ML20150C065

Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations

ML20150C065
Person / Time
Site:	Braidwood
Issue date:	10/01/1988
From:	NRC
To:
Shared Package
ML20150C040	List: ML20150C036 ML20150C065
References
ES-601-DRFT, NUDOCS 8807120299
Download: ML20150C065 (347)

Text

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ES-601 Rev 5 10/1/88 DRAFT ADMlHISTRATION OF NRC REQUALIFICATION PROGRAM EVALUATIONS A. Purpose This standard provides general guidance and requirements to NRC examiners for the administration of NRC requalification examinations. This program evaluates the effectiveness of a facility's licensed operator requalification training program to maintain the competency and currency of licensed operators. This is done by evaluating the ability of the facility to adequately prepare written examination questions and simulator scenarios and their ability to properly evaluate their operators' performance. In addition, satisfactory completion of the examinations by individual operators would satisfy the regulatory requirement to pass an NRC administered requalification examination prior to licerise renewal. This document is not a substitute for the operator licensing reguiations and is sub. ject to revision or other internal operator licensing policy changes.

B. Program Description The NRC requalification examinations administered under this standard per the provisions of 10 CFR 55.59(a)(2)(iii) attempt to minimize the potential for an ad' verse impact on the safe operations of facilities, and to provide the staff with an assessment of the effectiveness of facility requalification training programs, i The requirements and procedures are derived based on a systems approach to training (SAT) program in accordance with INPO Guideline 86-025, and rely upon existing requalification program standards for guiding the NRC examination development and implementation. This approach will allow the NRC to administer

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requalification examinations that are consistent with existing facility {

880712o299 880623 PDR V ADOCK 05000457 PDC Examiner Standards 0001.0.0 of 28 t _

ES-601 Rev 5 10/1/88 developed programs, thereby reducing the impact on the facilities and improving the reliability of the NRC assessment of requalification training programs, i

I Each requalification examination will be developed by an examination team  !

consisting of NRC examiners and facility representatives and will be reviewed by facility representatives and by the Resident Inspector where practical. The examination will be based upon the facility requalification program and its learning objectives, to the extent practical. This approach will result in more technically sound and operationally oriented examinations. In addition, l

coevaluation of operator performance by the NRC and the facility will enhance i

the ability of the NRC to assess both individual and program performance.

The NRC administered requalification examination is composed of an operating test and a written examination. The operating test consists of a simulator l

evaluation which emphasizes time-critical and team-dependent behavior with a flagging system to enable follow-up of individual weaknesses. The walk-through evaluation will cover plant systems identified by the NRC and the facility that,are important to the safe operation of the facility as contained within Groups I and II of the "Examiners' Handbook for Developing Licensing Examinations" (See page 2-18 of NUREG/BR-0122). The written examination consists of a two section open book examination: Section A will be a "Plant Operations" section and is administered on a static simulator; Section B will be a "Limits and Controls" section and is administered in a classroom setting.

4 C. Administrative Controls The NRC will plan to examine an average of 20% of the licensed operators and senior operators at each facility on an annual basis. The following criteria outline the requirements for the administration of the NRC Requalification Evaluation Program.

1. Facility Notification Examiner Standards 0002.0.0 of 28

ES-601 Rev 5 10/1/88 The attached corporate notification letter is used to inform facility program managers of the impending requalification program evaluation. This letter I should be mailed at least 90 days in advance. Site visits should be scheduled to coincide with the requalification training cycle of the facility. The facility should know 30 days in advance which operators will bs evaluated.

2. Selection of Operators The facility will propose operators for NRC examination 60 days prior to the administration date. The NRC will select crews and individuals to be examined based on the following criteria:

a. Number of individuals on crew not examined during current license tem,

b. Number of examinees required to sample 20% of licensed personnel,

c. Number of staff (not crew) licensed personnel not examined during current license term, and Id. Length of time until license expiration.

e. Priority given to crew (s) in training during the examination week (s).

An operator that has previously passed an NRC requalification examination during the term of the license may be included in the simulator crew I evaluation, if he/she is a inember of a crew selected. Such an individual will l

not be required to take the written or walk-through examination. Poor performance in the simulator examination would be evaluated as described in Section D.7.a.

The sample will include additional shifts composed of licensed personnel who l are not routinely performing shif t duties, in order to sample approximately l 20 percent of the operators each year. If a facility evaluates mixed crews (shift and non-shift license holders), mixed crews may be evaluated. I i

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3. Facility Involvement

a. The facility will be requested to provide two employees, one from the operations staff and one from the training staffs, to assist the NRC to form the NRC examination team. The employee from operations shall be an active licensed SR0; the employee from training should preferably be a licensed SRO, but may be a certified instructor.

The function of these individuals is to provide facility specific technical assistance to the NRC in the development and review of the written examination items, plant walk-through topics, and simulator scenarios. If necessary due to insufficient facility staff resources, facility representatives may participate in the actual conduct of the operating test or written examination,

b. To ensure examination security, the individuals shall not in any way be involved in requalification program activities between the start of their involvement in examination development and the administra-tion of the examinations. Also, the individuals shall be instructed 5

and agree not to comunicate in any fashion the content or scope of the examination to unauthorized persons. Each individual will be required to sign a statement prior to reviewing any examination material that he/she will not knowingly divulge information concerning the NRC examination, and then to sign a second statement after examination administration that he/she has not knowingly given information about the specific content of the examination to any unauthorized person.

c. For the simulation facility examinations, a facility management representative with responsibilities for the conduct of plant operations (as a minimum, first level above shift supervisor) be present during administration of these examinations,

d. In addition, the facility will be required to grade, in parallel with the NRC.

4. Timetable for Administration of Requalification Examinations Examiner Standards 0004.0.0 of 28

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ES-601 Rev 5 10/1/88 l 90 days in advance - The facility is notified.

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60 days in advar.ce -

The facility provides proposed materials for examina- l tion construction (including written examination question and simulator scenario banks and job performance measures with follow-on questions for important safety systems).

The facility proposes crew composition.

30 days in advance -

NRC notifies facility of crew selections.

14 days in advance -

NRC team visits the facility to prepare for the examinatiores.

7 days in advance -

NRC prepares for examination in the Regional office.

Examination Week -

NRC administers requalification examinations to selected crews.

5. Examination Administration The simulator examination is normally administered first, followed by the plant ,

walk-through evaluations for each crew. The two part written examination will l be sdministered after all simulator and plant walk-through evaluations have l

been completed. This order of administration is intended to provide for an operational atmosphere prior to the written examination. Each portion of the requalification examination shall include the appropriate oral briefing or rules handout.

6. Requalification Program Evaluation

a. Program Evaluation l

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A program evaluation should normally be based on a minimum sample size of at least 12 licensed operators and senior operators. If the annual 20% sample does not meet this minimum sample size then the program evaluation will be deferred until inclusion of the next annual cycle, unless the interim results warrant imrrediate action.

A satisfactory requalification program must meet each of the following:

(1) 90% pass / fail decisions agreement between the NRC and facility grading of the written and operating examinations.

(2) At least 80% of all operators pass the examination.

(3) The program is judged satisfactory in accordance with the guidance giver, for the simulator evaluation.

-(4) The program meets the requirements of 10CFR55.59 or, in lieu of paragraphs (c)(2),(c)(3),and(4),isbasedonsystemsapproachto training.

When using the above percentages, fractions of individuals should be rounded I

up to the next highest number. For example, if twelve (12) licensed individuals l

are evaluated, 80% passing would be 9.6, thus ten of twelve passing should be considered as reeting the 80% requirement. This rule stivuld be applied throughout this standard,

b. Reference Material Evaluation NRC reserves the right to declare a facility training program unsatisfactory and to postpone NRC administered requalification I examinations if the facility generated materials are inadequate for l examination preparation. Enforcement action may be considered if  !

necessary to bring facility generated material to the level of quality for examination preparation. l

7. Requalification Performance for an Individual Examiner Standards 0006.0.0 of 28

ES-601 i Rev 5 10/1/88 l For an individual to successfully pass the requalification examination as graded by the NRC, the following apply:

a. Achieve at least 80% overall on the written examination,

b. Satisfactorily complete the walk-through examination, and

c. Be judged satisfactory on the simulator examination.

8. Examination Process Critique The operators will be orovided with an examination process critique sheet and encouraged to complete the form at the conclusion of the examination process.

The facility will be responsible for collating the critiques and providing them to the HQ Branch Chief, with a copy to the Regional Branch Chief, after the administration of the examination. The Regional Chief Examiner will compute the mean and standard c'eviation for each item and include the results in the exam report.

D. Simulator Evaluations The purpose of this portion of the examination is to evaluate the crew's time-critical and team-dependent behavior and individual performance during simulated events.

Until full cor.pliance with 10 CFR 55.45(b), for plants without a simulation facility, the facility shall propose an alternate method such as a control room mockup for the conduct of this portion of the examination. NRC Will determine the usefulness of such alternatives.

1. Scenario Scope and Cortent The facility shall provide at least 15 simulator scenarios to the examination team. The scenarios must be approximately 50 minutes in length and both l

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ES-601 Rev 5 10/1/88 couprehensive and realistic, i.e., not a series of unrelated events. The examination team should verify the scenarios against the facility requalification program learning obejetives and compare the critical tasks with the K/A catalog to ensure they possess importance factors of 3.5 and above. The scenarios may be modified by the team based upon the technical advisement of the facility representatives. The scenarios should be based upon lessons covered in the requalification cycle, recent industry events, LERs, emergency and abnorral procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident prevention and mitigation. Each scenario should exercise each crew member as appropriate to his/her position during the scenario. That is, each individual should be required to perform at least one critical task during this portion of the operating test. Each simulator evaluation should place individual crew members in the most senior watch standing positien in which the individual normally operates on shif t. Each evaluation shall exercise the crews' abilities in the use of Emergency Operating Procedures, Technical Specifications, and the Erergency Plan.

2. . Scenario Complexity, Standards and Criteria I

The NRC will review scenarios to ensure tasks are compatible with  !

NUREG-1122/1123 "Knowledge and Activities Catalogs for Nuclear Power Plant Operators" for abilities with importance factors of 3.0 and above. The following should also be considered:

(a) too complex -

beyond the scope of lessons covered (unrealistic) l beyond the ability of procedures beyond the simulation facility capability (b) too simple -

should be integrated events no team dependent behavior no time critical behavior absence of equipment malfunctions The examination team will review scenarios to ensure expected responses are provided.

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ES-601 Rev 5 10/1/88 The NRC and the facility representatives as the examination team will jointly  ;

identify "critical tasks" for each scenario that are crucial to the maintenance of plant safety. To identify critical tasks, review the JTA or other facility 1 training material for identification of critical tasks for each scenario. In addition, the knowledge or ability should be rated 3.5 or above in the K/A catalog. The facility representatives' review should substantiate the task as critical to plant safety. Should the crew or individual incorrectly perform these critical tasks, this would establish a basis for an unsatisfactory evaluation.

3. Simulator Examination Length and Position Rotation A scenario's contact time (not including time spent on briefings, simulator setup or simulation facility problems) should average 50 minutes, based upon real tire performance.

Position rotation will be dependent upon facility rotation practices. Crews will.be evaluated in the simulator as they are configured by the facility for i operating the plant. Control manipulative skills will be evaluated in the I walk-through. For example, senior operators may be required to perform control board operations on the simulator.  !

l The number of scenarios shall be sufficient, with a minimum of two per crew, to ensure that each examinee is tested to the extent that he/she may operate during both normal and emergency operating conditions.

4. Recording and Flagging System Any individual weakness observed on competencies detailed on NRC Form 157, page 4, will be potential items for follow-up. Follow-up may not be Examiner Standards 0009.0.0 of 28

ES-601 Rev 5 10/1/88 required if the examiner's concerns are resolved during the facility led scenario critique.

Passive observationt will be made. Questioning of operators during the scenario should only be done after the completion of the facility led scenario critique. Follow-up questions for flagged items should be asked at this time.

The Chief Examiner may question the plant management representative for clarification, if necessary,

a. Individual observations - record any deficiency noted. Failure for an individual, on the simulator portion only, shall be based upon significant deficiencies that could challenge the safety status of the facility such as:

(1) inability to effectively manipulate controls (2) failure to actuate a reactor trip when required (3) failure to ensure ESFAS systems inject / actuate when required

, (4) f ailure to emergency borate or initiate ADS when required (5) violation of Technical Specifications (6) failure to take any other action or combination of actions that would prevent a challenge to plant safety.

(7) Initiate inappropriate actions or combination of actions that create a challenge to plant safety.

Significant deficiencies will normally be associated with identified critical tasks as indicated in D.2 above.

b. Tear. observations - evaluation of crew perfornance will be made as directed in the "Simulator Crew Evaluation Form."

c. Flagged items of weakness noted on the simulator examination should be covered throagh follow-up questions after completion of the scenario critique to determine if there is a need for remedial training, l unless resolved during the facility led critique. These questions should also reference a K/A to indicate importance, and be reviewed by the facility representatives.

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5. Number of Examiners Required ,

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The minimum number of examiners required is one for every two operators plus one examiner as coordinator and the Chief Examiner, who may act as the coordi- ,

nator or as an examiner.

6. Assistance of Facility Operations Management The facility will be requested to provide a member of the plant operations staff to observe the process. The Chief Examiner is the principal point of contact between the facility mar,agement and the NRC.

7. Individual / Crew / Program Simulator Evaluation Guidance Following each scenario, the crew performance will be critiqued by the facility graders at the simulation facility. The evaluation is to be observed by the NRC examiners. Use the "Crew Evaluation Form" to document the results of the examination. The facility evaluators should also complete a copy of this form or an equivalent facility form for each crew.

Ia. Individual Evaluation (1) An individual may fail the NRC examination based on significant deficiencies (see D.4) observed during the simulator examination.

(2) An individual may fail the NRC examination based on follow-up questioning on deficiencies observed in the simulator.

(3) An individual who has passed an NRC requalification examination and is being used as a crew member may fail the examination or be found to require remedial training as a result of poor performance meeting the criteria of D.4.a.

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b; ES-601 Rev 5 10/1/88 (4) NRC or facility evaluator judgement that a crew is UNSATISFACTORY in the simulator will not necessarily result in an UNSATISFACTORY individual performance evaluation. That is, an individual operator may have made only minor errors in l execution such that they were overcome during the questioning after the scenario critiques and may not have contributed significantly to the poor crew performance,

b. Crew Evaluation (1) Crew performance shall be evaluated in accordance with the "Simulator Crew Performance Evaluation Form."

(2) If a crew is judged UNSATISFACTORY in the simulator by either the NRC or the facility evaluators, the crew must be taken off shift, given remedial training, and reexam'ned prior to resuming licensed duties. NRC should administer the test if the

, facility's requalification program is currently judged UNSATISFACTORY and NRC has not verified that adequate corrective measures have been instituted. Otherwise, the facility will be permitted to administer the r3 examination.

c. Program Evaluation (1) A program may be judged UNSATISFACTORY if the NRC judges at least one crew UNSATISFACTORY and the facility evaluators judge that crew SATISFACTORY; (e.g., facility evaluators feel no remedial training is necessary).

(2) A program may be judged UNSATISFACTORY if there is less than 90%

agreement between the NRC and the facility on the individual pass / fail determinations with the facility evaluating fewer individuals UNSATISFACTORY.

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ES-601 Rev 5 10/1/88 (3) If the facility evaluators judge one crew performance UNSATIS-FACTORY and the NRC does not, remedial training is indicated but the program will not be penalized for holding a higher standard of operator performance.

(4) If two or more crews are determined to be UNSATISFACTORY, regardless of individual failures, the overall program will be judged UNSATISFACTORY.

8. Video Taping The following basic guidelines apply:

a. If equipment is available, the simulator examination will be video taped.

b. Image clarity and degree of coverage mt St be adequate to make taping

, useful.

c. After initial set up of the camera by the licensee's personnel under observation of the Chief Examiner, the recording will be made with unattended camera (s). The only intervention will be to change the tape.

d. The critiques will be video taped if the scenarios are video taped,

e. Two copies of the video tape will be made, one for NRC and one for the facility.

The video tape will be used primarily to resolve areas of contention between the facility and NRC examiners' parallel evaluations of the operators.

Additionally, the facility, the examiners, and operators will be provided an opportunity to review those portions of the video tape that directly affect the pass / fail decisions, e.g., performance of previously identified critical items, if they so request. NRC will supply the video tapes and maintain custody of one copy and leave one copy with the facility. After examination results are i Examinar Standards 00013.0.0 of 28

ES-601 Rev 5 10/1/88 finalized, and all cor.flicts resolved, the NRC and the facility will erase the video tapes. The facility tape custodian will sign a statement upon receipt of the video tape indicating that the tape will be used only for its intended prupose and will be promptly erased at the conclusion of the examination.

E. Walk-Through Evaluations The purpose of this portion of the operating test is to assess the individual's understanding of and the ability to perform actions associated with plant systems and sanipulations that operators may either perform, or direct the performance of, and to assess the requalification program's effectiveness in keeping the operator's knowledge current with respect to these important safety-related tasks and the associated systems.

1. Applicable Plant Systems The facility will identify those plant systems applicable to maintenance of public health and safety in the mitigation of the consequences of an event, and those systems that can directly initiate an event. Criteria for system selection include:

.a. Systems covered during the facility requalification cycle.

b. New or recently modified systems,

c. Systems the subject of recent facility LERs or vendor notices (e.g.,

GESILs).

d. PRA identified risk dominant systems / components for plant or vendor generic plants.

e. NRC Information Notices.

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ES-601 Rev 5 10/1/88 The NRC team will evaluate the facility identified systems. Absent other information, systems should be selected from those identified in Groups I and II of the "Examiners Handbook for Developing Licensing Examinations,"

NUREG/BR-0122 with at least 50% of the selected systems from Group I of the Handbook.

Selected systems will be discussed with the facility representatives to ensure optimum site specific relevance. NRC additions and/or substitution will be discussed with the facility representatives.

2. Identify Tasks The facility representatives will review the facility JTA including learning objectives and NUREG-1122/1123 highlighting tasks / abilities for the identified systems that meet the following criteria:

a. Are applicable to the facility.

'b.

Are at the A0/R0/SR0 level - RO is responsible for A0/R0 tasks. The SR0 is responsible for A0/R0/SR0 tasks.

c. Have a X/A ability rating of 3.5 or higher. Items may be used that have ratings below 3.5 after NRC examiners consult with the facility l representatives, i A list of plant specific tasks should also be developed. These are tasks / abilities that may not be specifically addressed by the JTA or NUREG-1122/1123 but which have been covered, due to special needs, in the requalification program, e.g., special procedures, EDG operations. The facility representatives will review and concur on job applicability and importance for the complete list of tasks.

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3. Job Perforinance Measures (JPMs)

For each of the tasks identified, review the JTA and/or learning objectives and appropriate cross references te determine the training mode. Seventy-five JPMs shall be submitted by the facility. Refer to the Lesson Plan, Qualification Card or Job Performance Measure which addresses the task. The JPMs should include:

a. Initial conditions

b. lnitiating cues

c. References

d. Performance elements and standards

e. Cues f, Any appropriate output statements.

g. Appropriate knowledge areas for in-depth questions and answers.

Criteria for satisfactory completion of the task will be identified prior to administration of the examination. Critical steps which may not be included in the facility documentation of the JPM should be identified.

1 The team should review JPM criteria and critical steps based on the technical support of the facility representatives. The examination team should review proposed JPMs per the criteria in the "JPM Quality Checklist." All questions and answers will be reviewed by the facility representatives for job relevance and safety significance prior to examination administration. If the NRC asked follow-up or probe questions during the walk-through, these questions should .

1 be reviewed as soon as possible after the walk-throich is completed.

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4. Time Allocation The walk-through will be planned for approximately 2-1/2 hours in length. This includes both the control room and in-plant time and is reflective of actual examination contact time. Time required for nonexamination evolutions / items will not be considered during examination planning. These evolutions / items include, but are not limited to, the following:

a. Transit time to and frum the plant site,

b. Time spent complying with facility security and radiological admin-istrative requirements.

c. Transient time from the control room to in plant locations,

d. Transit time from one in-plant location to another.

.e. Time required for the operator to locate examination aides, e.g.,

procedures, prints, etc.

5.  : Examination Construction and Administration The walk-through will be constructed and administered as follows:

a. Time should be allotted during the operating test for evaluating the performance of ten (10) JPMs. Aminimumoffour(4)JPMsshouldbe evaluated outside the control room. Five of the ten tasks should be

'cosenon" tasks. These common tasks will be administered to each operator and used in determining the effectiveness of the requalification program in preparing the operators to perforin the tasks.

b. A JPM worksheet will be completed for each task.

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c. The detailed questions as recorded on the "JPM Question Form" will be based upon the tetting objectives established in part E.3 above and should have a K/A rating of 3.0 or above. Question construction should meet the guidelines established for the development of the written examination. The X/A for each question and correct answer will be indicated. Each JPM will have a minimum of two questions which directly relate to the JFM, and which address the basic understanding and application of knowledge of the JPM. Correct reeponses for.these questicos should not nonna11y be directly found in control room references,

d. Each examination will be reviewed by the Chief Examiner also, using the guidance in NUREG-1021.

e. The facility examiners will conduct the walk-through while an NRC examiner grades in parallel. The NRC examiner may ask questions of the operator necessary and appropriate to ensure adequate coverage of

, the content of the walk-through at the completion of each JPM, and to ensure that the operator has demonstrated satisfactory understanding and application of knowledge regarding the JPM, the NRC examiner must ensure that the facility enluator is conducting an appropriate examination.

f. After administration, the NRC shall resolve with the facility representatives all unforeseen technical questions or issues that could result in an individual failing the examination. The facility training manager will be informally briefed on the preliminary results of the examinations.

6. Individual and Program Evaluation

a. Individual Performance Criteria In order to be judged satisfactory on the walk-through portion of the examination, each operator shall:

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ES-601 l Rev 5 10/1/88 (1) satisfactorily complete 80% of the JpMs administered and

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(2) correctly answer 70% of the questions related to the 10 tasks,

b. Program Performance Criteria l

(1) If greater than 25% of the operators incorrectly answer more than 20%

of the comon task questions (for example, 3 out of 10 questions),

a programatic weakness is indicated in the area of plant systems knowledge and systems interactions.

