114, Procedure OP-AB.ZZ-128 OBJ 1 KA 295002G010 (3.8/3.7)

295002G010 ..(KA's)

ANSWER 5.12 (2.00) 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)

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

295001K104 295001A201 ..(KA's)

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ANSWER 6.01 (3.00).

" (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)

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- 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 psi (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)

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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 12-K K103 (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 SL (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)

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

'OBJ 'S &-3 KAL 211000A308-(4.2/4.2).

'211000A308 ..(KA's)'

ANSWER i6.07 (3.00) . 20% .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 & 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) -l 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)

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' ANSWER ~ 6.09 (2.50) 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, 11 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 2 KA 206000G011 (3.7/4.4) 206000G005 (3.6/4.3)

206000G011 206000G005 ..(KA's)

ANSWER 6.11 (3.00) Loss of Power to (Emergency) Bus (0.5) . Engine Overspeed Generator differential current 3. Generator Overcurrent 4. Bus differential current 5. Low lube oil pressure (5 0 0.5 each)

l

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

_ _ _ _ _ _ _ _ _ _ _

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'

i 2; .

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

, RESPONSIBILITIES (13%) .d

.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)

~ . hours (0.5)

lC. 14 days - (0. 5) .

1'

l l l 1

l 1-(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

El___ ____ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-. , - _

8 d

[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 (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%) ANSWE .16 (2.50)

A'. Site Area Emergency Alert Unusual Event D. . General Emergency '

E.- Site Area-Emergency (5 0 0.5 each) 1 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) hour 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 hour 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 **********)

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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 \|
1989 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 8(0) 9(0) 11(0) 13(0) 14(0) Security Operator Exams Emergency Planning Other

IR 05000354/1989004

Text

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