(2) If one or more facility evaluator (s) evaluates two or more e operators as satisfactory when the NRC evaluator evaluates the saine operators as unsatisfactory, the program will be found to be unsatisfactory.

F. Written Examination The purpose of the two section open reference written examination is to assess the individual's knowledge of plant systems, procedures, and operating limits

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including the Technical Specifications.

Section A is a "Plant Operations" section and is normally administered on a static simulator. Untilfullcompliancewith10CFR55.45(b),forfacilities without a simulator, section A should be administered in a control room mockup if it exists. If neither is available, then a classroom setting should be used. NRC and the facility being evaluated will agree on the compensatory l measures (computer printouts, photographs, etc.), required for a classroom or mockup setting. Section A is designed to evaluate the operator's knowledge of l

plant systems, integrated plant operations and instruments and controls. In j addition, recognition of Technical Specification (TS) LCOs and the operator's ability to diagnose postulated events shall be evaluated, l l

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ES-601 Rev 5 10/1/B8 Section B is a "Limits and Controls" section and is administered in a classroom setting. Section B of the written examination is designed to evaluate the ability of the operator to analyze a given set of conditions and determine the proper procedural and administrative guidance,

1. Scope and Content

a. Section A - Plant Operations This section of the written examination is designed to utilize tha simulator as a reference tool in answering questions. The questions should be related to plant systems, controls, and recognition of TS LCOs in an open reference format.

This section has a minimum of two "frozen" conditions on the simulator, one condition being at power with some equipment in an abnormal statt.s; one condition for which the plant has experienced a major transient resulting in ESFAS initiation.

,b. Section B - Limits and Controls This section of the written examination is designed to utilize plant procedures (including emergency, normal operation, and abnormal) and ,

administrative controls (including TS, E-plan, Administrative Procedures) in an open reference format.

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2. Item Development and Review '

a. Proposed examination items shall be provided as an item bank by the facility. Proposed items should be reviewed for appropriateness,  ;

clarity, and importance to safety, as described in the "Guidelines Examiner Standards 00020.0.0 of 28

ES-601 Rev 5 10/2/88 for the Development and Review of Open Reference Examinations." Proposed items may be modified, deleted or replaced if necessary.

b. A technical review of the references provided for each test item will be conducted to verify item accuracy. Each test item will be reviewed for question construction with emphasis on its applicability to an open reference examination using "NRC Che:klist for Open Reference Test Itens."

Each item should be reviewed for an associated learning objective. Learning objectives should be verified as job related and relevant. Review of lesson material for test items should be conducted to determine if the learning oDjectivcs are related to corresponding task (s) in the facility JTA and the K/A catalog. The K/A rating should be 3.0 or above.

If a clear tie to the JTA does not exist, the applicability of the item shall be discussed with the facility representatives. Return any test items which do not meet these criteria to the facility training department for modification.

Upon'. completion of question revision, the facility representatives should review all test items evaluating them for (1) appropriateness, (2) time required to answer each item, (3) technical accuracy, (4) clarity, and (5) K/A and objective references. After the facility representatives have completed the review, they will provide the results to the NRC for use in final examination development.

4. Sampling Plan The facility will provide a sampling plan (i.e., test specifications which identify the percentage to be sampled of each topic area) with their proposed items as described in F.2 above. The facility sampling plan should document the validity of test items by linking each item topic with: (1)aK/Awithan importance value of 3.0 or greater (or equivalent safety rating from a facility JTA); (2) a facility learning objectives; and (3) safety-related tasks as Examiner Standards 00021.0.0 of 28

ES-601 Rev 5 10/1/88 identified by the facility JTA. The NRC's sampling plan will encompass the facility's sampling plan with an addition of no more than 20% of items beyond the facility's sampling plan. The facility's sampling plan should indicate the percentage of items on Parts A and B of topics covered during the prior full recualification program. Thc plan 2hould indicate the systematic approach to training basis and other materials used to develop the plan and document the comprehensiveness per 10 CFR 55.59(a)(2).

5. Construct Additional items Should it be necessary to develop additional items to satisfy the sampling plan, request the facility to do so. Also, the NRC team may develop itens as specified in paragraph 1.4.A above. These items should also be reviewed in accordance with this standard.

6. Construct the Final Examination Using the time required to answer the test items provided by the facility, construct an exanination using the sampling plan. A competent operator should be able to complete the examination in I hour and 15 minutes. Once the examination is constructed, use Examiner Standard ES-107 to perform a QA review. The NRC team will review the final examination with the facility representatives for clarity and technical accuracy. Use the attached instructions and cover sheets for examination administration. The examination shall be entered into the EQB main bank af ter administration.

The examination may be constructed in alternate forms, i.e., each operator may have a different sequence of questions on his/her examination. This assists in eliminating the need for having multiple sets of reference material. Handouts (e.g., plant curves, blank forma, etc.) may be provided with the test to help )

relieve the burden on the utility to provide additional sets of reference material.

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7. Procedure for Parallel Grading Using the exanination and key, the facility and NRC will independently grade each section of the written examination. The grading of all written examina-tions shall be completed within 15 working days of the examination administration date.

8. Individual and Program Evaluation

a. Individual Performance Criteria In order to be judged satisfactory.on the written portion of the examination, each operator must achieve at least 80% overall score as graded by the NRC,

.b. Program Performance Criteria In order for a facility's requalification program to be judged satisfactory, the following criteria must be met for the individuals evaluated:

(1) Hinety percent (901) pass / fail decisions agreemeat between NRC and facility grading, and (2) at least 80% of all operators pass the examination.

9. Examination Proctoring Each section of the examination shall be proctored in accordance with ES-201.1 and form ES-201-3 shall be completed.

10. Reference Material The facility shall be responsible for providing the following reference raterials:

Examiner Standards 00023.0.0 of 28

ES-601 Rev 5 10/1/88 During the "Plant Operations" (Section A) portion of the examination, one copy of all controlled material available in the control room should be available to examinees. Examination reference material will NOT include material that is intended for training use only. All reference material must be authorized for actual operation of the power plant.

During the "Lir.its and Controls" 'Section B) portion of the examination, each examinee shall have available fvr tse the following material (complete, controlled current issue):

a. Technical Specifications

b. Plantprocedures(E0P/A0P/0P,etc.)

c. Emergency Plan (as available in the control room)

d. Administrative procedures applicable to operations

e. Other plant reference material normally available in the control room

, (e.g., curves and data book, forms, plant drawings, flow charts, etc.).

NOTE: "Non-controlled" reference material, such as the Emergency Procedure Owner's Group Basis Documents will not be provided unless the facility certifies that these documents are authorized to be used during plant operations.

G. Actions Required for Unsatisfactory Individual or Prograq Evaluation

1. Unsatisfactory Individual Evalestion If an operator fails an NRC administered requalification examination, the operator shall be removed from licensed duties until remediation and l

Examiner Standards 00024.0.0 of 28 j

ES-601 Rev 5 10/1/88 reex6mination has been completed satisfactorily. NRC should administer the test if the facility's requalification program is currently judged UNSATISFAC-TORY and the NRC has not verified that adequate corrective measures have been instituted. Otherwise, the facility will be permitted to administer the reexamination for returning the individual to licensed duties; however, license renewal would require another NRC administered exam.

2. Unsatisfactory Requalification Program Evaluation For any program evaluated as unsatisfactory, the following actions are required unless findings indicate otherwise. Additional actions may be taken at the

, discretion of the Regional administrator or his designee. The sequence of actions below is not required. The determination whether plant shutdown is required should be ongoing until the Regional Administrator or his designee has reviewed all in (d) below.

a. Require the facility to identify program deficiencies and corrective

, actions required to improve operator performance.

'b. Meet with senior facility management to review audit findings.

identified deficiencies, root causes, corrective actions proposed, schedule for corrective action implementation, and follow-up i inspections and examinations,

c. Determine the required corrective actions by the facility, the required follow-up by the NRC, and the schedule for each. l

d. The Regional Administrator or his designee shall determine whether plant shutdown pending completion of corrective action is required.

This decision should be based on the:

)

1 (1) Significance of generic performance deficiencies identified during the program evaluation, 4

Examiner Standards 00025.0.0 of 28

ES-601 Rev 5 10/1/88 (2) Recent SALP performance, especially as related to Criterion 7, Training Effectiveness and Qualification, (3) Recent facility events which relate to licensed operator performance, and (4) Recomendations by resident inspectors.

H. Operator License Renewal Policy

1. Licenses for operators and senior operators will be renewed upon timely application, as described in ES-109/110 if the individual in question has successfully passed an NRC requalification examination within the term of his/her license.

2. If an individual licensee has been administered an NRC requalification

' examination two (2) times during the term of his/her license without pass-ing any examination, then his/her license will be terminated or will expire without renewal and he/she may apply for license under 10 CFR 55.31 and sucessfully cceplete an NRC license examination to maintain a license.

i

3. If an individual has not successfully passed an NRC requalification  :

examination within the term of his/her license but has failed an NRC l requalification examination fewer than two (2) times, then the individual license is extended under the timely application provisions until the next NRC requalification examination. After the results of that examination, ;

the individual will conform with either H.1 or H.2 above.

4. If an individual has passed one (1) NRC requalification examination curing

, the term of his/her license then the provisions of H.1 apply without regard to the facility requalification program status or any subsequent or  ;

priorunsuccessfulNRCrequalificationexamination(s).

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i Examiner Standards 00026.0.0 of 28  !

ES-601 Rev 5 10/1/88

1. Final Requalification Program Evaluation Report  !

A final requalification program evaluation report similar to the final examina-tion report for a licensing examination shall be prepared when the grading of )

requalification examinatiens has been completed. A complete copy of the report !

shall be filed in the facility requalification file. A copy of the NRC Adnin-istered Requalificatien Examination Results Sumary, shall be forwarded to the Management Assistant, Regional Support and Oversight Section, OLB. The results summary is required to verify OLTS data and for statistical data. l J. Record Retention i

1. A facility requalificatitn file shall be maintained for each facility.

All evaluation foms, records, assignment sheets, and correspondence n Sting ta the requalification program audit for the latest two 3 Jations shall be retainec.

2. ,When the requalification evaluation has been completed by the Regional Office, a copy of all NRC administered written, oral and simulator

' examination results shall be supplied to the facility. The facilities are required to maintain these records until the operator's or senior operator's license is renewed in accordance with 10 CFR 55.59.

3. A copy of the results sumary shall be sent to the Management Assistant, i Regional Support and Oversight Section, OLB. These sumaries shall be used for statistical data gathering.

4 Material relating to an individual failure shall be retained by the Regicnal Office as necessary to support denial of license renewal per 10CFR55.57(b)(2)(iv). l l

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Examiner Standards 00027.0.0 of 28

ES-601 Rev 5 10/1/88 Attachr..ents :

1. Corporate Hotification Letter

2. Examination Process Critique Sheet

3. Simulator Crew Evaluation Form

4. JPet Work Sheet

5. JP! Question Form

6. Briefing Sheet

7. Wiitten Erhmination Ccver Sheet

8. JPM Quality Checklist

9. Simulator Scener o Review Checklist

10. Guidelines for the Development and Review ,

of Open Ieference Evaninstions )

11. NRC Checklist for Open Reference Ttst items l

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Examiner Standards 00028.0.0 of 28 I

)

eyucg% ^ UNITED STATES 8 g NUCLEAR REGULATORY COMMISSION

{ t WASHINGTON, D. C. 20665

\...+/ ATTACHMENT 1 CORPORATE NOTIFICATION LETTER (thSERTCORPORATEADDRESSEE)

SUBJECT:

REQUALIFICATION PROGRAM EVALUATION In a telephone conversation between M (title)andM (Section Chief), arrangements were made for an evaluation of the requalifica-tion program and licensed personnel at the (facility name). The evaluation visit is scheduled for the week of (date).

For this visit, the NRC examiners will administer NRC prepared operating and written examinations. The NRC examiners will discuss with the appropriate facility personnel and operators the schedule and the process for these examinations. For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclo-sure 1 "Reference Material Requirements." M has been advised of our reference material requirements and where they are to be sent.

NRC reserves the right to declare a facility training program unsatisfactory and to postpone NRC administered requalification examinations if the facility ,

generated materials are inadequate for examination preparation. Enforcement l acti6n may be considered if necessary to bring facility generated material to l the level of quality necessary for examination preparation.

Additfonally, it is requested that a licensed SR0 from both the (plant name) Operations Department and Training Department be designated as the facility representatives for these examinations. These individuals must not be scheduled for an NRC administered examination during this visit, or participate as an instructor once selected. Also, the facility representatives will be required to certify that, as a result of their involvement, no portion of the examination has been knowingly compromised. '

The facility managenent is responsible for providing adequate space and I t

accommodations to properly develop and conduct the examinations. Enclosure 2, "Administration of Requalification Examinations," describes our requirements for developing and conducting the examinations. M has also been informed of these requirements. Also, a facility operations management representative should observe the simulation facility examination process at the site.

Enclosure 3, contains the "NRC Rules and Guidance for Examinees" that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all operators are aware of these rules. Enclosure 4 "Requirements and Procedures for Requalification Examina-

tions," is included for your guidar.ce and information in preparing for these examinations.

This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101, which expires May 31, 1989. Coments on burden and duplication may be directed to the Office of Management and Budget Reports Management Room 3208, New Executive Office ,

Washington, DC.

Thank you for your consideration in this matter. If you have any questions on the evaluation process, please contact (Regional Section Chief and telephone number).

Sincerely, (AppropriateRegionalTitle)

Enclosures:

1. Reference Material R$,uirements

2. Administration of Requalification Examinations

3. NRC Rules and Guidance for

, Examinees DIS RIBUTION:

Project Manager Branch Chief, OLB Resident Inspector Regional Section Leader Examiner (s)

Facility Training Coordinator Facility Operations Manager l

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^g UNITED STATES

[~

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a NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20666

\...../ ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS For the written examination, the following items must be provided to the MRC 60 days prior to the examination date:

1. Propcsed R0 and SR' requalification written examinatirn test items. (A minimun, of 350 per section of the examination.)

Since the written examination is open reference, examination items must meet the following:

a. Items that require only memorization or recall are not permitted;

b. Items should require that the examinee comprehend, interpret, integrate, or apply available information;

c. Items should contain situations, aspects, or conditions that do not duplicate lesson plans or references; and

.d.

Iters should require examinees to locate and use references.

.The written examination will be composed of two sections, each designed to be completed in 1-1/2 hours. Each section will be separate. Section A

'will be administered on a static simulator; Section B will be administered in a classroom setting. Section A is designed to evaluate the operator's knowledge of plant systems, integrsted plant operations, and instrumenta-tion and controls. In addition, recognition of Technical Specification LCOs and the operator's ability to diagnose postulated events should be evaluated. Section B of the written examination is designed to evaluate the ability of the operator to analyze a given set of conditions and determine the proper procedural and/or administrative guidance.

2. All reference mate *ial and objectives for the proposed test items.

For the simulation facility, the following items must be provided to the NRC 60 days prior to the examination date:

1. A minimum of 15 scenarios The scenarios should sample areas such as LERs, emergency and abnormal procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident prevention and mitigation. The scenarios should evaluate each crew member as appropriate to his/her license, and shall exercise their abilities in the use of Emergency Operating

l Procedurcs, Technical Specifications, and the Emergency Plan. l The scenario's 1et time (not including time spent on briefings, I setup or simult . ion facility problems) should average 50 minutes, based upon real time performance.

For the plant walk through examination, the following items must be I provided to the NRC 60 days prior to the examination date: )

(1) A list of systems and topics appropriate to the plant walk through examination that were covered during the requalification cycle and are important to safety. All reference material required to support an examination on these topics should be provided.

(2) Seventy five (75) job performance measures.

These performance measures should be both in plant and control room operator functions, that are required for the safe opera-tion of the facility. They shall include acceptable performance e.riteria.

( 3.' Any additional reference material required for examination preparation will be requested by the examination team.

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a uo uq% UNITED STATES

[ j, NUCLEAR REGULATORY COMMISSION g 'j WASHINGTON, D. C. 20665

\..../ ENCLOSURE 2 ADMINISTRATION OF REQUAllFICATION EXAMINATIONS i

1. 20 percent of the facility licensed operators shall be selected for evaluation. Normally the crew currently in the requalification cycle will be selected. A random sample without replacement will be used to preclude a satisfactory operator from being subject to reexamination by the NRC during the term of the license. Thesamplewillincludeothershift(s) made up of licensed personnel who are not routinely performinc shift duties.

2. The simulator and a simulator operator (s) will be provided for exanination development. The date(s) and duration of time needed to develop the examinations will be agreed upon by the chief examiner and the facility.

3. The reference material used in the simulator will be reviewed by the chief examiner. No material will be made available that is solely used for

' training.

4. 'A single room shall be provided for completing Section B of the written

/ examination. The location of this room and supporting rest room facili-

' ties shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the examination.

5. Minimum spacing is required to ensure examination integrity as determined

'by the chief examiner. Minimum spacing should be one examinee per table, with a 3 foot space between tables. No wall charts, models, and/or other

' training materials shall be present in the examination room.

6. Copies of reference material for Section 8 of the written examination will be provided for each examinee. The refertnce material will be reviewed by the chief examiner and will consist of Technical Specifications, operating / abnormal procedures, administrative procedures, Emergency Plans as available to the plant operators.

7. Video taping capabilities can be utilized. The facility should contact the chief examiner for restrictions related to its usage.

8. Since connon tasks and detailed systems knowledge will be probed during the walk through portion of the operating test, operators will be re- l quested not to discuss the walk through with other examinees until after the complete examination has been administered.

9. An attempt will be made to distinguish between R0 and SR0 knowledge and abilities, to the extent that such a distinction is supported by the facility training materials.

1. 'o,, UNITED STATES I

!' o NUCLEAR REGULATORY COMMISSION l

{ ,

WASHINGTON, D. C. 20665

%,...../

ENCLOSURE 3 NRC RULES AND GUIDANCE FOR EXAMINEES

1. Use black ink or dark pencil ONLY to facilitate legible reproductions.

2. Print your name in the blank provided on the cover sheet of the examination.

3. Fill in the date on the cover sheet of the examination, if necessary.

4. Answer each question on the examination. If additional paper is required, use only the lined paper provided by the examiner.

5. Use abbreviations only if they are co inonly used in facility literature.

6. 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.

7. Show all calculations, methods or assumptions used to obtain an answer to

'a mathematical problem, whether asked for in the question or not.

8. Unless solicited, the location of references need not be stated.

9. : Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWERS BLANK.

10. If parts of the examination are not clear with respect to their intent,

'ask questions of the examiner only.

11. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that .you have not received or been given any assistance in cottpleting the examination. This must be signed AFTER the examination has been completed.

IP. Rest room trips are to be limited and only one examinee at a time may l leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination  !

compromise.

13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.

14. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for a total of four hours. i i

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15. Ne existence of questions that will require all examinees to refer

... ... a indications or controls, particular care must be taken to r, '

Individual examination security and avoid any possibility of cc +  ; e or appearance of cheating. ,,

1

16. When you are finished and have turned in your completed examination, l leave 1:;e examination area.  :

O e

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ATTACHMENT 2 EXAMINEE CRITIQUE OF NRC REQUALIFICATION EXAMINATION As part of its efforts to improve all aspects of the NRC requalification examination process, NRC is asking all test-takers to provide feedback on these examinations. Please use this form to comment on the NRC requalification examination that you have just completed. After you have answered the questions below, and provided any comments that you wish to make, please give this form to your training manager who will send it to the NRC Regional Branch Chief.

Please take a few minutes and respond to each of the following questions, by circling the number that best represents your experience on the examination just completed. Each question is written in the form of a statement, and the number which you circle indicates how strongly you agree or disagree with that statement. For example, if you circle number 1 for a perticular question, that indicates that you are in strong agreement with the statement. If you circle number 4, that indicates mild disagreement. If you circle number 3, that indicates that you neither agree nor disagree with the statement made in that question.

THERE ARE NO RIGHT OR WRONG RESPONSES. Your participation is strictly voluntary, but please remember that your responses, together with any comments that you might have, will help to improve the requalification examination process. All responses are anonymous.

WRITTEN EXAMINATION:

1. 'The content of the questions reflected the content of the requalification

, program at my plant.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

1

L

2. The overall time allotted for the examination was sufficient to answer all the questions.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

1.

3. The information to be used to answer each question was available.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

4. There was an opportunity for me to have any questions regarM aa the

. examination clarified prior to the end of the examination.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

2

OPERATING TEST:

. l. The content of the JPMs and the questions on the walk-through portion was consistent with the content of the requalification program at my plant.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

2. The overall time allotted for the walk-through portion of the operating test was appropriate.

Strongly agree Strongly disagree I

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. 1 2 3 4 5 Comments:

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3. The-scenarios used for crew evaluation on the simulation facility portion of the operating test were consistent with team (crew) training at my plant. l Strongly agree Strongly disagree l 1 2 3 4 5 Comments:

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4. The instructions for the conduct of both portions of the operating test were clearly explained by the examiner (s).

Strongly agree Strongly disagree 1 2 3 4 -5 s

Comments:

ADDITIONAL COMMENTS ON THE CONTENT AND/0R CONDUCT OF THE NRC REQUALIFICATION WRITTEN EXAMINATION AND OPERATING TEST JUST COMPLETED:

1 PLEAsE CIRCLE THE LEVEL OF THE EXAMINATION JUST COMPLETED: R0 SRO PLEASE 00 NOT INDICATE YOUR NAME ON THIS QUESTIONNAIRE.

THANK-YOU.

l This request is covered by Office of Management and Budget Clearance Number 3150-0011 which expires December 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Room 3208, New Executive Office Building, Washington, DC 20503.

4

ATTACHMENT 3 INSTRUCTIONS ON USE OF SIMULATOR CREW EVALUATION FORM Enclosed is an evaluation form for use dJring the trial simulator examination component of the requalification examination. In keeping with the purpose of the requalification exam, these scales are geared toward evaluating the crew as a whole, rather than individual operators, Please follow the instructions below when rating team performance on the simuletor examination:

1. Review the rating scales prior to the onset of the simulator examination to familiarize yourself with each performance issue to be evaluated.

2. Use the "Operator Actions" Form (ES-302, attachment 6), and the expected operator actions included on that form, to make notes during the examination, as described in ES-302.

3. Immediately after the simulator examination is over, evaluate the crew by completing the Simulator Crew Evaluation Form. Be sure to address all the rating factors for all 6 concetencies.

4. Provide an overall roting of "satisfactory" or "unsatisfactory" for each competence. If you gave the crew more than one rating of "1" on the rating f actors for that competence, your score for them on that competence overall should ce "unsatisfactory." Although part of the purpose of the walk-through is to follow up on areas of weakness noted during the simulator portion of the excmination, if the crew receives a rating of "unsatisfactory" on one or more competences, their overall evaluation should also be unsatis factory.

, 5. There is space for comments beneath each competence rating and below the overall rating. This space is provided if you feel the need to annotate or explain rating (s). In particular, use this space to document the failure of an individual candidate due to his/her exceptionally poor performance.

We need your feedback to evaluate the usefulness of these ratings scales.

Af ter you have had an oppot tunity to use the form, please provide us with the following information:

Were the scales clear, concise, and easily understood?

-Were the scales written so that you could evalaate crew (versus individual) performance?

Could you comfortably decide which ratings to give the crew, based on the decriptions of the performance provided? If not, how could these descriptions be improved? l Were there rating issues which you believe are not appropriate for simulator requalification examinations?

Were there any performance issues missing from these rating scales?

Please note your comments and suggestions on the page provided at the back of the evaluation form and provide them to John liannon at the exit meeting.

Thanks very much for your assistance.

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SIMULATOR EXAMINATION

SUMMARY

SHEET CREW MEMBERS:

Name Position

,t OVERALL TEAM RATING ON THE SIMULATOR EXAMINATION:

Satisfactory Unsatisf actory Comments:

Please use the space below to note your comments on the. evaluation form-(attach additional pages, if necessary):

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UNDERSTANDING / INTERPRETATION OF ANNUNCIATOR / ALARM SIGNALS DID THE CREW:

l (a) NOTICE and ACKNOWLEDGE alarms, and ATTEND T0 alarms in order of their importance/ severity?

3 2 1 All alarms that directly Minor awareness or failed to notice related to significant response difficulties and/or extremely changes in plant or lapses slow at responding conditions were noted to significant.

alarms at critical times; easily distracted by nuisance alarms (b) Correctly INTERPRET the meaning and significance of alarms and annunciators (including the use of the Alarm Response Procedures, as applicable)?

3 2 1 Crew'readily determined Minor inaccuracies in Significant misin-what failures / events alarm interpretation terpretations, alaris were indicating but without safety resulting in plant related co1 sequences degradation (c) l VERIFY that annunciators / alarm signals were consistent with plant / system conditions?

3 2 1 All necessary verifi- Minor lapes in alarm Verification of cations performed, verification, but no failed systems including the identi- inappropriate actions was poor or fication of erroneous taken as a result of altogether absent alarms inadequate verification SCORE ON UNDERSTANDING / INTERPRETATION OF ANNUNCIATORS / ALARM SIGNALS:

Satisfactory Unsatisfactory Comments:

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l DIAGNOSIS OF EVENTS / CONDITIONS BASED ON SIGNALS / READINGS DID THE CREW:

l (a) RECOGNIZE off-normal trends / status?

3 2 1 Timely and accurate Recognition of trends -Failed to recognize recognition of trends at time of, but not trends, even after even prior to alarms prior to, sounding of sounding of alarms and alarms annunciators (b) USE INFORMATION and use REFERENCE MATERIAL (prints, books, charts) to aid in the diagnosis /classificaticn of events and conditions?

3 2 1 Correct, timely use Minor errors by crew Failure to use of information and in use or interpretation reference material, reference material of information and misuse / misinterpretation led to accurate reference material of information resulted diagnoses in improper diagnoses (c) . Correctly DIAGNOSE plant conditions based on those control room indications?

3 2 1 Diagnoses by crew Minor errors /diffi- Faulty diagnoses were accurate and culties in diagnoses resulted in timely incorrect control manipulations SCORE ON DIAGNOSIS OF EVENTS / CONDITIONS BASED ON SIGNALS / READINGS:

Satisfactory Unsati s f actory Comments:

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UNDERSTANDING OF PLANT / SYSTEMS RESPONSE DID THE CREW: l (a) LOCATE and INTERPRET control room indicators correctly and efficiently to ascertain and verify the status / operation of plant systems?

3 2 1 Accurate and efficient Minor errors in locating Serious omissions instrument location & or interpreting instruments delays or inaccuracies interpretation by all and displays; some crew made in instrument crew members members required assistance interpretation (b) Demonstrate an UNDERSTANDING of how the plant, systems, and components operate, including setpoints, interlocks, and automatic actions?

3 2 1 All crew members demon- Minor instances of errors Inadequate knowledge strated thorough due to gaps in crew of system / component understanding of how knowledge of system / operation resulted in systems / components component operation; some serious mistakes or operate crew members required plant degradations

, assistance (c) . Demonstrate an understanding of how their ACTIONS (or inaction) affected system / plant conditions?

I 3 2 1 All members understood Actions or directives Crew appeared to act the effect that indicated minor without knowledge of,  !

actions or directives inaccuracies in under- or disregard to, effect had on plant / system standing by individuals, on plant conditions but actions were corrected by team SCORES ON bdDERSTANDING OF PLANT / SYSTEM RESPONSE:

Satisfactory Unsatisfactory

)

Comment:

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l COMPLIANCE /USE OF PROCEDURES AND TECHNICAL SPECIFICATIONS l

DID THE CREW:

(a) REFER T0 the appropriate procedures in a timely manner?

3 2 1 Crew used procedures Minor failures by Failed to correctly as required; knew crew to refer to refer to procedures when what conditions were procedures without required, resulting in covered by procedures prompting, but did faulty system operation and where to find them affect plant status (b) CORRECTLY IMPLEMENT procedures, including following procedural steps in correct sequence, abiding by cautions and limitations, selecting correct paths on decision blocks, and correctly transitioning between procedures?

3 2 1 Timely, accurate Minor instances of Importance procedural enactment of procedural misapplication, but steps were not enacted steps by crew, corrections made in correctly, which led demonstrating thorough sufficient time to to impeded and/or slow understanding of avoid adverse impact recovery or unnecessary procedural purposes / bases degradation (c) '. RECOGNIZE E0P ENTRY CONDITIONS and carry out appropriate immediate actions without the aid of references or other forms of assistance?

I 3 2 1 1 Consistently accurate Minor lapses or Failed to accurately and timely errors; individual recognize conditions I recognition and crew members needed or execute actions, I implementation assistance from others even with use of aids to implement procedures (d) CORRECTLY RECOGNIZE and COMPLY with Technical Specifications and Action l Statements of LCOs?

3 2 1 Recognized and Minor difficulties in failure to recognize /

fully complied with referring to and/or comply with Tech Spec LCOs/ Action Statements applying Tech. Specs.; LCOs crew had to prompt SRO on TS requirements SCORE ON COMPLIANCE /USE OF PROCEDURES AND TECHNICAL SPECIFICATIONS:

Satisfactory Unsatisfactory Comments:

l s

CONTROL BOARD OPERATIONS DID THE CREW: ,

(a) LOCATE CONTROLS efficiently and accurately?.

3 2 1 Controls and Instances of Instances of failure i indicators were hesitancy / to locate controls  :

located without difficulty in jeopardized system hesitation by locating controls status individual operators by one or more operators (b) MANIPULATE CONTROLS in an accurate and timely manner?

3 2 1 Smooth manipulation Minor shortcomings Mistakes made in of the plant in manipulations, manipulating controls within controlled but recovery from caused sy-tem parameters errors without transients and causing problems related problems (c) 'Take MANUAL CONTROL of automatic functions, when appropriate?

3 2 1 All cperators took Minor delays and/or Failed to control  ;

control, and smoothly prompting necessary automatic systems operatored automatic before overriding / manually, even when systems manually, without operating automatic ample time and i assistance, thereby functions, but plant indications existed averting adverse events transients were l avoided when possible  !

SCORE ON CONTROL BOARD OPERATIONS:

Satisfactory Unsatisfactory Comments:

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i COMMUNICATIONS / CREW INTERACTIONS l 010 THE CREW:

(a) EXCHANGE complete and relevant information in a clear, accurate, and '

attentive manner?

3 2 1 Members informed each Communications generally Members did not other of relevant info, complete and accurate, inform each other and actively sought and but some instances of of abnormal indica-listened to info. from needing to be prompted, tions or when others as/when necessary or failing to acknowledge performing evolutions; or respond to info. from inattentive when others important info. was requested or provided (b) INTERACT with other regarding issues / circumstances outside of their individual area of responsibility to facilitate safe plant conditions?

3 2 1 Members assumed Members listened to Members were responsibility for each others conversations inattentive to what issues outside their in general; major technical was happening own boards, as errors corrected around them; poor appropriate coordination of activities (c) ,MAKE TEAM DECISIONS in a timely, effective manner?

3 2 1 All individuals provided Major team decisions Leader or other crew input to decisions, generally included members did not accept i Decisions resulted in early, input from most crew input from others, recuperative action members, but some resulting in incorrect delays or other or untimely decisions /

l problems in reaching directives effective decisions SCORE ON COMMUNICATIONS / CREW INTERACTIONS:

Satisfactory Unsatis f actory Comments:

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r ATTACHMENT 4 JOB PERFORMANCE MEASURE WORKSHEET' facility:

Task

Title:

Task No.:

' Job Performance Measure No.:

K/A

Reference:

Operator:

Evaluator: Date:

Applicable methods of testing:

Simulate performance Actual performance Classroom Simulator Plant ,

READ TO THE OPERATOR I wi11 explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be. satisfied.

Initial Conditions:

Task Standards:

Required Materials:

General

References:

Initiating Cues:

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PERFORMANCE INFORMATION

- (Denote critical steps with a check mark)

Performance step:

P Standard:

i Comment:

L Performance step:

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Comment:

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Standard:

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VERIFICATION OF COMPLETION- l 4

-l Job Performance Measure No.

. Operator's Name:  !

Date performed:  !

Evaluator:

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' Number of attempts:

Result: - (Denote by an S for satisfactory or _a U for unsatisfactory and ;

requires remedial training).

Evaluator's signature and date: ,

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ATTACHMENT'S SYSTEM WALK-THROUGH TEST PLAN Page_of_

Facility: System Topic: Performance Measurement:

Question  : KA Rating Answer:

Response /Coments:

Question  : KA Rating ,

Answer:

Response /Coments:

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t Question  : KA Rating i

Answer:

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Response / Comments:

l Question  : KA Rating l Answer: _

i Response / Comments:

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^

SYSTEM WALK-THROUGH FOLLOW-UP DOCUMENTATION Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement ,

2. Question Number l Question (to be completed during exam):

1 Response (to be completed during exam):

Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam): ,

Response (to be completed during exam):

Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

, Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam):

Response (to be completed during exam):

Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam):

Response (to be completed during exam):

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l ATTACHMENT 6 BRIEFING CHECKLIST - SYSTEM WALK-THROUGH

1. If the NRC examiner is a visitor, escort responsibility for ensuring compliance with safety, security and radiation protection procedures is the responsibility of the operator escorting the examiner.

2. Plant equipment should not be operated. Nothing the facility or NRC examiner says or asks will be intended to violate that principle.

3. If clarification of questions is needed during the walk-through, there should be no hesitation to request the examiner reword or clarify the question.

4. The examiner will be taking notes throughout the test to document operator performance. Frequently an examiner will stop questioning for this purpose.

The amount of note-taking is not dependent upon the operator's level of performance. The examiner must document satisfactory as well as less than satisfactory performance. 1

5. The walk-through is considered "open book." The reference material in the facility / control room which is normally available to operators is available, including calibration curves, previous log entries, piping and instrumentation

' diagrams, calculation sheets, and procedures. However, operators are respons- ,

,ible for knowing from memory the immediate actions of emergency and other I

. procedures as appropriate to the facility.

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6. 'The system walk-through has been planned for approximately two hours in length. However, there is no specific time limit for the walk-through.

,The examiner will take whatever time is necessary to cover the areas

, selected, in the depth and scope required. There will be a minimum cf 4 Job Performance Measures (tasks) evaluated from the control room and 4 ,

Job Performance Measures evaluated outside of the control room. However, )

the total number of JPM's will be no less than ten (10).

7. The examiner will explain what tasks are to be completed, which steps to simulate or discuss arid provide initial conditions. The operator is to proceed with completing the task as if directed by plant procedures and/or shift supervision. During the task the examiner will supply the necessary plant conditions and/or parameters needed to simulate the task. The operator should explain each step of the task to the examiner before doing it.

8. When all of the steps for each task are performed correctly, the criteria for the examination will have been completed.

9. If the operator feels the need for a break during the walk-through, the operator should request this from the examiner. The examiner is not allowed to reveal the results of the walk-through at its conclusion.

10. The NRC examiner may ask clarifying questions of the operator at the end of each JPM.

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Part 8 - For tests with simulation facility available

1. The primary responsibility is to operate the simulation facility as if it were the actual plant.

2. Team work and communication between operators is evaluated. It benefits the exam process to verbalize observations, analysis, and reasons for actions more than normally would be done during actual plant operations.

3. If an operator recognizes an incorrect decision, response, answer, analysis, action taken, or interpretation of the team of which the operator is a part but fails to correct, then the examiner may dssume that that operator agrees with the incorrect item.

4. A rough log may be kept during each exercise that would be sufficient to complete necessary formal log entries which may be evaluated under admin-istrative topics.

5. A designated facility instructor will act as the auxiliary operators, radiation health and chemistry technicians, maintenance supervisors, plant management, and anyone else needed outside the control room area.

6. The facility examiner will provide a shift turnover before the exercise begins. The shif t turnover will include present plant conditions, power history, equipment out of service, abnormal conditions, surveillance due,

'and instructions for the shift.

7. 'The control board switches may be purposely misaligned to enhance a simulated scenario or transient where appropriate and is not part to the evaluation. If misaligned, they should be tagged or otherwise highlighted as appropriate to the facility. The examiner will rot misalign switches lduring the scenario as an awareness drill.

Note: The chief examiner has the option to tell the operators that no control board switches will be misaligned on a given scenario or set of scenarios.

If no switches are misaligned, the chief examiner may wish to reduce the time it takes of the operators to complete the board walkdown and accept the shift.

8. Operators will be alluwed three to five minutes to familiarize themselves with the status / conditions of the control boards prior to the start of the exercise.

9. The simulation facility part of the examination will consist of a minimum of two exercises lasting approximately 50 minutes each. There will be a short break between exercises to set up the initial conditions for the next exercise.

10. If operators have any questions concerning the administration of the operating test, those questions should be answered prior to the start of the test.

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ATTACHMENT 7 U. S. NUCLEAR REGULATORY COMMISSION ~

REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

REACTOR TYPE:

DATE ADMINISTERED: -4 OPERATOR:

% 0F SECTION CATEGORY OPERATOR'S CATEGORY VALUE SCORE VALUE A Plant Proficiency B Limits and Controls l Final Grade I

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ATTACHMENT 8 JOB PERFORMANCE MEASURE QUALITY CHECKLIST

1. Supported by facility's job / task analysis.

2. Operatierelly important (meets threshold criteria of K/A 3.5 or as determined by the facility and agreed to by NRC).

3. Designated as either SRO only or both R0/SRO.

4. Time validated (time allowed for task completion indicated on JPM).

Questions related to the task need not be time validated.

5. Either the task itself or the questions that follow require operator problem recognition and diagnosis. Questions require knowledge correct

.' actions for abnormal system responses whenever applicable.

6. Perforr.ance standards are specific in that exact control end indication nomenclature and criteria (switch position, meter reading) are specified, esen if such criteria are not specified in the procedural step.

7. Critical elements and associated performance standards are identified and agreed to by the facility and the NRC.

8. Performance standards should provide complete and proper system response cues where appropriate such that the examiner can properly cue the operator when asked.

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9. Answers to questions at the end of the task are NOT found directly in the procedure just used (i.e., do not ask why a certain caution exists if the cautionitselfidentifiestheanswer).

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ATTACHf1ENT 9 Rey 1 4/15/88 SIPULATOR SCENARIO REVIEW CHECKLIST

( Attach separate copy to each scenario reviewed)

SCEf;ARIO IDENTIFIER: REVIEWER:

1. Scenario contains at least one (1) time-critical crew response.

Time-critical is defined to require affirmative action by one or more crew member (s) in order to prevent or mitigate an event within a limited time.

2. Scenario contains at least one (1) team-dependent crew response.

Team-dependent is defined to require transfer of information between crew members in order to prevent or mitigate an event.

'3. The scenario events involve each crew member.

4. Scenario is composed of related or linked events.

5. Scenario requires the use of: (check those that apply)

Abnormal operating procedures l

Emergency operating procedures Technical Specifications Emergency plan implementing procedures j

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6. Critical tasks are:

i Identified by facility ,

i Required to prevent or mitigate event-Importance . factor . 3.5 in K/A Catalog or facility JTA ,

7. Scenario events have K/A importance factor- 3.0 1

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ATTACHMENT 10 GUIDELINES FOR THE DEVELOPMENT AND REVIEW 0F OPEN REFERENCE EXAMINATIONS

1. Introduction The following guidelines are intended for those who are involved in the development and/or review of test items for the written portion of the NRC Requalification Examination. As described in ES-601, "Administration of HRC Requalification Program Evaluations," the written examination consists of two sections, one that utilizes the simulator to provide a context for questions on plant systems and controls, and a second that focuses on plant procedures and administrative controls. Both sections are administered in an "open reference" format. Candidates are allowed to use reference material, including simulator displays, during examination administration.

The intent of the change from closed to open reference written examinations, is twofold:

(1)ExaminationValidity. By permitting the use of references that are available to the operator, the conditions and requirements of the written examination more closely approximate those of the actual job. The information provided to the operators in the test items can and should closely ,

parallel the information typically available to them on the job, while the responses elicited by the questions should be similar or identical to the decisions, solutions, and actions required for effective job performance. In other words, the open reference format enhances the match between job demands and test demands -- a cornerstone of examination validity. )

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(2) Level of Knowledge. The open reference format also enhances examination validity by elevating the level of knowledge of the test items. As described later in these guidelines, candidate access to references precludes the use of questions that test for the mere recall of facts and specifics. Instead, open reference test items require test takers to demonstrate that they can apply, analyze, evaluate, or otherwise USE knowledge to handle the problems and issues encountered on the job.

11. Open Reference Guidelines Most principles for effective test item construction apply equally to all types of written questions, regardless of fonnat. Therefore, open reference test item developers and reviewers should consult references such as NUREG BR-0122, "Examiners' Handbook for Developing Operator Licensing Examinations,"

INP0's "Principles of Training System Development Addendum I, Test Item Development," and NUMARC's "Guidelines for Developing Written Test items for the NRC Requalification Exam." The guidelines below are those that have been found to be especially pertinent to the creation of open reference test items. These guidelines are divided into five categories:

(1) Selection of Test Topics (2) General Guidelines for Sections A 8 B (3) Specific Guidelines for Section A, "Plant Operations" (4) Ideas for Open Reference Formats (5) Open Reference Test Item Review Checklist (1) Selection of Test Topics Test item topics for the NRC requalification examination should be selected based on the following criteria.

A. R_equalification Training Program Curriculum. Test topics should be based on the curriculum of the most recent operator requalification program training cycle. However, NRC may substitute up to 20% of the examination topics selected by tne facility with subjects not emphasized during the requalification cycle under 10 CFR 55.59.

B. Performance Basis. Like the requalification program itself, test topics should be drawn from a job-task analysis (JTA) of the operator and senior operatcr positions. The facility should validate their test items by demonstrating a link between each iten and the following JTA products:

important operator tasks as identified by the JTA important K/As (rated 3.0 or higher) as identified in the NRC K/A Catalog (NUREG 1122/1123) or e facility-specific K/A catalog facility learning objectives identified as important to safety C. Adequacy o_f Test Coverage. The facility's proposed sampling plan (or curriculum evaluation plan) should by checked to ensure that it provides balanced, cocprehensive coverage of the topics covered during the requalificaticn training cycle. Facility test item topics may be revised if subject areas are found to be under or over-represented in the sampling plan relative to their coverage in the requalification program. In addition, 20% may be substituted by the NRC. Recent safety-related issues and events (e.g., relevant LERs) shou d be addressed in the sampling plan.

(2) heneralGuidelines The following guidelines should be followed in the construction and review of test items for both parts of the written examination. These guidelines are intended to supplement, not replace, the good practice criteria found in NUREG BR-0122 and related documents.

l A. Operational Orientation. As discussed earlier, examination validity is enhanced to the extent that the demands of the test match the demands of the job. Therefore, in addition to being derived from important X/As and testing objectives, the context and stipulations of test items should mirror the situations encountered in the work setting. The following example illustrates effective and ineffective ways to design test items from K/As and learning objectives.

K/A: Knowledge of the design attributes of the Turbine Driven Auxiliary Feedwater Pump Differential Pressure Controller.

Task: Operate the TDAFWP controls during all modes of plant operation.

Terminal Learning Objective: The student will be able to operate the TDAFWP Differential Pressure Controller without error during a loss of feedwater event.

Enabling Objective: Upon completion of this lesson, the student will be able to explain the operation of the TDAFWP Differential Pressure Controller.

Poor Test Item: State the parameters used by the TDAFWP Differential Pressure Controller.

Better Test Item: Priortoisolatingthe"C"steamgenerator(perEPP11),it was n,oted that the transducer-fed auxiliary feed flow indicators for the "C" steam generator were reading greater than the flow indicators to the "A" and "B" steam generators. What is the reason for this flow deviation?

Notice that the second test item requires the candidate to demonstrate mastery of the knowledge by applying it to an actual job situation. In developing items, it may be useful to ask oneself "why is the K/A important to satisfactory job performance?" and "in what situation will be operator need this K/A?" The answers to these questions can provide a basis / context for test items.

B. Level of Kvwledge. The operational orientation required of test items on the open reference examinations, as well as the candidates' access to controlled documents, precludes the use of questions that test for mere recall or memorization. Rather than requiring candidates to simply recognize or recall facts and specifics, open reference test items should have the candidates demonstrate understanding by requiring them to use their knowledge to address real-life situations and problems. A test item at the l

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higher level of knowledge requires candidates to determine or identify the appropriate fact, rule, or principle to a novel situation and then correctly apply it. A description of each level cf knowledge, along with comon verbs and example questions, is found in Table 1.

C. Realistic Context. Tc provide additional assurance of examination validity, the situation or problem posed in the open reference test item should be as similar as possible to the actual situations that candidates encounter or. the job. Situations described in the questions should not only be realistic, but should also be free of comon "context" problems, including "backwards logic" and "window dressing."

Backwards logic questions provide candidates with infonnation they normally have to produce, while asking them for information they normally receive. For example:

K/A: , Ability to calculate snutdown margins.

Backward Logic Item: Given a shutdown margin is 5.5%, how long has the unit been shut down?

Better Iter: The unit has been shut duwn for x hours. Calculate the shutdown margin.

1 Questions with window dressing have additional, unnecessary information, typically in an attempt to make a memory level item more operationally j oriented. For example:

Item with Window Dressing: The plant has tripped due to the effect of a tornado crossing the site boundary. You, as Shift Supervisor, direct the phor,e talker to complete the 15 minute notifications. He informs you that the normal notification network is inoperable. What method do you direct him to use for completing the 15 minute notification?

Revised Iter: If the norrial notification network is inoperable, what methed dc you direct the phone talker to use to complete the 15 rinute notification after the plant has tripped?

Another common problem when constructing questions with realistic contexts is that quite often "real world" situations have more than one correct solution or response. Check the question and references over carefully to ensure that each' test itesi has only one correct answer.

4 D. Q'vestion Novelty. One of the most effective ways to ensure that candidates have higher levels of knowledge is to present them with novel situa'tions and recuire them to both realize what information is relevant and how to apply it. If test questions do not contain unique or varied circumstances compared to that which was presented in training, the item will be reduced to simple recall. Review the training material to ensure that i questions do not include overly familiar conditions. Keep in mind, however, that all conditions and situations should be reasonable, realistic, and safety-related. l E. Use of References. References should be considered tools that candidates use to solve problems. It should be the proper use of these tools that is l

tested during the open reference examination, not the recall of facts and j specifics. Purely "look up" questions should not be included in the examination; rather, questions should be restricted to those that test to see if candidates can identify, locate, or select appropriate reference information to produce organized responses and satisfactory solutions to job related problems and issues. For example:

Pure "Look up" Item: In the event that a safety limit is violated, the reactor shall be:

a. placed in a hot shutdown condition within I hour

b. placed in a hot shutdown cor.dition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

c. placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

d. placed in a cold shutdown condition within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Better Use of

References:

While operating at 1001 power, VCT and pressurizer alarms and indications show decreasing pressurizer level. Also, the blowdowr and main stean radiation monitors have alarmed. While following the appropriate Abnormal or Emergency Procedures, you as tha Shift Supervisor must evaluate the existing condition, l

Based on this information, the following emergency classification should be declared:

,a. Notification of Unusual Event

b. Alert

c. Site Area Emergency

d. General Emergency F. Difficulty Level. It is not unusual for i :st constructors to believe, erroneously, that open reference test items should be more difficult, to compensate for the candidates' access to reference material. Frequently, this increased difficulty is in the form of requiring knowledge of more obscure or  :

otherwise unnecessary inforration. Both open and closed reference examination l items should have the same standard of difficulty; that is, difficulty should be based on the job demands and responsibilities of operators.

G. Time Limits. Relative to closed reference examinations, candidates take considerably longer to answer open reference test items. (Weakercandidates especially have been found to spend an appreciable amount of exam time

corisulting references versus writing responses). It is impcrtant to provide candidates an ample amount of time to complete the exanination, although not so much time as to allow less than competent operators the opportunity to locate answers without prior familiarization. The following guidelines should be used to deternine the appropriate length of the examination:

1. Each two hour examination section should be constructed to take a competent operator an expected I hour 15 minutes to complete.

2. Wher, possible, the response tine of each question should be estimated by having a subject matter expert actually answer the question, including searching through references.

H. Correct Mode of Measurement. No matter how high their importance ratings or operational relevance, certain operator knowledges, skills and abilities are not amer.able to written testing. For example:

Arrange the major steps in the proper secuence to start, parallel, and l'oad 06 2:

Use Governer Control to increase DG.2 KW Raise DG Speed to 900 RPM Press start button on AI30B Match Voltage with Bus IA2 Voltage Close Breaker IAD2.

Despite its operational orientation, the underlying skill addressed in the l above test item would be better assessed by having the candidate simulate or step l l

through the steps during either the simulator or walkthrough portions of the l

operating examination. Table 2 provides an overview of the best uses for each test mode. Make sure that the K/As and learning objectives selected for the written examination can be effectively measured during the written testing.

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(3) Specific Guidelines for Section A, "Plant Operations" The following guidelines are specific to the Plant Operations section of the written examination, performed on a static simulator. These guidelines are divided into two sections, Question Development and Simulator Setup.

Question Development

a. To ensure that the operators' knowledge of plant operations is adequately evaluated, Section A of the written examination should address a mix of normal, abnormal and emergency modes of ope-ation,

b. Questions should require the operators, to tne extent possible, to refer to control room indications in formulating their responses, as in the following example:

Which one of the following describes the location of the steam break?

(a) Insice containment, upstrean of the steam line flow transmitters

('b ) Inside containment, downstream of the steam line flow transmitters (c) Outside containment, between "C" MSIV and "C" main steam line check l

valve.

(d) Outside containment, between "C" MSly and "C" main steam line containment penetration. {

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The nurt)er of scenarios used should be minimized due to the extensive amount of time necessary to set up, run and check the transients, d.

The nust>er of malfunctionr/ failures for each scenario should be limited. In general, the scenario should contain one major failure (e.g.,

LOCA,SGTR,steamlinebreaks,ejectedcontrolrods,lossofallACpower).

In addition to the major failures, no more than four minor failures should be used (e.g., failure of a safety related pump to start, failed pressurizer

pressure meter indication, nuclear instrumentation failure). In many cases, one major failure and 2-3 minor failures will provide sufficient effects to test a wide range of objectives.

e. Questions may be used that do not relate to the transient but use the simulator as a frame of reference only, provided the candidates are aware of this lack of relationship to the transient.

f. Special attention should be given to ensure that multiple questions stemning from one event do not suffer from double jeopardy. The candidate should be able to be understand and correctly answer each question based only on the information given in the question, rather than on the answer to a previous question.

Simulator Setup g .' Prior to the test, the simulator recorders should be rotated to provide clean readings, and the recorders should be checked for proper operation,

h. All indications should be checked (e.g., bulbs, meters, manual loader indications, etc) to ensure they are in proper working order.

i. When the simulator has been frozen, the chart recorder drive power should be secured, if necessary. l l

J. Prior to administering the test, the simulator indicat'ons should be verified proper based on expected question responses,

k. Any "first-out" annunciaters that would normally blink to announce first-out conditions should be frozen and provided to candidates.

1. If a transient is stabilized by use of plant procedures, the step at which the simulator is frozen should be noted and this information recorded on the simr' Or operations summary sheet. Progress of the procedure step in e:iect should also be given to the examinees as necessa ry.

(4) Ideas for Open Book Formats.

Table 3 provides a list of sample formats to assist question developers in

, generating performance-based, open reference test items, h

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l TABLE 1 LEVEL OF KNOWLEDGE DESCRIPTIONS AND EXAMPLES

1. MEMORY The memory level involves the recall of facts and specifics, the recall of rrethods and processes, or the recall of a pattern, structure, or setting.

For measurement purposes, the recall situation involves little more than bringing to mind the appropriate material. Appropriate verbs include:

To define To develop To distinguish To outline

. To recall To identify To recognize To list For the operator licensing examination some examples include:

State the basis for a procedural step or caution.

State the basis for a procedural change.

State the purpose of a specific procedure.

Items that require only memorization or recall are not permitted on open-reference examinations.

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2. COMPREHENSION Comprehension represents the lowest level of true understanding. It refers to a type of understanding such that the individual knows what is I

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being comunicated and can make use of the material without necassarily i relating it to other material or realizing its fullest implications. Appropriate verbs include: l To translate To estimate To prepara To differentiate To cc:nprehend Tc explain To interpret To sumarize To grasp To demonstrate by example To distinguish To see implication effects, and consequence Questions based at this level and above are permissible to ask on an open-reference examination.

3. APPLICATION 4

These types of questions require candidates to apply the knowledge to various c'oncrete situations. The knowledge may be in the form of general tdeas, rules of procedures, or generalized methods. Appropriate verbs include:

To apply To predict To employ To use To relate To develop For the operator licensing examination examples of this cognitive level would include:

Calculation of plant parameters.

Use of reference material such as graphs, charts, curves, etc.

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4. ANALYSIS The analysis level involves the breakdown of a comunication into its constituent elements or parts such that the relative hierarchy of ideas is made clear l

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and/or the relations between the ideas expressed are made explicit.

Appropriate verbs include:

To discriminate To categorize To analyze To choose To detect To discover To infer To select

5. SYNTHESIS Synthesis involves the putting together of elements and parts so as to form a whole. Appropriate verbs include:

To create To perceive To propose To organize To integrate To prepare To plan To compile To design To incorporate To synthesize To visualize

6. EVAL.UATION The evaluation level involves judgment about the value and methods for given purposes. Appropriate verbs include:

t To judge To evaluate To assess To decide To compare To determine To appraise Evaluation is the optimum level of open-reference procedures questions.

Typically questions at this level would propose a situation and require the operator to use analysis and synthesis to formulate judgments / decisions about appropriste actions.

____mm____._mm._. __._____ ____ _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . ________.m___ _ _ _ . __ _ _ _ . _ _ . _ _ _ _

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EXAMPLES A , knowledge level question, requiring the operator to respond from memo.y on the basis of a caution:

A caution at the beginning of FRP-H.1 requires RCS bleed and feed to be started at STEP 9 if ANY S/G wide range level decreases to less than 60%

[63%). Which item below is the basis for this caution?

A) Steps 1 through 8 deal only with diagnostic evaluation of the event and may be time consuming.

B) Steps 1 through 8 consist of a "loop" that is difficult to exit from.

C) Wide range level is not calibrated (therefore not accurate) for 60%[63%).

D) This level assumes S/G dryout is inninent and RCS bleed and feed must .

be started immediately for core cooling. l i

A comprehension level question, requiring the operator to differentiate between types of turbine runbacks.

Indicate what type of turbine runback occurred: LOAD LIMIT, LOAD REFERENCE < BOTH.

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The following question falls into the _ application level (i.e., applying a procedure).

HBR Unit #2 is at 1001 power, steady state. The HP.97 calculator in the control room is 00S. Based on the values given below, determine the "QUADRANT POWER TILT" as defined in Technical Specifications.

NORMAL UPPER DETECTOR CURRENTS N-41 = 230 N.42 = 235 N-43 = 232 N.44 = 236 NORMAL LOWER DETECTOR CURRENTS N-41 = 233 N.42 = 238 N-43 = 231 N-44 = 240 PRESENT INDICATED DETECTOR CURRENTS UPPER LOWER N-41 232 236

'N.42 238 243 h'-43 235 234 N-44 239 243 The following question is at the analysis level, it requires the operator analyze conditions and discriminate an idea:

Determine the posting required for a room using the results of the following radiological survey:

)

1. AIRBORNE ACTIVITY: 6.34E.9uci/cc(Co-60)

2. FLOOR SMEAR: Beta. 610 dpm/cm squared; Alpha. 4dpm/cm squared

3. EQUIPMENT SMEAR: Beta- 1800 dpm/cm squared: Alpha. 16 dpm/cm squared

4. GENERAL RADIATION LEVEL: 110 mr/hr

The following question represents the synthesis / evaluation level -- putting together of elements and parts to form a whole:

Determine if plant conditions satisfy the requirements of foldout "B" S1 TERMINATION CRITERIA. Justify your answer with specific values of any required plant parameters.

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TABLE 2 '

OVERVIEW 0F THE BEST USES FOR EACH TEST MODE-Written:

- Knowledge and abilities that are difficult to infer from behavior alone.

- Knowledge of factual information.

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- Paper & pencil abilities and skills (e.g., calculations)

- Responses requiring information that can be supplied on paper

- Interpretation of reference, if open reference Walkthrough:

- Areas needing interpretation

- Areas needing props

- Knowledge of locations

- Interpretation of references

- Administrative requirements Simulator:

Overall ability to operate Integrated use of knowledge and abilities Connunications Team Interactions Time-critical

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TABLE 3 EXAMPLE FORMATS FOR OPEN REFERENCE QUESTIONS PROVIDE THE OPERATOR WITH: REQUIRE THE OPERATOR T0:

1. Plant / System /Corponent Diagnose cause of the problem (s)

Condition (s)/ Problem (s)

2. Plant / System / Component Identify location of problem (s)

Condition (s)/ Problems (s)

3. Plant / System / Component Indicate a Condition (s)/ Problem (s) action (s)ppropriate(recuperative) 4 Plant / System / Component Indicate actions to achieve conditions specified effect

5. Plant / System / Component Identify precipatory events /

Conditions actions

6. Pl[ ant / System / Component Classify / Categorize or Conditions / otherwise indicate if

. conditions meet specified criteria

7. Proposed / Hypothetical Comment on Appropriateness /

course of action /reconnendation Acceptability of these actions /recomendations

8. Plant conditions and operator Indicate purpose of/ reasoning 4

actions / procedural steps behind these actions / steps

9. Requisite data Computation of parameters

10. Plant conditions and/or Predict expected plant /

operator actions system / component response (s)

11. System / Component status Indicate effect on sare or other system (s)/cotponent(s)

12. Plsnt/ System / Component Indicate proper procedure (s)/

Conditions references to turn to.

ATTACHMENT 11 NRC CHECKLIST FOR OPEN REFERENCE TEST ITEMS Item level

1. Does each test item have a documented link to important operator tasks.

A/As, and/or fccility learning objectives?

2. Is each test item operationally oriented, i.e., is there a match between job demands and test demands?

3. Is the question at least at the "comprehension" level of knowledge?

4 Is the context of the questions realistic and free of window dressir.g and backwards logic?

5. Does the item require an appropriate use of reference material, i.e., is it free of "look up" questions?

6. Is the item at the correct level of difficulty for the job position?

7. Is the item appropriate for the written examination end the selected written exam format (e.g., shcrt answer; multiple choice)?

8. I's an appropriate mix of operating modes presented in the scenarios in S.ection A "Plant Operations?"

9. D.o questions in Section A take advantage of the simulator control room l

setting?

10. Is the item free of double jeopardy?

11. Is the item clear, precise and easy to read and understand?

12. Is there only one correct answer to the question?

13. Does the item pose situations and problems other than those presented

, during training?

Test Level

1. Does the facility sampling plan adequately cover the requalification topics?

2. Does the facility sampling plan ensure comprehensive, balanced coverage of the requalification prcgram topics?

3. Can the test be completed in the time allotted?

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I NASTEi COP';

Nuclear Regu4atory Commission Operator Licensing .

Em ami nat i on l

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This document is removed f-om Official Use Only category on date of examination.

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EEBBX 21LDI BEDWOL l l

SIBIIC SidWLOIDS E100 EldWL910B EEI-WE 1

SErotti9 09s: 1 Egge pate: 88/05/19 1 Ini tialize simulator to IC-12. Set all recorders to correct time.

Establish exam condi tions as f oll ows:

Eve 01 Ilee daliz! Denctioil90 1 O 0537 Using MTI, insert malfunctions for SRV 0707 F051G f ail s to open, failure to scram, 0856 and failure of ARI. Di sabl e light bulb for 'A' solenoid on F051G.

2 +5 Place RHR loop B in Suppr es si on Pool Cool i ng . (Verify SP temperature trend changes.) ,

3 '8 Commence Fast Reactor Shutdown when SP temper ature reaches 95 F. Use cont-inuous cl ose moti on on FCVs so power trace shows clear demarkation and steady trend to mi nimum posi ti on.

4 *10 Before SP temperature reaches 110 F, arm and depress manual stram pushbuttons and place Mode switch in Shutdown.

5 Scram +1 Initiate both SLC trains, inhibit ADG, and verify RWCU i sol at i on.

6 Scram +2 Transfer RCIC suction back to CST.

7 Scram +3 Bypass RHR A/B, Air. LPSP, MSIV, and J NCCW A/B.

8 Scram +7 Per f orm Di v. 1, 2, and 3 injection pre-vention and place RCIC flow controller in manual at mi ni mum. .

I 9 Scram +B XH-11 restor & tion and CRDH 'A' restor-ation.

10 Scram +9 Restore Air to Drywell and Containment.

. Scram +10 Cleanup boards and place simulator in FREEZE at about 10 to 20*/. power.

Call up Reactor Power and Suppression Pool Temperature traces on the ERIS screens and verify traces approximate those attached.

i U. S. NUCLEAR REGULATORY COMMISSION PILOT REQUALIFICATION EXAMINATION  !

FACILITY: EEBBY_1h2.______

. REACTOR TYPE: BWB-DE6__ ._____

i DATE ADMINISTERED: DDf9DZ1B________

OPERATOR: ________________ ,

I CATEGORY OPERATOR SECIl0S _EQ1915. _SGQBC__ EEBGEUI005.  :

A. Plant Proficaency ___@Q___ _______.

j Scenario 1 2

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1 l'All work done on this examanation is my own. I have neither given nor roceived aid.

1 Operator's Signature i l

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NRC RULES AND GUIDANCE FOR EXAMINEES

1. Rest room trips are to be l i mi ted and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of cheating.

2. Use black ink or dark pencil ONLY to f acilitate legible reproductions.

3. Print your name in the blank provided on the cover sheet of the examination.

4 Fill in the correc t date on the cover sheet of the examination, if necessary.

5. Answer each question on t he ex ami nat i on. If additional paper is required, use only the lined paper provided by the examiners.

6. Use abbrevi ati ons onl y if they are commonly used in facility literature.

7. lhe point value for each quebtion is indicated i n parentheses af ter the question and can be used as a guide for the depth of answer required.

8. Show all c a l c u l a t i on r., methods, or assumptions used to obtain an answer to a mathematical problem, wh' ether asked for in the quest i on or not.

9. Unl ess solici ted, the location of references need not be stated.

10. Par ti al credit may be given. Therefore, ANSWER ALL PARTS OF THE DUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.

11. If parts of the ex ami nati on are not clear with respect to intent, ask questions of the ex ami ners onl y.

12. You must sign the statement on each cover sheet that i n d i c a t et-that the wor k on the examination is your own and that you have not received or been given any assi st ance in completing the ex ami nati on.

This must be signed AFTER cach section of the examination has been completed.

13. Cheating on the ex ami nat i on will result in a revocation of your license and couid result in more severe penalties.

14 The examination is designed to take approximately 90 minutes per section to compl ete. However, one hour will be allowed for each of the two scenarl o setups in Section A. Two hours will be allowed for Sections B and C. This guideline will be strictly adhered to.

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15. Due to the existence of questions that will require all ex ami nees to ref er to the same indications or controls during the Plant Proficiency phase of the ex ami nat i on, particular care must~be taken to maintain i ndi vi dual exam security and thus avoid any possability of compromise or appearance of cheating.

16. Individual sets of ref er ence mat er i al , as well as an abridged set of Plant Operating Manuals have been provided for the Li mi ts and Control s phase of the ex ami r.at i on. Do not write on or make any notations or markings on any of the reference materials.

17. When you hase signed and turned in each t,ettion of your completed examination. leave the exami nati on area and go-to the area that is designated by tne examtner.

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SCENARIO 1 INITIAL CONDIT IONS

,Approximately 20 minutes ago the Unit was at :

94% power steady, state 1200 MWe All controls in auto / normal No active or potential LCOs existed Then a transient occurredLanttiated by a f ailure .of an SRV. Actions were taken in accordance with'ON1-B21-1 in an attempt to.close the valve. An Unusual Event was declared 15 minutes'ago with.all required actions / paper work /notsfications made. PCI-B13 was subsequent l y entered.

Those questions identafted wi th Scenarlo 1 at the top are related to these intial' conditions. Any other questions are not scenario related.

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OUESTION A.07 (7.00)

Scenario 1 Di vi si on 11 diesel generator is running unloaded:

a. What specific signal caused the diesel generator to AUTO start?

' 03 .

b. Af t er placing the SYNC SEL switch'in the TH1 position, can the D2 vi si on 1I dzesel generator be paral 1eled with LH-1-A and then loaded? (Justify your answer.) [3.03

c. Which D2vtsion 11 diesel generator trips are NOT bypassed under the current plant conditions? [2.O]

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

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Oz__ELONI_E60ElglENGX______________ PAGE 9 l QUESTION A.08 (4.00)

Scenario 1 Based on current plant conditions, which Plant Emergency I n s t r u c t i on s.

shoul d the Unit Supervisor be operating in accordance with?

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

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.e___ELONI_E6QElCIENCY______________ PAGE 10 QUEST]ON A.09~ (7.00)

Scenario 1 Valve PS2-F2OO has been overridden opent

a. What plant conditions / operator actions cause P52-F2OO to close?

L?.53

b. Predict the effects on the f ol l owi ng systems / component s. ) f '

P52-F200 had'NOT been overridden open:

1. Mai n Steam Isolation Valves. [1.53

2. Control Rod Dri ve Fl ow Control Valves. C1.53

3. DrywelL cool er s. C1.53 (esss CATEGORY A CONT]NUED ON NEX1 PAGE *****)

9 ._ _ EL 8N1_ EBQE J C J E NCy_,,,_ _ _ _,, _ _ _ _ _ _ PAGE 11 l

l DUESTION A.!O (3.00)

Scenario 1 Determine the single cause for the BUS EH-12 BREAKER TRIP annunciator. j l

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(***** CA1EGORY A CONTINUED ON NEXT PAGE *****)

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9t._ EL 9NI_ E8QE J QlGNQ y _ _ _ __ _ _ _ _ _ _ _ _ _ PAGE 12 QUESTIDN A.I1 '(6.00)

Scenario 1 4

Consider the Standby Laquid Control systems-

e. Provide FIVE. indications of. proper operation _.of.SLC Train'B

, that the operator should verify upon initiation. [5.03

b. What signal igenerated by the Redundant Reactivity Control System-C22) will cause the SLC pumps to trip OFF7 C1.03

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

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' ez__EbeN1_E6QElglghQy______________ PAGE' 13 OUESTION A.12 (4.00)

Scenario 1 Consider the Automatic Depressurization system:

i c.

If switches B21C-S30A and S31A were. armed and depressed si mul t aneousl y, what would be the-effect on the ADS valves?

[1.03

b. What si gnal s are NOT yet present for an automatic ADS i nitiation.

signal to be generated? L3.03 1

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(**se: CATEGORY A CONTINUED ON NEXT PAGE *****)

T 9t_ EL9NI_EB9ElGIE K Y__________,___ pAgt 34 QUEST 1ON .A.13. -(5.00)

Scenarie'1 Step 3.1.7 of PEJ-B13 directs the operator s to reset the reactor scram and the.ARI. With the current plant conditions, specifItally describe why this step can or cannot be completed.

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(***st CATEGORY A CONTINUED ON NEXT PAGE *****)

91__ELONT_E6QElQl[NCy______________. PAGE 15 GUESTION A.14 , (S.00)

Sc enari o 1 Consider the High Pressure Core Spray system:

a. What signb1 caused.the automatic realignment of the'HPCS ' pump suction to the primary source? C1.53

b. Explain why meter E22-R603 indicates ZERO gpm. C2.O]

c. Predict the changes i n the current system configuration that will occur if reactor water level decreases to <.120 in. [1.53 9

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(***** CATEGORY A CONTINUED ON NEXT PAGE ***se)

The f ol l owi ng questions are not related to the initial condi ti ons est abli shed by the scenario, 1

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9___ELONI_ESQElG1ENCY______________ PAGE 16 QUESTION A.15 (5.00)

Following a complete loss of.off-site power, the plant is shutdown with power being suppli ed by the thr ee Di vi sional diesel generatorb.

If all three diesel generators were to trip and could not be restarted, STATE FIVE indicators on panel lH13-P601 that would be -

eve 21able for use by the operators to monitor RPV water level.

Provi de MPL specific answers.

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cOUESTION A.06 (4.00) l l

l With the plant operating at 90*/.-power and all controls in NORMAL / AUTO l

per_their respective SOls, reactor feedpump 'A' turbine trips.

Which of the f oll owing statements best describes responses of the Feedwater and Reactor Rec i rcul at i on systems?

a. The MFP immediately starts. It's flow control val ves respond to l the startup level controller si gnal s. The recirc system flow l control valves do not' move.

b. The MFP 1mmediately starts. It's f l ow control valves respond to master l evel controllar signals. The recirc system f low control valves do not move.

c. The MFP i mmedi a t el y starts. It's flow control- val ves respond to master level controller signals. The recirc system-flow control 4

val ves runback to about 48% f l ow posi ti on.

d. T he MF P starts when reactor water l evel decreases to level 4 It's flow control valves respond to the master leval cont rol l er si gnal s. Tne r eci rc system flow control valves runback to about 48% flow position.

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

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I Nuclear Regul ator y- Commi ssi on Operator Licensing ,

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NRC Official Use Only I

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EX851NES SUIDE i l

EEBBY EILQI BE9W96  !

SIBI1C SibWL9IDB EX8b SibWL9IDB EEI:UE SEEDgC19 69x 2 Eggs Dett: 88/05/19 Ini tialize simulator to IC-36. Set all recorders to correct time.

Establish exam condi tions as f ollows: i l

Place APRM A in bypass.

Sel ec t APRM E for power monitor.

Piace RFPT B in manual on the potentiometer, manual / min.

on its flow c on t r ol l er . 1 Dial RFTP A potentiometer to minimum.

Place Auto XFR Switch to DFF. .

Remove BLUE permissive light from LPCI C injection valve, install a "bad" bulb.

Insert Malfunction Ms: 365 APRM A Upscale.

605 C34-B Stgnal failure. I l

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1 U. S. NUCLEAR REGULATORY-COMMISSION PJLOT REQUALIFICATION EXAMINATION .I FACILITY: PgBBY_1g2_______ l REACTOR' TYPE: DWB-GEk_________

I DATE ADMINISTERED: 99/ 9D/18_ _ _ _ _ _ _ _ .

1

-OPERATOR: ________________

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CATEGORY OPERATOR-SEGI1QN _EQ]N15, _SQQ8E__ EE8QEN1@@E_

A. Plant Pr of i c i enc y ___QQ___ ________

Scenario 2 ,

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All work done on thi s exami nation is my own. I have ne.ther given'nor I recelved atd.

Biie?;is?G sii ;i;?-------

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NRC RULES AND GUIDANCE FOR EXAMINEES

1. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of cheating.

2. Use black ink or dark pencil ONLY to facilitate legible reproductions.

3. Print your name in the blank provi ded on the cover sheet of the examination.

4 Fill in the correct date on the cover sheet of the e:: ami na t i on ,

if necessary. j i

S. Answer each quest 2on on the ex ami nat i on. If add 2 ti onal paper is required, use only the 32ned paper pr ovi ded by the ex aminer s.

6. Use abbrev 2ations only 2f they are commonly used in facility literature.

I

7. lhe poi nt valuc fer each question is 2ndicated in parentheses af ter the questson and can be used as a gusde for the depth of answer r equ2 r ed. i

8. Show all calculataonn, mcthods, or assumpt2ons used to obtaln an answer to a mathematacal p r ob l eni, whether asked for in the quest)on or not.

9. Unless solicited, the location of references need not be stated.

10. Par t i al credit may be gi ven. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.

11. If parts of the examination are not clear with respect to intent, ask questions of the examiners onl y.

12. You must sign the statement on each cover sheet that ind2 cates that the work on the examination is your own and that you have not received or been given any assistance i n completing the exami nation.  ;

This must be signed AFTER each section of the examination has been '

completed.

13. Cheating on the examination will result in a revocation of your license and could result in more severe penalties.

14 The examination is designed to take approximatel y 90 mi nutes per secti on to complete. However, one hour will be allowed for each of the two scenario setups in Section A. Two hours will be allowed for Sections B and C. This guideline will be strictly adhered to.

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15. Due to the existence of questions that will require all examinees to refer to the same indications or controls during the Plant Proficiency phase of the examination, particular care must be taken to maintain i ndi vi dual exam security and thus avoid any 1 possibility of compromise or appearance of cheating. )

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16. Individual sets of reference material, as well as an abridged set of Plant Operating Manuals have been provided for the Limits and Control s phase of the ex ami nati on. Do not write on or make any l notations or markings on any of the ref erence materi al s.

17. When you have signed and turned in each section of you- completed ex ami na t i on , leave the ex ami na t i on area and go to the area that is des 2gnated by t h E' examiner.

_ ,.m.. . . _ . . . . , , . , -- . . , . _ . , , , ,_-,_...,,_.,_,___.-.-c. .c-.-., _. _ ,. . .

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~l, SCENARIO.2 INIT1AL CONDITIONS 1 1 1 1

The reactor is operating near full rated power (*96%). all rods

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are out at end of core life. RFPT 'B' signal f ailure .f reez e circui t is activated and actions per DN1-C34 wer e compl eted. WO-88-0231 is in progress for the auxiliary transfer switch. Troubleshooting efforts are in progress for APRM A.

Those questions i denti f i ed wi th - Scenar.i o 2 at 'the top are related to these initial c ond i t i onte . .Anv other questions are not scenari o rel at ed, l

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_ez__EbeN1_[@Q[JgjEN9y________ PAGE 17 DUESTION A.16 (4.00) i Scenario 2 I For the current plant conditions, which of the following statements correctly describes the status of the Normal and Startup supply breakers if the main turbine trips?

a. L1006 and LICO9 closed, L1202 and L1102 closed.

b. LIOO6 and L1009 open, L1202 and L1102 open.

c. L1006 and L1009 open, L1202 and L1102 closed.

d. L1006 and L1009 closed, L1202 and L1102 open.

1 (suses CATEGORY A CONTINUED ON NEXT PAGE seass)

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.1 9 __EL9NI_E69E1CJENCf._____________, PAGE 18 l 1

QUESTION A.17 (0.00) l Scenario 2 j l

Constder the current statue of the Feedwater and Feedwater' Level l Control systems. For each event, predict the effect on Reactor water level (INCREASE, DECREASE, REMAIN THE SAME).

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c. A short circuit causes IN11-FIOO to cl ose,

b. RFPT A GOV MODE CONT swttch, 550, is taken to MANUAL.

c. RFPT A f l ow c on t r ol l er , C34-R601A, is placed in MANUAL. ,

d. RFPT B Loss-of-signal Reset, IC34-SSB, pushbutton i s depr essed.

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(***** CATEGORY A CONTINUED ON NEXT PAGE eeees)

02_ _ E69NJ _ EBQE J QJ [NG,Y,,_ _ _ _ _ _ _ _ _ _ _ _ _ PAGE 19 QUESTION A.1B '(6.00)

Scenario'2 Predict a final stabl e value of reactor ~ power' i f APRM E were to' fail upscal e with no operator action. JUSTIFY your answer.

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.ez__EL9NI_E8QElqlENgy______________ PAGE 20 QUESTION A.19 (4.00)

Scanario 2 Dacreasing the LOAD L IMIT SET by 20% will:

(Choose the correct answer.)

c. have no effect because the pressure amp.is in control.

b. cause TCVs to cl ose down and BPVs to open up to maintain reactor power whil e reducing turbine MWe.

c. cause TCVs to c l ose down and BPVs to remain closed resulting in a reactor scram on high pressure or high flux.

d. cause TCVs to cl ose down and BPVs to remain closed. The Recirc System will run back reactor power to within the C85/N32 capacity.

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The follow 2ng questions are not related to the in2t2al condi ti ons est abli shed by the sct'nario.

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es__ELONI_EBOElcigNCY______________ PAGE 2 l

DUESTION A.Ol (9.00) l l

During a reactor startup, the RO notices that SRM count rate  !

indicates SxlOE4 cps shortly after withdrawing a gang of rods during the approach to criticality, and calls the reactor critical at that time: J

a. St ate the condi ti ons and indications the RO uses to determine --

criticality? (3.0) {

b. The RO notices that the SRM counts are lxlOES cps 56 seconds after calling the reactor critical. Calculate the reactor period. (SHOW ALL WORK) (2.O) l

c. B',' t he t i me t he SRMs indicate 1xlOE6' cps, what is the minimum l

r?ading on the IRMs to meet overlap requirements? (2.0) i

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d. Wher IRMs are appr ox i ma t el y midscale on range 7, reactor power -

will turn and l evel out. Why? (2,0)

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9:__E60N1.28QElGlENQY______________ PAGE 3 OUESTION A.02 (5.00)

During a plant heatup, Main Turbine shell warming i s being perf ormed with No. 2 MSV poppet val ve f ull y open to provide a shell warmi ng rate of 100 degrees F/hr. BESIDES rolling the Main Turbine off its turn 2ng gear or exceeding any warming rate limitations, what undesi r abl e plant action will occur if the warming rate is not reduced as the plant is pressurized State the setpoint when thi s act ion will occur.

(***** CATEGORY A CONTINUED ON NEX1 PAGE 44***)

9t _ _ E6 f LNI_ EBQE1Q1g NQy_ _ _ _ _ _ _ _ _ _ _ _ _ _ PAGC 4~

QUEST?ON A.03 (4.00)

The CRD flow controller (IC11 R600) is in-MANUAL with a c on t r ol l er output of 60 with the reactor at power. The reactor SCRAMS.

What effect does having this controller in MANUAL vs AUTO have on these parameters f ol l owi r.g the scram 7 (INCREASE, DECREASE, REMAIN THE SAME)

a. CRD hydraulics flow as read on IC11 R606.

b. CRD cooli ng water fIow'as read on 1C11 R605.

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

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O___EL991 E6QElGIEUGX______________ PAGE 5 QUESTIUN A.04 (5.00)

Shortly after a MSIV i sol a t i on at full power,.you notice.that peak reactor pressu-e was 1120 psi g. Whi.ch st atement (s) describe (s) t h c-electrical status of the RPS sceam sclenoids, the BACKUP seram solentods, and the ARI sol enoi ds assuming all systems functioned properly?

a. 411 sol enoi ds energtred.

b. All sol enoi d s deenergized.

c. RPS and ARI sol enoi ds energized, BACKUP solenoids deenergized,

d. HPS and ARI sol enoi ds deenerg2 2 ed , BACKUP sol enoi ds energized.

e. RPS sol enoi ds energized. ARI and BACKUP sol enoids deenergized.

f. RPS solenoids deenergized, ARI and BACKUP sol enoi ds energi z ed.

(e**** CATEGORY A CONTINUED ON NEXT PAGL *****)

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9t__EL9NI_ES0EIGIEURY__________ ___ PAGE G QUESTION A.Ob (5.00)

If a valid Reactor. Water Level I signal was' generated:

a. Predict which Di vi si on 11 ECCS i nj ection val ve(s) will NOT open automatically and provide the singl e reason why.

(Explain f ull y. ) t3.03

b. Does this condition render the system (s) ' inoperable? L2.03 y

4 (seats CATEGORY A CONTINUED ON NEXT PAGE tast)

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• NRC Officic1 Uno Only

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% Cop:u Nuclear Regulatory Commission Operator Licensing E x ami na t i on This document is removed from Official Use Only category on date of examination.

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L-U. S.. NUCLEAR REGULATORY COMMISSION SENIOR OPERATOR REOUALIFICATION EXAMINATION FACILITY: E E BBY_1 & 2_ _ _ _ _ _ _

REACTOR TYPE: 9WB-DE6.________

DATE ADMINISTERED: @@/95/12________

OPERATOR: ________________

001E_10_QEEB01061 A grade of 80% overall f or Sections A and B combined is the standard for succebsful completion of the written examination.

CATEGORY OPERATOR SECIl0V _EDIVIS. _SCQBE__ EE6GENIeQE_

A. Plant Proficiency __199,__ ________

B. Li mi t s and Controls __199 __ ________

Total __299___ ________ ___________

FINAL GRADE All work done on this examination is my own. I have neither-given nor received aid.

Operator *s Signature f

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NRC RULES AND GUIDANCE FOR EXAMINEES

2. Rest room trips a e to be limited and only one examinee at a time may leave. You must avoid all contact witt, anyone outslMe the examination room to avoid even the appearance or possibility of cheating.

2. Use black ink or dark pencil ONLY to facilitate legible reproductions.

3. Print your name in the blank provided on the cover sheet of the ex ami nat i on.

4 Fall in the correct date on the c over sheet of the examinati on, 3i necessary.

5. Answer each question on the exami nati on. If add 2tional paper ;s required, use onl y the lined paper pr ovi ded by the examiners.

6. Use abbrevi ati ons only if they are commonly used in facility l a ter atur e.

7. lhe poi nt value for each questaon is i ndi c at ed in parentheses after the Questien and can be used as a guide fCsr the depth of antwer 2 required.

6. Show all calculataons, methods, or a s sump t. : on s used to obtain an answer tc a mathemat) cal problem, whether asked for in the questaon or not.

9. Unl ess solici ted, the location of references need not be stated.

10. Par ti al uredit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.

11. If parts of the examinati on are not clear with ret,pect to intent, ask questions of the ex ami ner s onl y.

12. You must sign the statement on each cover sheet that indicates that the work on the examination is your own and that you have not i received or been given any assistance in completing the ex ami nati on.

This must be signed AFTER each section of the ex ami nati on has been completed.

13. Cheating on the examination will result in a revocation of your .

license and could result in more severe penalties. l 14 The examination is designed to take approximately 90 minutes per section to complete. However, one hour will be allowed for each of the two scenario setups in Section A. Two hours will be allowed for Sections B and C. This guideline will be strictly adhered to. g i

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15. Due to the existence of questions that will require all examinees to refer to the same indications or controls during the Plant Proficiency phase of the examinati on, particular care must be taken to maintain individual exam security and thus avoid any possibility of compromise or appearance of cheating.

16. Indi vi dual sets of reference material, as well as an abridged set of Plant Operating Manuals have been provided for the Limits and Controls phase of the exami nati on. Do not write on or make any notations or markings on any of the ref erence material s.

37. When you have signed and turned in each sec t i on of your completed ex a mi n a t i on, leave the examination area and go to the area that is designated by t he ex ami ner .

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! Sc__LIMIIf.eUD_G99IBQL5________ PAGE 46

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i OUESTION B.01 (6.00) 4 During preparatton for a monthl y surveill ance on the DIV I D / G ,- 1 the "A" train of M25/26 is placed in the EMERG RECIRC mode. Train "B" is verified to be in standby readiness, with its associated suction damper closed. When the D/G is started, you notice that the "B" train of M25/26 has automatically started in the EMERG  ;

RECIRC mode,

e. What caused'this automatic startup of "B" train of M25/26'

b. Why does this event require an NRC notification?

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Dz-_kl0115.9NQ QQNISQL5________ PAGE -/

DUESTION. B.02 (8.00) l A GENERAL EMERGENCY has been declared. Containment-Hi Rad monitors D19N2004 and B both read 15,000 R/hr. -T.ie reactor has been shut down i for fave hours.

i a. Determi ne the appropri at e protec ti ve action recommendations that would be required based on the above inf ormation. [6.03  ;

b.- What is the approx imat e core . inventory loss f or this accident?

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Bi__L101I5 9NQ,QQNIBQLQ________. PAGE 48'

-l DUESTION B.03 ( 6. 00).

-During-the performance of SVI-C71-T0039, valve B21-F022B fails to close. In accordance with the appli cabl e Tech Spec 3. 6. 4,' the assocaated penetration must be -i sol ated. Specifically,awhich val ves must be cl osed .to compl y wi th the LCO?

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(***** CATEGORY B CONTINUED ON NEXT PAGE *****) '

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Di__k1MlIE_9NQ_QQNIRQL5________ PAGE 49 QUESTION B.04 (6.00)

Choose the correct statement regarding refueling cperationst

e. At least 23 feet of water shall be maintained.over the top of the Reactor Pressure Vessel Flange.

b. The Conta':nment Building overhead crane may be used to handle control -ods in the RPV.

c. AlI core alterations wi11 be< observed and' direct 1y supervised by an SRO licented individual who has no other concurrent responsibilities during this operation,

d. During fuel l oadi ng into the RPV, only SRMs A and C need'to be OPERADLE.

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D___61M1I!_0Np_gDNI606@________ PAGE 50 l

DUESTION B.OS (8.00)

Pr ovi de the correct Emergency classification for each of the f oll owi ng condi tions. Include the reference for the specific Emergency Action l evel s to support your cl assi f i cati on.

(e.g., A.I.1, B.II.3, etc.)

a.

During operations, UNIDENTIFIED LEAKAGE i s calculated to be 7 gpm.

b. ESW Pump "B" motor windings burn up and RHR Pump "A" is RED TAGGED out, c.

Securi t y per sonnel report that the Main Turbine casing has falled f ollowing an overspeed trip, d.

Reactor water chem 4stry results indicate 320 uct/cc DOSE EQUIVALEN1 10 DINE and reactor water level is -20 inches on the fuel zone range.

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

Dz__ Lib 1IE_eNQ,QQNIBQLS________ PAGC 51 QUESTION B.06 (6.00)

During a plant startup, the Reactor Mode Swi tch is placed in RUN Just prior to observing that containment vacuum breaker M17-F010 as open due t' M14 system operation. Choose an action from.the fol1owing 1ist that is required for thi s condition.

c. Operation may continue and the provisions of Specification 3.0.4 do not apply.

b. Within four hours, restore M17-FOIO to OPERABLE and closed, or close the associated MOV and deactivate it.

c. Within four hours, close the associated MOV.

d. Within one hour, restore M17-FOlO to closed or be in at least HO1 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

e. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, restore M17-FOlO to OPERABLE or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(ase** CATEGORY D CONTINUED ON NEXT PAGE ***es)

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- E-- Lit!115 8NQ,QQt!ISQ(g-------- PAGE 52 ,

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-DUESTION' B.07 (6.00) ,

i Assume that the. main generator i s l oaded - to 313 MWe - *

~ Dotermine the minimum time permisaible for-a step l change in load to 1190 MWE.

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B___L1011S_eNp,GQNJ8Q65.,______ PAGE 53 QUESTION B.08 (6.00) i Which of the f ollowing i ndi vi duals may be all owed to'make changes to the Reactor Recirc. Flow Control Valve position at full power without direct supervision

a. An unlicensed System Engineer to check valve response, provided the consent of the licensed oper ator at the controls and the Unit Supervisor is obtained.

b. An unlicensed i ndi vi dual in the SRO Training Progran provi ded the consent of the licensed operator at the controls and the Unit Supervisor as obtained.

c. The encoming Unit Supervisor, provided - the knowledge and consent of the licensed operator at the control s i s obtai ned'.

d. The encoming Shift Supervisor, provided the knowl edge and consent of the licensed operator at the controls and the Unit  !

Super vi sor is obtained, h

c. An individual assigned to the shift in order to f ulfill h15 8-hour on-shift r e qu i r ernen t of the Accelerated Requalification Program.

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9 Bi__ Lib 1ID_9NQ_QQUICQLg________ .PAGE 54 OUESTION B.09 (0.00)

With the plant at 10 0'/. p owr * , state YES or NO for each case as to whether PRIMARY CONTAINMENT-INTEGRITY i s maintained.

c. Valve G33-F001 is ancapable of automatic closure, and is currently open,

b. Suppression pool temperature is 101 degrees F during a RCIC full flow test CST to CST.

c. The Annulus door to the Auxillary Building is found propped open.

d. Suppression Pool Level is 18 feet 8 inches.

o. A PPO reports that the Orywell outer airlock door is found open and cannot be closed.

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(sese* CATEGORY B CONTINUED ON NEX1 PAGE ****s)

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D___b1M11S_eNQ,QQNI6QLS________ PAGE 55 QUESTION B.10 (6.00) l During power operation on May 18, 1988, the secondary windings on transf ormer LH-2A f ai l ed, and the transformer is declared inoperable i at 0800 that day. The f ol'; owi ng is a record of the surveillances l completed during the last , hours because of this events l

SIV-R43-T1317 Start 1000 5/18, complete 1300 5/18 SVI-R43-T1318 Start 0300 5/19, complete 0750 5/19 SVI-R10-T5217 Start 0805 5/18, complete 0822 5/18 i Start 1545 b/18, complete 1600 5/16 Start 2340 5/18, complete 2345 5/18 i Start 0720 5/19, complete 0740 5/19 l What is the LATEST that you can sati sf actorily complete the nex t requi r ed SVI-R10-TS217 and NOT violate Tech Specs?

c. 1520 May 19

b. 1540 May 19

c. 1740 May 19

d. 1800 May 19

e. 2200 May 19

f. 0740 May 20 I

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Bi_ L1511E_899_CONIB965________ PAGE 56 DUESTION B.ll (0.00)

Identify the statement (s) that is(are) NOT correct with regard to Sciety Tagging?

a. When locks are used-in c onj unct i on wi th red tags, the locks should be placed on the component prior to the tag being placed.

b. Red and White tags are not permi t ted to be attached to the same device at the same time.

c. The Unit super vi sor may dtreet the une of a "human" red tag.

d. A valve may be red tagged in the open position to provide r el i ef protection.

e. A breaker may be red tagged closed to provide emergency power,

f. Yellow tags are requir ed for all temporary ground connections.

(esses CATEGORY B CONTINUED ON NEX1 PAGE *****)

Di__ LID 115 eyp,QQNISQL5________ PAGE 57- '

l QUESTION B.12 (6.00) i The plant is in cold shutdown, all MSIVs closed,;no testing in progress. RPS Bus "A" is being powered from the MG set.

ThG RPS "A" MG vol tage regul ator fails high, causing a trip of the associate. EPAs. -What will be the INDICATED and ACTUAL vol ve posi ti on of the MSIVs due to .thi s transient?

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- Bu__L151IE_9NQ,QQNIBQLE________ PAGE 59 4

DUESTION B.13 (6.00)

Ascume thr f ollowing Main Generator Conditions:

H2 pressure reads 60 psig on N35-R161. ,

Meter N41-Rol7 reads 0.05 lagging.

Present load is 800 MWe.

c. Determine the maximum MWe l oad 'permi tted.

b. Predict the cor respondi ng MVARs f oe. the max i mum permitted l megawatt load.

c. Identsfy the lim 1 ting generator component for these maximum allowed c ondi t i on s.

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Ba__6101IS_9NQ_CgNI59(p____,,_, PAGE 59 GUESTION B.14 (6.00)

Durang power operation, an el ec tr i cal problem is encountered with RHR "C" Suppr essi on Pool Suction valve (E12-F105), Other than RHR "C,' what TWC syst errb/ subsystems must be declared inoperable af E12-F105 must be closed?

(:*ss: CATEGORY B CONTINUED ON NEXT PAGE *****>

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.Dt__L101I5_9SD GDSIBRLS________ PAGE 60 1 t I

QUESTION B.15 (H.00)

D3ter mi ne a f adequate core cooling is assured'for each of the ,

f ollowing accident conditions. Consider each case independentl y and answer YES or NO.

i

o. No injection or alternate injection system running, reactor level -120 i nches decreasi ng, RPV pressure at 900 psig, one

< SRV open. '

b. No i nj ec ti on or alternate injection system running, reactor l evel bel ow bottom of active fuel (BAF), RPV pressure at 900 psig, one SRV open. , i i

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c. No i nj ecti on or al ternate i nj ecti on system running, reactor l level bel ow BAF, RPV pressure at 500 psi g. one SRV open.

d. No inject!on or alternate injection system running, reactor l evel bel ow BAF, RPV at z ero psi g, eight SRVs open.

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4 ts**** END OF CATEGORY B sesse)

(senessessesse END OF EXAMINATION seessetestessee)

]

NRC Cffic!O1 Us3 Only p

o MASTEn Copt i

Nuclear Regulatory Commi ssi on Operator Li c ensi ng .

Em ami nat i on l

j Thi s document is removed from Official Use Only category on date of examination.

NRC Official Use Only

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: EEBBY_lk2_______

REACTOR TYPE: QWS-QEk_________

DATE ADMINISTERED: DQ4QDil2________

OPERATOR: ________________

NOTE TO QPE691QRt A grade of 80% overall for Sections A and C combined as the standard for cuctossful completion of the written examination.

CATEGORY OPERATOR SECIlgN _EglN15_ _SCQ6g , &[6 GENI @QE.

A. Plant Proftciency __100 l C. Limits and Controls __190___ ________

Total __200 FINAL GRADE i

All work done on this evamination as my own. I have neither gi ven r,o r rocGived aid.

l Operator 's Si gna ture l i

NRC RULES AND GulDANCE FOR EXAMINEES

1. Rest room trips are to be limited and only one examinee at a time may l eave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility ,

of cheating. '

2. Use black ink or dark pencil DNLY to facilitate legible reproductions.

3. Print your name in the blank provided on the cover sheet of the examination.

4. Fall in the corr ec t date on the cover sheet of the examination, if nec essar y.

S. Answer each quest 2on on t he ex ami na t i on. If addi t i onal paper as required, use onl y the li ned paper prov3ded by the ex aminers.

6. Use ab br evi a t i on ts onl y af they are commonl y used in facility laterature.

7. 1he point value for each question as indicated in parentheses after the que st i on and can be used as a guide for the depth od answer required.

6. Show all cal c ul at a onn, methods. or assumptions used to obtain an answer to a mathematlcal problem, whether asked for in the questaon or not.

9. Unless sol s ci ted, the location of references need not be stated.  ;

10. Par t i al credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.

1

11. If parts of the exami nati on are not clear with respect to intent, ask questi ons of the examiners only.

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12. YLJ must sign the statement on each cover sheet that indicates that the work on the examinati on is your own and that you have not received or been given any assistance in completing the examination, i This must be signed AFTER each section of the examination has been completed.

13. Cheating on the examination will result in a revocation of your license and could result in more severe penalties.

14 The examination is designed to take appr ox i ma t el y 90 minutes per sec t i on to compl ete. However, one hour will be allowed for each of the two scenario setups in Section A. Two hours will be allowed for Sections B and C. This guideline will be strictl y adhered to.

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15. Due to the existence of questions that will require all examinees to refer to the same indications or controls during the Plant Proficiency phase of the examination, particular care must be  ;

taken to maintain individual exam security and thus avoid any possibility of compromise or appearance of cheating.

16. Indi vi dual sets of reference material, as well as an abridged set of Plant Operating Manual s have been provided for the Limita and Control s phase of the examination. Do not write on or make any notations or markings on any of the ref erence material s.

I

17. When you have signed and turned in each section of your completed ew ami na t i on , l eave the ex ami nati on area and go to the area that is designated by the examaner.

Gz__k1DlIf_eNQ,QQNIBQLE______________ PAGE 21 1

QUEST I ON C.Ol (4.00) l During power operation, the oncoming In-Plant Supervising Operator.

(Bergaining Unit Supervisor) calls in to inform you.that he will be four hours late coming in to ralieve the watch. If the on-duty In-Plant Supervi sing Operator leaves the sate at the normal shift reli ef time, will the minimum shift manning requirement still be met?

] Explain your answer.

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Gi__L1512E_ebD_G9918965_____________ PAGE 22 QUESTION C.O? (6.00)

Which of the f ollowing Individuals may be allowed to make changes to the Reactor Recirc Flow Control Val ve posi tion at full power without direct supervistent

a. An unlicensed System Engineer to check valve response, provided the consent of the licensed operator at the controls and the Unit Supervisor is obtained.

b. An unistensed 2 ndi vi dual in the SRO Training Program provided the consent of the licensed operator at the controls and the Unit Super vi sor is obtained.

c. The oncoming Unit Super vi sor , pr ovi ded the knowledge and consent of the licensed operator at the control s is obtained. ,

d. The oncoming Shift Superv3sor, provided the knowledge and consent of the licensed operator at the controls and the Unit Supervisor is obtained, i

e. An indi vi dual assigned to the shaft a n order to fulfill his B-hour on-shaft requirement of the Accelerated Requalification Program.

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(*ses* CATEGORY C CONTINUED ON NEXT PAGE ****s)

L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ . . _ _ . . _ . . _ . _ _ . . . _ _ . _ _ _ _ _

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Gi__L15115.999.G9NIBQL5______________ PAGE 23 QUESTION C.03 (4.00)-

Which of the f ollowing statements is correct with regard to shift stoffing requirements?

c. The licensed operator at the controls may take temperature readings on the Di vi si on 1 Leak Detec ti on panel- (H13-P632)-

i n response to a RCIC 150 TIMER RUNNING STM TNL TEMP H1 annunicator.

b. The licensed operator at the control s may shi f t the Off-Gas System from the AUTO mode to the TREAT mode during a plant startup per 101-1.

c. The licensed operator at the controls may start the Motor Driven Fire Pump if needed during fire fighting efforts.

I (esses CATEGORY C CONTINUED ON NEXT PAGE assss)

I

Gi__L151I5.eNp,QQNIBQLp._____________ PAGE 24 1

=

QUESTION C.04 (6.00)

e. The Reactor Mode Switch is in Shutdown and reactor temperature is at 180 degrees F. Is the Unit Supervisor position required

to be manned' 4

y Now, assume the Reactor Mode Switch as now placed in the STARTUP/ HOT l STANDBY position for testing of the mode switch interlocks onlyt

b. What is the present Reactor Operational Condition?

c. Is it permi ssi bl e to withdraw a control rod in this condition? l 4

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Gz__L1011D_ANQ_QQNIBQLg______________ PAGE 25 QUESTION HC 05 (8.00)

With the plant at 100% power, state YES or NO for each case as to whether PRIMARY CONTAINMENT INTEGRITY.is maintained.

c. Valve G33-FOOL is incapable of automatic closure, and is currently open,

b. Suppression Pool temperature is 101 degrees F during a RCIC full flow test CST to CST.

c. The Annulus door to the Auxiliary Building is found propped open.

d. Suppression Pool level is 18 feet 9 inches.

c. A PPO reports that the drywell outer airlock door i s f ound open and cannot be closed.

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1 Gi_ LIM 1IE_eNQ_QQNIBQLE______________ PAGE 26 1

QUES 110N C.06 (8. 00) -

During power oper a t i ons , Reactor Recirc-Pump "A"' trips and i s not

' rec over abl e. You ubserve the f ollowing pl ant . parameters:

Total core flow = 4S x IOE6 lbm/hr APRM power = 60*/. o f rated Identify the correct action (s) for the. current pl ant. condi ti ons.

a. Reduce "B" loop flow to less than 4S% rated loop flow.

b. Reduce reactor power with cram rods . to l ess than

• 47%

power.

c. Determine the APRM and LPRM noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 70 minutet after each SX pnwer increase,

d. The Reactor Mode Switch must be in SHUTDOWN no more than 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after the pump trip.

e. The Reactor Mode Switch must be in at least STARTUP/ HOT ST ANDBY no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the' pump-trip.

(***** CATEGORY C CONTINUED ON NEX1 PAGE *****)

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I Gi__L10115_eNQ_QQN16QL@______________ PAGE 27 1

QUESTION C.07 (6.00)

During power operation on May 18, 1988, the secondary windings on transformer LH-2A failed, and the transf ormer is declared i noperabl e at 0800 that day. The f ollowing is a record of the sur vei l l ances completed during the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> because of this event SIV-R43-T1317 Start 1000 S/38, complete 1300 S/18 SV1-R43-T1318 Start 0300 5/19, complete 0750 S/19 SVI-R10-15217 Start 0805 S/16, complete 0822 5/18 Start 154S S/18, complete 1600 S/18 Start 2340 S/ le, compl et e 2345 5/18 Start 0720 5/19, complete 0740 5/19 What is the LATES1 that you can satisfactorily complete the next required SV1-R10-T5217 and NOT viol ate Tech Specs?

a. 1520 May 19

b. 1540 May 19

c. 1740 May 19

d. 1800 May 19

e. 2200 May 19

f. 0740 May 20 (as*** CATEGORY C CONTINUED ON NEXT PAGE *****)

G___61DlIS_eND_CQN16Q(S______________ PAGE 28 QUESTION C.08 (8.00) ,

1 Identi f y the statement (s) that istare) NOT correct with regard to l Safety Tagging.

a. When locks are used in conjuncti on wi th red tags, the. locks

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should be placed on the component prior to the tag being placed.

b. Red and White tags are not permitted to be attached to the same device at the same time.-

c. The Unit supervisor may direct the use of a'"human" red tag.

d. A valve may be red tagged in the open position to provi de relie protection.

e. A breaker may be red tagged closed to provide emergency power.

4. Y el l ow tags are required for all temporary ground connections.

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Gi__ LIM 1IE_9N9 GQNIBQ65______________ PAGE 29 QUESTION C.09 (6.00)

Which s i t uat i on ( s) would NOT require the use of an MFI/LLJED tag?

a. A hydropump is connected to NCC "A" heat exchanger vent.

~b. A f l oor drain plug is installed in-the HPCS pump room,

c. An alternate lubricant is used in CRDH Pump A.

d. During OPCON,2, scaf f olding is erected in_ containment'620' elevation near the B33 FCV skid.

e. A jumper is installed and removed as required by an SVI.

f. One of the four inputs to an annunicetor on H13-P970 is defeated.

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l Gr_ _ L I MI IS MD_ G QNISQL 5_ _ _ _ _ _ _ _ _ _ _ _ _ _ .PAGE '30 ,

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GUESTION C.10 -(6.Od)

.The plant is.in cold: shutdown, all MSIVs closed, no testing

'in; progress. RPS Bus "A" is being. powered from the MG set..

The RPS " A"'MG voltage regulator fails high,-causing a trip of the associated EPAs.

What'will be the INDICATED and ACTUAL valve position of the' MSIVs due to this transient?

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G___ Lid 115_9NQ_QQNIBQLE______________ PAGE 31-QUESTION C.ll (6.00).

Assume the f ollowing Main Generator Condi t i ons:

H2 pressure reads. 60 psi g on N35-R161.

Meter N41-RO17 reads 0.85 lagging.

Present load is 800 MWe.

a. Determine the maximum MWe l oad permi t ted,

b. Pred2ct the corresponding MVARs f or the maximum permitted megawatt load.

c. Identify the li mi ti ng gener ator component for these maximum allowed conditions.

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

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'Gi__L10125_9NQ_QQNIBg65._____________ PAGE- 32 l

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GUESTION C.12 -(6.00)

Consider the f oll owi ng Post-LOCA, Reactor, Containment, and Drywell parameters:

Rx l evel 10 inches DW pressure 2.0 psig CNTMT pressure 2.0 psig DW H2 concentration 5%

CNTMT H2 concentration 5%

CNTMT Temperature 160 degrees F Determine.which hydrogen control measures should be currently employed:

a. Hydrogen recombiners

b. Canbust2 bl e Gas Mixing Compressors

c. Containment Venting

d. Containment Spray

e. Hydrogen Ignators i

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3 Gz__L101I5.9NQ,QQNIBQL$,,,,,,,,,,,,,_, PAGE 33 QUESTION C.13 (6.00)

During power operation, an electrical problem i s encountered wi th RHR "C" Suppressi on Pool Suc ti on Valve (E12-F105). Other.than RHR "C,". what two systems / subsystems must-be declared inoperable ,

if E12-F105 must be closed? "

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I G.i. _ _ L 101 I 5. 9N Q, Q QNI BQL S. _ _ . . _ _ _ _ _ _ _ _ _ PAGE 34 l

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OUESTlON C.14 (6.00)

The plant is in Operational Condition 2 at 9% power with-a startup in progress. The PPO informs you'that both Di vi si on 111 air compressors are incapable of starting. Can the startup '

continue to Operational Condition 17 Justify your answer and list the supporting references, i

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Gu__bidilS_0NQ,QQNI6QL5______________ PAGE 35 l

QUESTION C.13 (6.00)

Choose the correct statement regarding refueling operations ]

a. A.t least 23 f eet of water shall be maintained over the top of the Reactor Pressure Vessel flange. '

b. The Containment Building overhuad crane may be used to handl e control rods in the RPV.

t. All core al ternati ons will be observed and directly sugervised by a SRO licensed i ndi vi dual who has no other concurrent respo.,sibilities during this operation.

d. During fuel loading into the RPV, only SRMs A.and C are required t o be OPER43LE.

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l DUESTION C.16 (8.00)

Determine if the potential for RHR water hammer exists in each of the f ollowi ng scenarios and answer YES or-NO .

a. While conducting SPCU operations with return directed back to the Suppression Pool, G42-FOlO inadvertentl y closes,

b. Whi l e in the Suppression Pool -Cool i ng mode, a l evel 1 LOCA initiation signal is received.

c. Reactor pressure exceeds 135 psi g while in Shutdown Cooling,

d. While per f orming a full flow test of the RHR A to the Suppression pool, a loss of LH-1-A occurs (all plant systems in a normal 1ineup).

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ES-601 4

Rev 5 10/1/88 DRAFT ADMINISTRATION OF NRC REQUALIFICATION PROGRAM EVALUATIONS A. Purpose This standard provides general guidance and requirements to NRC examiners for the administration of NRC requalification examinations. This program evaluates the effectiveness of a facility's licensed operator requalification training program to maintain the competency and currency of licensed operators. This is done by evaluating the ability of the facility to adequately prepare written examination questions and simulator scenarios and their ability to properly evaluate their operators' performance. In addition, satisfactory completion of the examinations by individual operators would satisfy the regulatory requirement to pass an NRC administered requalification examination prior to ,

license renewal. This document is not a substitute for the operator licensing reguiationsandissubjecttorevisionorotherinternaloperatorlicensing policy changes.

B. Program Description The NRC requalification examinations administered under this standard per the provisionsof10CFR55.59(a)(2)(iii)attempttominimizethepotentialforan a'dverse impact on the safe operations of facilities, and to provide the staff witn an assessment of the effectiveness of facility requalification training programs.

The requirements and procedures are derived based on a systems approach to training (SAT) program in accordance with INPO Guideline 86-025, and rely upon existing requalification program standards for guiding the NRC examination development and implementation. This approach will allow the NRC to administer requalification examinations that are consistent with existing facility Examiner Standards 0001.0.0 of 28

7 s l ES-601 l Rev 5 10/1/88 developed programs, thereby reducing the impact on the facilities and improving l the reliability of the NRC assessment of requalification training programs.

1 Each requalification examination will be developed by an examination team consisting of NRC examiners and facility representatives and will be reviewed i by facility representatives and by the Resident inspector where practical. The l examination will be based upon the facility requalification program and its learning objectives, to the extent practical. This approach will result in l more technically sound and operationally oriented examinations. In addition, coevaluation of operator performance by the NRC and the facility will enhance the ability of the NRC to assess both individual and program performance. l The NRC administered requalification examination is composed of an operating test and a written examination. The operating test consists of a simulator evaluation which emphasizes time-critical and team-dependent behavior with a flagging system to enable follow-up of individual weaknesses. The walk-through evaluation will cover plant systems identified by the NRC and the facility that,are important to the safe operation of the facility as contained within ,

Grou;is I and 11 of the "Examiners' Handbook for Developing Licensing Examinations"(Seepage 2-18ofNUREG/BR-0122). The written examination consists of a two section open book examinstion: Section A will be a "Plant Operations" section and is administered on a static simulator; Section B will be a "Limits and Controls" section and is administered in a classroom setting. I l

C. Administrative Controls l

The NRC will plan to examine an average of 20% of the licensed operators and l senior operators at each facility on an annual basis. The following criteria outline the requirements for the administration of the NRC Requalification l

Evaluation Program. 1 1

1. Facility Notification l

Examiner Standards 0002.0.0 of 28 i

ES-601 Rev 5 10/1/88 The attached corporate notification letter is used to inform facility program managers of the impending requalification program evaluation. This letter should be mailed at least 90 days in advance. Site visits should be scheduled to coincide with the requalification training cycle of the facility. The facility should know 30 days in advance which operators will be evaluated.

2. Selection of Operators The facility will propose operators for NRC examination 60 days prior to the administration date. The NRC will select crews and individuals to be examined based on the following criteria:

a. Number of individuals on crew not examined during current license term,

b. Number of examinees required to sample 20% of licensed personnel,

c. Nunber of staff (not crew) licensed personnel not examined during ,

current license term, and Id. Length of time until license expiration.

.e. Priority given to crew (s) in training during the examination week (s).

An operator that has previously passed an NRC requalification examination during the term of the license may be included in the simulator crew evaluation, if he/she is a member of a crew selected. Such an individual will not be required to take the written or walk-through examination. Poor performance in the simulator examination would be evaluated as described in Section D.7.a.

The sample will include additional shifts composed of licensed personnel who are not routinely performing shift duties, in order to sample approximately 20 percent of the operators each year. If a facility evaluates mixed crews (shiftandnon-shiftlicenseholders),mixedcrewsmaybeevaluated.

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3. Facility Involvement

a. The facility will be requested to provide two employees, one frc:n the l operations staff and one from the training staffs, to assist the NRC to form the NRC examination team. The employee from operations shall be an active licensed SR0; the employee from training should preferably be a licensed SRO, but may be a certified instructor.

The function of these individuals is to provide facility specific technical assistance to the NRC in the development and review of the written examination items, plant walk-through topics, and simulator scenarios. If necessary due to insufficient facility staff resources, facility representatives may participate in the actual conduct of the operating test or written examination.

b. To ensure examination security, the individuals shall not in any way be involved in requalification program activities between the start

. of their involvement in examination development and the administra-tion of the examinations. Also, the individuals shall be instructed and agree not to comunicate in.any fashion the content or scope of '

the examination to unauthorizec persons. Each individual will be l

required to sign a statement prior to reviewing any examination  !

material that he/she will not knowingly divulge information concerning the NRC examination, and then to sign a second statement after examination administration that he/she has not knowingly given '

information about the specific content of the examination to any l unauthorized person.

c. For the simulation facility examinations, a facility management l

representative with responsibilities for the conduct of plant operations (as a minimum, first level above shift supervisor) be present during administration of these examinations,

d. In addition, the facility will be required to grade, in parallel with the NRC.

4. Timetable for Administration of Requalification Examinations Examiner Standards 0004.0.0 of 28

'l ES-601 Rev 5 10/1/88 90 days in advance - The facility is notified.

60 days in advance - The facility provides proposed materials for examina-tion construction (including written examination question and simulator scenario banks and job performance measures with follow-on questions for important safety Systems).

- The facility proposes crew composition.

30 days in advance - NRC notifies facility of crew selections.

14 days in advance - NRC team visits the facility to prepare for the examinations.

7 days in advance - NRC prepares for examination in the Regional office.

Examination Week - NRC administers reqit.lification examinations to  ;

selected crews.

5. lExaminationAdministration The simulator examination is normally administered first, followed by the plant walk-through evaluations for each crew. The two part written examination will be administered after all simulator and plant walk-through evaluations have been completed. This order of administration is intended to provide for an operational atmosphere prior to the written examinatien. Each portion of the requalification examination shall include the appropriate oral briefing or rules handout.

6. Requalification Program Evaluation

a. Program Evaluation Examiner Standards 0005,0.0 of 28

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ES-601 i Rev 5 10/1/88 I A program evaluation thould normally be based on a minimum sample size of at least 12 licensed operators and senior operators. If the annual 201 sample does not meet this minimum sample size then the program evaluation will be deferred until inclusion of the next annual ,

1 cycle, unless the interim results warrant imediate action, j i

A satisfactory requalification program cust meet each of the following:

I (1) 901 pass / fail decisions agreement between the NRC and facility grading of the written and operating examinations.

l (2) At least 80% of all operators pass the examination. i (3) The program is judged satisfactory in accordance with the guidance giver for the simulator evaluation.

-(4) The program meets the requirements of 10CFR55.59 or, in lieu of

. paragraphs (c)(2),(c)(3),and(4),isbasedonsystemsapproachto ,

training.

I When;using the above percentages, fractions of individuals should be rounded up to the next highest number. Forexample,iftwelve(12)If:ensedindividuals are evaluated, 80% passing would be 9.6, thus ten of twelve passing should be considered as meeting the 80% requirement. This rule should be applied throughout this standard,

b. Reference Material Evaluation NRC reserves the right to declare a facility training program unsatisfactory and to postpone NRC administered requalification l examinations if the facility generated materials are inadequate for l examination preparation. Enforcement action may be considered if necessary to bring facility generated material to the level of quality for examination preparation.

7. Requalification Performance for an Individual Examiner Standards 0006.0.0 of 28

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- l ES-601 Rev 5 10/1/88 For an individual to successfully pass the requalification examination as i graded by the NRC, the following apply:

a. Achieve at least 80% overall on the written examination.

b. Satisfactorily complete the walk-through examination, and I

c. Be judged satisfactory on the simulator examination.

i

8. Examination Process Critique l

The operators will be provided with an examination process critique sheet and )

encouraged to complete the form at the conclusion of the examination process.

The facility will be responsible for collating the critiques and providing them to the HQ Branch Chief, with a copy to the Regional Branch Chisf, after the l administration of the examination. The Regional Chief Examiner will compute l the mean and standard deviation for each item and include the results in the l exam report.

D. Simulator Evaluations I The purpose of this portion of the examination is to evaluate the crew's time-critical and team-dependent behavior and individual performance during l

simulated events.

Until full compliance with 10 CFR 55.45(b), for plants without a simulation facility, the facility shall propose an alternate method such as a control room mockup for the conduct of this portion of the examination. NRC will determine the usefulness of such alternatives.

1. Scenario Scope and Content The facility shall provide at least,15 simulator scenarios to the examination team. The scenarios must be approximately 50 minutes in length and both Exemirar Standards 0007.0.0 of 28

l ES-601 f

. Rev 5 10/1/88 comprehensive and realistic, i.e., not a series of unrelated events. The examination team should verify the scenarios against the facility requalification I 1

program learning obejetives and compare the critical tasks with the K/A catalog i to ensure they possess importance factors of 3.5 and above. The scenarios may i be s,odified by the team based upon the technical advisement of the facility representatives. The scenarior should be based upon lessons covered in the i recualification cycle, recent industry events, LERs, emergency and abnormal procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident prevention and mitigation. Each scenario  ;

should exercise each crew member as appropriate to his/her position during the scenario. That is, each individual should be required to perform at least one critical task during this portion of the operating test. Each simulator evaluation should place individual crew members in the most senior watch standing position in which the individual normally operates on shift. Each evaluation shall exercise the crews' abilities in the use of Emergency Operating Procedures, Technical Specifications, and the Emergency Plan.  ;

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2. . Scenario Complexity, Standards and Criteria The NRC will review scenarios to ensure tasks are compatible with  :

NUREG-1122/1123 "Knowledge and Activities Catalogs for Nuclear Power Plant  !

Operators" for abilities with importance factors of 3.0 and above. The following should also be considered:

i (a) too complex - beyond the scope of lessons covered (unrealistic)

- beyond the ability of procedures

- beyond the simulation facility capability

, (b) too simple - should be integrated events

- no team dependent behavior

- no time critical behavior

- absence of equipment malfunctions The examination team will review scenarios to ensure expected responses are l provided.

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Examiner Standards 0008.0.0 of 28

1 ES-601

. Rev 5 10/1/88 The NRC and the facility representatives as the examination team will jointly identify "critical tasks" for each scenario that are crucial to the maintenance l

of plant safety. To identify critical tasks, review the JTA or other facility  !

training materici for identification of critical tasks for each scenario. In I addition, the knowledge or ability should be rated 3.5 or above in the X/A catalog. The facility representatives' review should substantiate the task as critical to plant safety. Should the crew or individual incorrectly perform these critical tasks, this would establish a basis for an unsatisfactory 1 evaluation.

3. Simulator Examination Length and Position Rota?. ion  !

A scenario's contact time (not including time spent on briefings, simulator j setup or simulation facility problems) should average 50 minutes, based upon l real titre performance.

i Position rotation will be dependent upon facility rotation practices. Crews will.be evaluated in the simulator as they are configured by the facility for . l operating the plant. Control manipulative skills will be evaluated in the walk-through. For exarrple, senior operators may be required to perform control board operations on the simulator.

The number of scenarios shall be sufficient, with a minimum of two per crew, to l ensure that each examinee is tested to the extent that he/she may operate l during both normal and emergency operating conditions.

4. Recording and Flagging System i Any individual weakness observed on competencies detailed on NRC Form 157, page 4, will be potential items for follow-up. Follow-up may not be Examiner Standards 0009.0.0 of 28

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required if the examiner's concerns are resolved during the facility led i scenario critique.

Passive observations will be made. Questioning of operators during the scenario should only be done after the completion of the facility led scenario  ;

critique. Follow-up questions for flagged items should be asked at this time, j The Chief Examiner may nuestion the plant management representative for clarification, if necessary.

a. Individual observations - record any deficiency noted. Failure for an individual, on the simulator portion only, shall be based upon significant deficiencies that could challenge the safety status of the facility such as:

(1) inability to effectively manipulate controls (2) failure to actuate a reactor trip when required (3) failure to ensure ESFAS systems inject / actuate when required (4) failure to emergency borate or initiate ADS when required (5) violation of Technical Specifications (6) failure to take any other action or combination of actior.s that

would prevent a challenge to plant safety. I (7) Initiate inappropriate actions or combination of actions that create a challenge to plant safety.

I Significant deficiencies will nonnally be associated with identified I critical tasks as indicated in D 2 above.

b. Team observations - evaluation of crew performance will be made as directed in the "Simulator Crew Evaluation Form."

c. Flagged items of weakness noted on the simulator examination should be covered through follow-up questions after completion of the I scenario critique to determine if there is a need for remedial training, unless resolved during the facility led critique. These questions '

should also reference a K/A to indicate importance, and be reviewed by the facility representatives.

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5. Number of Examiners Required The minimum number of examiners required is one for every two operators plus one examiner as coordinator and the Chief Examiner, who may act as the coordi-nator or as an examiner.

6. Assistance of Facility Operations Management The facility will be requested to provide a member of the plant operations staff to observe the process. The Chief Examiner is the principal point of contact between the facility management and the NRC.

7. Individual / Crew / Program Simulator Evaluation Guidance l Following each scenario, the crew performance will be critiqued by the facility graders at the simulation facility. The evaluation is to be observed by the NRC sxaminers. Use the "Crew Evaluation Form" to document the results of the i examination. The facility evaluators should also complete a copy of this form.

or an equivalent facility form for each crew.  ;

la. Individual Evaluation (1) An individual may fail ti:e NRC examination based on significant j deficiencies (see0.4)observedduringthesimulator examination.

(2) An individual may fail the NRC examination based on follow-up questioning on deficiencies observed in the simulator.

(3) An individual who has passed an NRC requalification examination and is being used as a crew member may fail the examination or be found to require remedial training as a result of poor performance meeting the criteria of D.4.a.

Examiner Standards 00011.0.0 of 28

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i ES-601 l Rev 5 10/1/88 (4) NRC or facility evaluator judgement that a crew is UNSATISFACTORY in the simulator will not necessarily result in ali UNSATISFACTORY individual performance evaluation. That is, an individual operator may have made only minor errors in execution such that they were overcome during the questioning after the scenario critiques and may not have contributed significantly to the poor crew performance,

b. Crew Evaluation (1) Crew performance shall be evaluated in accordance with the "Simulator Crew Performance Evaluation Form."

(2) If a crew is judged UNSATISFACTORY in the simulator by either the NRC or the facility evaluators, the crew must be taken off  ;

shift, given remedial training, and reexamined prior to resuming licensed duties. NRC should administer the test if the

, facility's requalification program is currently judged ,

UNSATISFACTORY and NRC has not verified that adequate corrective measures have been instituted. Otherwise, the facility will be permitted to administer the reexamination.

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c. Program Evaluation l (1) A program may be judged UNSATISFACTORY if the NRC judges at least one crew UNSATISFACTORY and the facility evaluators judge that crew SATISFACTORY; (e.g., facility evaluators feel no remedial training is necessary).

(2) A program may be judged UNSATISFACTORY if there is less than 90%

agreement between the NRC and the facility on the individual pass / fail determinations with the facility evaluating fewer individuals UNSATISFACTORY.

Examiner Standards 00012.0.0 of 28

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. l ES-601 Rev 5 10/1/88 (3) If the facility evaluators judge one crew performance UNSATIS-FACTORY and the NRC does not, remedial training is indicated but the program will not be penalized for holding a higher standard of operator performance.

(4) If two or more crews are detennined to be UNSATISFACTORY, regardless of individual failures, the overall program will be judged UNSATISFACTORY.

8. Video Taping The following basic guidelines apply:

a. If equipment is available, the simulator examination will be video taped.

b. Image clarity and degree of coverage must be adequate to make taping

, useful. -

c. After initial set up of the camera by the licensee's personnel under observation of the Chief Examiner, the recording will be made with unattended camera (s). The only intervention will be to change the tape.

d. The critiques will be video taped if the scenarios are video taped.

e. Two copies of the video tape will be made, one for NRC and one for the facility.

The video tape will be used primarily to resolve areas of contention between the facility and NRC examiners' parallel evaluations of the operators.

Additionally, the facility, the examiners, and operators will be provided an opportunity to review those portions of the video tape thet directly affect the pass / fail decisions, e.g., performance of previously identified critical items, if they so request. NRC will supply the video tapes and maintain custody of cne copy and leave one copy with the facility. After examination results are Examiner Standards 00013.0.0 of 28

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ES-601

. Rev 5 10/1/88 finalized, and all cor.flicts resolved, the NRC and the facility will erase the l video tapes. The facility tape custodian will sign a statement upon receipt of the video tape indicating that the tape will be used only for its intended l prupose and will be promptly erased at the conclusion of the examination. l l

l E. Walk-Through Evaluations The purpose of this portion of the operating test is to assess the individual's understanding of and the ability to perform actions associated with plant systems and u.anipulations that operators may either perform, or direct the performance of, and to assess the requalification program's effectiveness in keeping the operator's knowledge current with respect to these important l

safety-related tasks and the associated systems.

1. Applicable Plant Systems The facility will identify those plant systems applicable to maintenance of public )

health and safety in the mitigation of the consequences of an event, and those, systems that can directly initiate an event. Criteria for system selection include: )

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a. Systems covered during the facility requalification cycle. '

1

b. New or recently modified systems.

c. Systems the subject of recent facility LERS or vendor notices (e.g., l I

GESILs).

d. PRA identified risk dominant systems /coirponents for plant or vendor j generic plants. I

e. NRC Information Notices.

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l Examiner Standards 00014.0.0 of 28 l

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ES-601 Rev 5 10/1/88 The NRC team will evaluate the facility identified systems. Absent other information, systems should be selected from those identified in Groups I and 11 of the "Examiners Handbook for Developing Licensing Examinations,"

NURF4/P" 0122 with at least 50% of the selected systems from Group I of the Hav a Selected systems will be discussed with the facility representatives to ensure optimum site specific relevance. NRC additions and/o.a substitution will be discussed with the facility representatives.

2. Identify Tasks The facility tepresentatives will review the facility JTA including learning objectives and NUREG-1122/1123 highlighting tasks / abilities for the identified systems that meet the following criteria:

a. Are applicable to the' facility,

b. Are at the A0/R0/SRO level - RO is responsible for A0/R0 tasks. The SR0 is responsible for A0/R0/SR0 tasks.

'c. Have a K/A ability rating of 3.5 or higher. Items may be used that have ratings below 3.5 after NRC examiners consult with the facility l representatives. l A list of plant specific tasks should also be developed. These are tasks / abilities that may not be specifically addressed by the JTA or l NUREG-1122/1123 but which have been covered, due to special needs, in the requalification program, e.g., special procedures, EDG operations. The facility representatives will review and concur on job applicability and importance for the complete list of tasks.

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Examiner Standards 00015.0.0 of 28 .

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ES-601 Rev 5 10/1/88

3. Job Performance Measures (JPMs)

For each of the tasks identified, review the JTA and/or learning objectives and appropriate cross references to determino the training mode. Seventy-five JPMs shall be submitted by the facility. Refer to the Lesson Plan, Qualification Card or Job Performance Measure which addresses the task. The JPMs should nelude:

a. Initial conditions

b. Initiating cues

c. References

d. Performance elements and standards

e. Cues

.f. Any appropriate output statements.

g. Appropriate knowledge areas for in-depth questions and answers.

Criteria for satisfactory completion of the task will be identified prior to administration of the examination. Critical steps which may not be included in the facility documentation of the JPM should be identified.

The team should review JPM criteria and critical steps based on the technical support of the facility representatives. The examination team should review proposed JPMs per the criteria in the "JPM Quality Checklist." All questions and answers will be reviewed by the facility representatives for job relevance and safety significance prior to examinaticn administration. If the NRC asked follow-up or probe questions during the walk-through, these questions should be reviewed as soon as possible af ter the walk-through is completed.

Examiner Standards 00016.0.0 of 28

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ES-601 Rev 5 10/1/88

4. Time Allocation '

i The walk-through will be planned for approximately 2-1/2 hours in length. This includes both the control room and in-plant time and is reflective of actual examination contact time. Time required for nonexamination evolutions / items will not be considered during examination planning. These evolutions / items include, but are not limited to, the following:

a. Trensit time to and from the' plant site.

b. T' e sper.t complying with facility security and radiological admin-istiative requirements.

c. Transient time from the control room to in plant locations.  !

d. Transit time from one in-plant location to another.

.e Time required for the operator to locate examination aides, e.g.,  :

procedures, prints, etc. j

5. lExamiration Construction and Administration f

.The walk-through will be constructed and admini; '.ered as follows: '

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a. Time should be allotted during the operating test for evaluating the performanceoften(10)JPMs. A minimum of four (4) JPMs should be evaluated outside the control room. Five of the ten tasks should be "connon" tasks. These common tasks will be administered to each operator and used in determining the effectiveness of the requalification program in preparing the operators to perform the tasks.

5. A JPM worksheet will be completed for each task.

Examincr Standards 00017.0.0 of 28

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c. The detailed questions as recorded on the "JPM Question Form" will be based upon the testing objectives established in part E.3 above and should have a K/A rating of 3.0 or above. Question construction should meet the guidelines established for the development of the written examination. The K/A for each question and correct answer will be indicated. Each JPM will have a minimum of two questions which directly relate to the JPM, and which address the basic understanding and application of knowledge of the JPM. Correct responses for these questions should not norina11y be directly found in control room references.

d .' Each examination will be reviewed by the Chief ixaminer also, using the guidance in NUREG-1021.

e. The facility examiners will conduct the walk-through while an NRC examiner grades in parallel. The NRC examiner may ask questions of the operator necessary and appropriate to ensura edequate coverage of the content of the walk-through at the completion of each JPM, and to ensure that the operator has demonstrated satisfactory understanding and application of knowledge regarding the JPM, the NRC examiner must ensure that the facility evaluator is conducting an appropriate examination.

'f. After administration, the NRC shall resolve with the facility representatives all unforeseen technical questions or issues that could result in an individual failing the examination. The facility training manager will be inforinally briefed on the preliminary results of the examinations.

6. Individual and Program Evaluation

a. Individual Performance Criteria In order to be judged satisfactory on the walk-through portion of the examination, each operator shall:

Examiner Standards 00018.0.0 of 28

ES-601 Rev 5 10/1/88 l (1) satisfactorily complett 601 )f the JPMs administered and (2) correctly answer 70% of the questions related to the 10 tasks,

b. Program Performance Criteria (1) If greater than 25% of the operators incorrectly answer more than 20%

of the common task questions (for example, 3 out of 10 questions),

a programatic weakness is indicated in the area of plant systems knowledge and systems interactions.

(2) If one or more facility evaluator (s) evalustes two or more operators as satisfactory when the NRC evaluator evaluates the same operators as unsatisfactory, the program will be found to be unsatisfactory.

F. Written Examination The purpose of the two section open reference written examination is to assess the individual's knowledge of plant systems, procedures, and operating limits inc1'uding the Technical Specifications.

Section A is a "Plant Operations" section and is normally administered on a static simula+.or. Until full compliance with 10 CFR 55.45(b), for facilities without a s^nlator, section A should be administered in a control room mockup if it exist.. If neither is available, then a classroom setting should be used. NRC and the facility being evaluated will agree on the compensatory measures (computer printouts, photographs, etc.), required for a classroom or mockup setting. Section A is designed to evaluate the operator's knowledge of plant systems, integrated plant operations and instruments and controls. In addition,recognitionofTechnicalSpecification(TS)LCOsandtheoperator's ability to diagnose postulated events shall be evaluated.

Examiner Standards 00019.0.0 of 28 l

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1 ES-601 i Rev 5 10/1/88 Section B is a "Limits and Controls" section and is administered in a classroom setting. Section B of the written examination is designed to evaluate the l ability of the operator to analyze a given set of conditions and determine the ]

proper procedural and administrative guidance.

1. Scope and Content

a. Section A - Plant Operations  ;

This section of the written examination is designed to utilize the simulator as a refe.*ence tool in answering questions. The questions should be related to plant systems, controls, and recognition of TS LCOs in an open reference format.

l This section has a minimum of two "frozen" conditions on the simulator, one condition being at power with some equipment in an )

abnormal status; one condition for which the plant has experienced a

major transient resulting in ESFAS initiation.  :

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.b. Section B - Limits and Controls j

This section of the written examination is designed to utilize plant procedures (including emergency, normal operation, and abnormal) and administrative controls (including TS, E-plan, Administrative j Frocedures) in an open reference fonnat. I

2. Item Development and Review l

a. Proposed examination items ? hall be provided as an item bank by the facility. Proposed items should be reviewed for appropriateness, clarity, and importance to safety, as described in the "Guidelines ,

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ES-601 Rev 5 10/1/88 j 1

I for the Development and Review of Open Reference Examinations." Proposed items may be modified, deleted or replaced if necessary.

b. A technical review of the references provided for each test item will be conducted to verify item accuracy. Each test item will be l reviewed for question construction with emphasis on its applicability f to an open reference examination using "NRC Checklist for Open l Reference Test Itens."

Each item should be reviewed for an associated learning objective. Learning objectives should be verified as job related and relevant. Review of lesson material for test items should be conducted to determine if the learning objectives are related to corresponding task (s) in the f acility JTA and the K/A catalog. The K/A rating should be 3.0 or above.

If a clear tie to the JTA does not exist, the applicability of the item shall be discussed with the facility representatives. Return any test items which do not meet these criteria to the facility training department for modification. .

Upon'. completion of question revision, the facility representatives should reviewalltestitemsevaluatingthemfor(1) appropriateness,(2) time required to answer each item, (3) technical accuracy, (4) clarity, and (5) K/A and objective references. After the facility representatives have completed the review, they will provide the results to the NRC for use in final examination development.

4. Sampling Plan The facility will provide a sampling plan (i.e., test specifications which identify the percentage to be sampled of each topic area) with their proposed items as described in F.2 above. The facility sampling plan should document 1 the validity of test items by linking each item topic with: (1) a K/A with an importance value of 3.0 or greater (or equivalent safety rating from a facility l JTA); (2) a facility learning objectives; and (3) safety-related tasks as l

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e ES-601 Rev 5 10/1/88 identified by the facility JTA. The NRC's sampling plan will encompass the facility's sampling plan with an addition of no more than 20% of items beyond the facility's sampling plan. The facility's sampling plan should indicate the percentage of items on Parts A and B of topics covered during the prior full recualification program. The plan should indicate the systematic approach to training basis and other materials used to develop the plan and document the comprehensivenessper10CFR55.59(a)(2).

5. Construct Additional Items Should it be necessary to develop additional items to satisfy the sampling plan, request the facility to do so. Also, the NRC team may develop items as specified in paragraph 1.4.A above. These items should also be reviewed in accordance with this standard.

6. Construct the Final Examination Using the time required to answer the test items provided by the facility, ,

construct an examination using the sampling plan. A competent operator should be able to complete the examination in I hour and 15 minutes. Once the examination is constructed, use Examiner Standard ES-107 to perform a QA review. The NRC team will review the final examination with the fecility representatives for clarity and technical accuracy. Use the attached instructions and cover sheets for examination administration. The examination shall be entered into the EQB main bank after administration.

The examination may be constructed in alternate forms, i.e., each operator may have a different sequence of questions on his/her examination. This assists in l eliminating the need for having multiple sets of reference material. Handouts  !

(e.g., plant curves, blank forms, etc.) may be piovided with the test to help l relieve the burden on the utility to provide additional sets of reference material.

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ES-601 Rev 5 10/1/88

7. Procedure for Parallel Grading Using the exanination and key, the facility and NRC will independently grade each section of the written examination. The grading of all written examina-tions shall be completed within 15 working days of the examination administration date.

8. Individual and Program Evaluation

a. Individual Performance Criteria In crder to be judged satisfactory.on the written portion of the examination, each operator must achieve at least 80% overall score as graded by the NRC.

.b. Program Performance Criteria In order for a facility's requalification program to be judged satisfactory, the following criteria must be met for the individuals evaluated:

(1) Ninety percent (90%) pass / fail decisions agreement between NRC and facility grading, and I

(2) at least 80% of all operators pass the examination.

9. Examination Proctoring Each section of the examination shall be proctored in accordance with ES-201.1 and form ES-201-3 shall be completed.

10. Reference Material The facility shall be responsible for providing the following reference materials:

Examiner Standards _ _ _ _ 00023.0.0_of._28_,__ _ _

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ES-601 Rev 5 10/1/88 During the "Plant Operations" (Section A) portion of the examination, one copy of all controlled material available in the control room should be available to examinees. Examination reference material will NOT include material that is intended for training use only. All reference material must be authorized for actual operation of the power plant.

Duringthe"Lir.itsandControls"(SectionB)portionoftheexamination,each examinee shall have available for use the following material (complete, controlledcurrentissue):

a. Technical Specifications

b. Plantprocedures(EOP/A0P/0P,etc.)

c. Emergency Plan (as available in the control room)

d. Administrative procedures applicable to operations

'e.

Other plant reference material normally available in the control room (e.g., curves and data book, forms, plant drawings, flow charts, )

etc.).

NOTE: "Non-controlled" reference material, such as the Emergency Procedure Owner's Group Basis Documents will not be provided unless the facility certifies that these documents are authorized to be used during plant operations, i l

G. Actions Required for Unsatisfactory Individual or Program Evaluation

1. Unsatisfactory Individual Evaluation If an operator fails an NRC administered requalification examination, the operator shall be removed from licensed duties until remediation and Examiner Standards 00024.0.0 of 28

i ES-601 Rev 5 10/1/88 reexamination has been completed satisfactorily. NRC should administer the test if the facility's requalification program is currently judged UNSATISFAC-TORY and the NRC has not verified that adequate corrective ineasures have been f instituted. Otherwise, the facility will be permitted to administer the j reexamination for returning the individual to licensed duties; however, license renewal would require another NRC administered exam.

2. Unsatisfactory Requalification Program Evaluation For any program evaluated as unsatisfactory, the following actions are required unless findings indicate otherwise. Additional actions may be taken at the discretion of the Regional administrator or his designee. The stquence of actions below is not required. The determination whether plaat shutdown is required should be ongoing until the Regional Administratar or his designee has reviewed all in (d) below.

a. Require the facility to identify pregram deficiencies and corrective actions required to improve operr. tor performance.

'b. Meet with senior facility management to review audit findings.

identified deficiencies, root causes, corrective actions proposed, schedule for corrective action implementation, and follow-up inspections and examinations.

c. Determine the required corrective actions by the facility, the required follow-up by the NRC, and the schedule for each.

d. The Regional Administrator or his designee shall determine whether plant shutdown pending completion of corrective action is required. l This decision should be based on the:

1 (1) Significance of generic performance deficiencies identified l during the program evaluation, l l

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ES-601 Rev 5 10/1/88 (2) Recent SALP performance, especially as related to Criterion 7, Training Effectiveness and Qualification.

(3) Recent facility events which relate to licensed operator performance, and (4) Recomendations by resident inspectors.

H. Operator License Renewal policy

1. Licenses for o'perators and senior operators will be renewed upon timely application, as described in ES-109/110 if the individual in question has successfully passed an NRC requalification examination within the term of 1 his/her license, i

2. If an individual licensee his been administered an NRC requalification '

'exsmination two (2) times durir.g the term of his/her license without pass-ing any examination, then his/her license will be terminated or will  ;

expire without renewal and he/she may apply for license under 10 CFR 55.31 and sucessfully ccrplete an NRC license examination to maintain a license.

3. If an individual has not successfully passed an NRC requalification  ;

. examination within the term of his/her license but has failed an NRC requalification examination fewer than two (2) times, then the individual license is extended under the timely application provisions until the next NRC requalification examination. After the results of that examination, the individual will conform with either H.1 or H.2 above.

4. If an individual has passed one (1) NRC requalification examination curing the term of his/her license then the provisions of H.1 apply without regard to the facility requalification program status or any subsequent or prior unsuccessful NRC requalification examination (s).

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ES-601 Rev 5 10/1/88 I. Final Requalification Program Evaluation Report A final requalification program evaluation report similar to the final examina-tion report for a licensing examination shall be prepared when the grading of requalification examinations has been completed. A complete copy of the report shall be filed in the facility requalification file. A copy of the NRC Adnin-istered Requalification Examination Results Sumary, shall be forwarded to the Management Assistant, Regional Support and Oversight Section, OLB. The results summary is required to verify OLTS data and for statistical data.

J. Record Retention

1. A facility requalification file shall be maintained for each facility.

All evaluation forins, records, assignment sheets, and correspondence relating to the requalification program audit for the latest two evaluations shall be retained.

2. ,When the requalification evaluation has been completed by the Regional Office, a copy of all NRC administered written, oral and simulator

' examination results shall be supplied to the facility. The facilitiat are

. required to maintain these records until the operator's or senior operator's license is renewed in accordance with 10 CFR 55.59.

3. 'A copy of the results sumary shall be sent to the Management Assistant, Regional Support and Oversight Section, OLB. These sumaries shall be used for statistical data gathering.

4 Material relating to an individual failure shall be retained by the Regional Office as necessary to support denial of license renewal per 10CFR55.57(b)(2)(iv).

Examiner Standards 00027.0.0 of 28

ES-601 Rev 5 10/1/88 Attachments:

1. Corporate Notification Letter

2. Examination Process Critique Sheet

3. Simulator Crew Evaluation Form

4. .1PM Work Sheet

5. JPM Question Form

6. Briefing Sheet

7. Written Examination Cover Sheet

8. JPM Quality Checklist

9. Sirolator Scenario Peview Checklist

10. Guidelines for the Development and Review of Open Reference Examinations

11. NRC Checklist for Open Reference Test Items 1

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ATTACHMENT 1 CORPORATE NOTIFICATION LETTER (INSERTCORPOP.ATEADDRESSEE)

SUBJECT:

REQUALIFICATION PROGRAM EVALUATION In a telephone conversation between M (title)andM (Section Chief), arrangements were made for an evaluation of the requalifica-tion program and licensed personnel at the (facility name). The evaluation visit is scheduled for the week of (date).

For this vir.it, the NRC examiners will administer NRC presared operating and written examinations. The NRC examiners will discuss wit 1 the appropriate facility personnel and operators the schedule and the process for these examinations. For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclo-sure 1 "Reference Material Requirements." M has been advised of our reference material requirements and where they are to be sent.

NRC reserves the right to declare a facility training program unsatisfactory and to postpone NRC administered requalification examinations if the facility '

generated materials are inadequate for examination preparation. Enforcement action may be considered if necessary to bring facility generated material to the 1,evel of quality necessary for examination preparation.

Additionally, it is requested that a licensed SRO from both the (plan'tname)OperationsDepartmentandTrainingDepartmentbedesignatedas the facility representatives for these examinations. These individuals must not be scheduled for an NRC administered examination during this visit, or participate as an instructor once selected. Also, the facility representatives will be required to certify that, as a result of their involvement, no portion of the examination has been knowingly compromised.

The facility managenent is responsible for providing adequate space and acconnodations to properly develop and conduct the examinations. Enclosure 2, "Administration of Requalification Examinations," describes our requirement, for developing and conducting the examinations. M has also been informed of these requirements. Also, a facility operations management representative should observe the simulation facility examination process at the site.

Enclosure 3, contains the "NRC Rules and Guidance for Examinees" that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all operators are aware of these rules. Enclosure 4, "Requirements and Procedures for Requalification Examina-

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tions," is included for your guidance and information in preparing for these l examinations.

This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101, which expires May 31, 1989. Coments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office ,

Washington, DC.

Thank you for your consideration in this matter. If you have any questions on the evaluation process, please contact (Regional Section Chief and telephone number).

Sincerely, I

(Appropriate Regional Title)

Enclosures:

1. Reference Material Requirements

2. Administration of Requalification Examinations

3. NRC Rules and Guidance for

, Examinees DISTRIBUTION:

Project Manager i Branch Chief, OLB Resident Insnector Regional Sec' tion Leader Examiner (s)

Facility Training Coordinator Facility Operations Manager I

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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS For the written examination, the following items must be provided to the MRC 60 days prior to the examination date:

1. Proposed RO and SRO requalification written examination test items. (A minimune of 350 per section of the examination.)

Since the written examination is open reference, examination items must meet the following:

a. Items that require only memorization or recall are not permitted;

b. Items should require that the examinee comprehend, interpret, integrate, or apply available information;

c. Items should contain situations, aspects, or conditions that do not duplicate lesson plans or references; and .

.d. Items should require examinees to locate and use references.

.The written examination will be composed of two sections, each designed to

be completed in 1-1/2 hours. Each section will be separate. Section A will be administered on a static simulator; Section B will be administered

'in a classroom setting. Section A is designed to evaluate the operator's knowledge of plant systems, integrated plant operations, and instrumenta-

' tion and controls. In addition, recognition of Technical Specification LCOs and the operator's ability to diagnose postulated events should be evaluated. Section B of the written examination is designed to evaluate the ability of the operator to analyze a given set of conditions and determine the proper procedural and/or administrative guidance.

2. All reference material and objectives for the proposed test items.

For the simulation facility, the following items must be provided to the NRC 60 days prior to the examination date:

1. A minimum of 15 scenarios The scenarios should sample areas such as LERs, emergency and abnonnal procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident prevention and mitigation. The scenarios should evaluate each crew member as appropriate to his/her license, and shall exercise their abilities in the use of Emergency Operating

7 .

Procedures T ThescenarIo'echnicalSpecifications,andtheEmergencyPlan.

s net time (not including time spent on briefings, setup or simulation facility problems) should average 50 minutes, based upon real time performance.

For the plant walk through examination, the following items must be provided to the NRC 60 days prior to the examination date:

(1) A list of systems and topics appropriate to the plant walk through examination that were covered during the requalification cycle and are important to safety. All reference material required to support an examination on these topics should be provided.

(2) Seventy five (75) job performance measures.

These performance measures should be both in plant and control room operator functions, that are required for the safe opera-tion of the facility. They shall include acceptable performance '

criteria.

(3) Any additional reference material required for examination preparation will be requested by the examination team.  ;

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ENCLOSURE 2 ADMINISTRATION OF REQUALIFICATION EXAMINATIONS

1. 20 percent of the facility licensed operators shall be selected for evaluation. Normally the crew currently in the requalification cycle will be selected. A random sample without replacement will be used to preclude a satisfactory operator from being subject to reexamination by the NRC during the term of the license. Thesamplewillincludeothershift(s) made up of licensed personnel who are not routinely performing shift duties.

2. The simulator and a simulator operator (s) will be provided for examination development. The date(s) and duration of time needed to develop the examinations will be agreed upon by the chief examiner and the facility.

3. The reference material used in the simulator will be reviewed by the chief examiner. No material will be made available that is solely used for

' training, l

4. 'A single room shall be provided for completing Section B of the written '

/ examination. The location of this room and supporting rest room facili- l

' ties shall be such as to prevent contact with all other facility and/or

. contractor personnel during the duration of the examination.

5. 'Hinimum spacing is required to ensure examination integrity as determined

'by the chief examiner. Minimum spacing should be one examinee per table, with a 3 foot space between tables. No wall charts, models, and/or other

' training materials shall be present in the examination room.

6. Copies of reference material for Section B of the written examination will I be provided for each examinee. The reference material will be reviewed by l the chief examiner and will consist of Technical Specifications, '

operating / abnormal procedures, administrative procedures, Emergency Plans as available to the plant operators. '

7. Video taping capabilities can be utilized. The facility should contact the chief examiner for restrictions related to its usage.

8. Since connon tasks and detailed systems knowledge will be probed during the walk through portion of the o)erating test, operators will be re-quested not to discuss the walk t1 rough with other examinees until after the complete examination has been administered.

9. An atter t will be mde to distinguish between R0 and SRO knowledge and abilitit , to the extent that such a distinction is supported by the facility training materials.

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,o ENCLOSURE 3 NRC RULES AND GUIDANCE FOR EXAMINEES

1. Use black ink or dark pencil ONLY to facilitate legible reproductions.

2. Print your name in the blank provided on the cover sheet of the examination.

3. Fill in the date on the cover sheet of the examination, if necessary.

4. Answer each question on the examination. If additional paper is required, use only the lined paper provided by the examiner.

5. Use abbreviations only if they are connonly used in facility literature.

6. 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.

7. Show all calculations, methods or assumptions used to obtain an answer to

',a mathematical problem, whether asked for in the question or not. '

8. tnless solicited, the location of references need not be stated.

9. : Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.

10. If parts of the examination are not clear with respect to their intent. l

'ask questions of the examiner only.

11. You must sign the statement on the cover sheet that indicates the work on i the examination is your own and that you have not received or been given l any assistance in completing the examination. This must be signed AFTER 1 the examination has been completed.

12. Rest room trips are to be limited and only one examinee at a time ray leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.

13. Cheatino on the examination would result in a revocation of your license I and could result in more severe penalties.

14. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for a total of four hours.

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15. Due to the existence of questions that will require all examinees to refer i to the ser.e indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheatir,g.

16. When you are finished and have turned in your completed examination, leave the examination area.

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ATTACHMENT 2 EXAMINEE CRITIQUE OF NRC REQUALIFICATION EXAMINATION As part of its efforts to improve all aspects of the NRC requalification examination process, NRC is asking all test-takers to provide feedback on these examinations. Please use this form to comment on the NRC requalification examination that you have just completed. After you have answered the questions celow, and provided any comments that you wish to make, please give this form to your training manager who will send it to the NRC Regional Branch Chief.

Please take a few minutes and respond to each of the following questions, by circling the number that best represents your experience on the examination jest completed. Each question is written in the form of a statement, and the number which you circle indicates how strongly you agree or disagree with that statement. For example, if you circle number I for a particular question, that indicates that you are in strong agreement with the statement. If you circle number 4, that indicates mild disagreement. If you circle number 3, that indicates that you neither agree nor disagree with the statement made in that question.

THEkE ARE NO RIGHT OR WRONG RESPONSES. Your participation is strictly voluntary, but please remember that your responses, together with any comments that you might have, will help to improve the requalification examination process. All responses are anonymous.

WRITIENEXAMINATION: ,

1. 'The content of the questions reflected the content of the requalification

,prograr at my plant.

Strohglyagree Strongly disagree 1 2 3 4 5 Comments: , , _ _

Mm.

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2. The overall time allotted for the examination was sufficient to answer all the questions.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

The information to be used to answer each question was available.

3.

Strongly agree Strongly disagree 1 2 3 4 5 Coments:

e

4. There was an opportunity for me to have any questions regarding the

. examination clarified prior to the end of the examination.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

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1 OPERATING TEST:

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1. The content of the JPMs and the questions on the walk-through portion was consistent with the content of the requalification program at my plant.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:

2. The overall time allotted for the walk-through portion of the operating test was appropriate.

Strongly agree Strongly disagree

. I 2 3 4 5 e

Comments:

3. The scenarios used for crew evaluation on the simulation facility portion of the operating test were consistent with team (crew) training at my plant.

Strongly agree Strongly disagree 1 2 3 4 5 Comments:  ;

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4. The instructions for the conduct of both portions of the operating test were clearly explained by the examiner (s). _,

Strongly agree Strongly disagree 1 2 3 4 5 Comments: .

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ADDITIONAL COMMENTS ON THE CONTENT AND/OR CONDUCT OF THE NRC REQUALIFICATION WRITTEN EXAMINATION AND OPERATING TEST JUST COMPLETED:

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4 PLEA $E CIRCLE THE LEVEL OF THE EXAMINATION JUST COMPLETED: R0 SRO PLEASE DO NOT INDICATE YOUR NAME ON THIS QUESTIONNAIRE.

THANK-YOU.

This request is covered by Office of Management and Budget Clearance Number 3150-0011 which expires December 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Room 3208, New Executive Office Building, Washington, DC 20503.

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ATTACHMENT 3 INSTRUCTIONS ON USE OF SIMULATOR CREW EVALUATION FORM Enclosed is an evaluation form for use during the trial simulator examination component of the requalification examination. In keeping with the purpose of the requalification exam, these scales are geared toward evaluating the crew as a whole, rather than individual operators. Please follow the instructions below when rating team performance on the simulator examination:

1. Review the rating scales prior to the onset of the simulator examination to familiarize yourself with each performance issue to be evaluated.

2. Use the "Operator Actions" Form (ES-302, attachment 6), and the expected operator actions included on that form, to make notes during the examination, as described in ES-302,

3. Immediately after the simulator examination is over, evaluate the crew by completing the Simulator Crew Evaluation Form. Be sure to address all the rating factors for all 6 competencies.

4. Provide an overall rating of "satisfactory" or "unsatisfactory" for each competence. If you gave the crew move than one rating of "1" on the rating factors for that competence, your score for them on that competence overall should be "unsatisfactory." Although part of the purpose of the walk-through is to follow up on areas of weakness noted during the simulator portion of the examination, if the crew receives a rating of "unsatisfactory" on one or more competences, their overall evaluation should also be '

unsatisfactory.

, 5. There is space for comments beneath each competence rating and below the overall rating. This space is provided if you feel the need to annotate or explain rating (s). In particular, use this space to document the failure of an individual candidate due to his/her exceptionally poor performance.

We need your feedback to evaluate the usefulness of these ratings scales.

Af ter you have had an opportunity to use the form, please provide us with the following information:

Were the scales clear, concise, and easily understood?

Were the scales written so that you could evaluate crew (versus individual) performance?

Could you comfortably decide which ratings to give the crew, based on the decriptions of the performance provided? If not, how could these descriptions be improved?

Were there rating issues which you believe are not appropriate for simulator requalification examinations?

Were there any performance issues missing from these rating sceles?

, Please note your comments and suggestions on the page provided at the back of the evaluation form and provide them to John Hannon at the exit meeting.

Thanks very much for your assistance.

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SIMULATOR EXAMINATION

SUMMARY

SHEET CREW MEMBERS:

Name Position OVERALL TEAM RATING ON THE SIMULATOR EXAMINATION:

Satisfactory Unsatisfactory Coments:

Please use the space below to note your coments on the evaluation form (attach additional pages, if necessary):

+

6

UNDERSTANDING / INTERPRETATION OF ANNUNCIATOR / ALARM SIGNALS DID THE CREW:

(a) NOTICE and ACKNOWLEDGE alarms, and ATTEND T0 alarms in order of their importance/ severity?

3 2 1 All alarms that directly Minor awarenes. or Failed to notice related to significant response difficulties and/or extremely I changes in plant or lapses slow at responding l conditions were noted to significant alarms at critical times; easily j distracted by .

I nuisance alarms (b) Correctly INTERPRET the meaning and significance of alarms and annunciators (including the use of the Alarm Response Procedures, as applicable)?

3 2 1 Crew'readily determined Minor inaccuracies in Significant misin-what failures / events alarm interpretation terpretations, .  !

alaris were indicating but without safety resulting in plant j related consequences degradation (c) l VERIFY that annunciators / alarm signals were consistent with plant / system l conditions?

3 2 1 All necessary verifi- Minor lapes in alarm Verification of cations performed, verification, but no failed systems including the identi- inappropriate actions was poor or fication of erroneous taken as a result of altogether absent alarms inadequate verification SCORE ON UNDERSTANDING / INTERPRETATION OF ANNUNCIATORS / ALARM SIGNALS:

Satisfactory Unsatisfactory Comments:

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DIAGNOSIS OF EVENTS / CONDITIONS BASED ON SIGNALS / READINGS DID THE CREW:

(a) RECOGNIZE off-normal trends / status?

3 2 1 Timely and accurate Recognition of trends Failed to recognize recognition of trends at time of, but not trends, even after even prior to alarms prior to, sounding of sounding of alarms and alarms annunciators (b) USE INFORMATION and use REFERENCE MATERIAL (prints, books, charts) to aid in the diagnosis / classification of events and conditions?

3 2 1 Correct, timely use Minor errors by crew Failure to use of information and in use or interpretation reference material, reference material of information and misuse / misinterpretation led to accurate reference material of information resulted diagnoses in improper diagnoses (c) . Correctly DIAGNOSE plant conditions based on those control room indications? l 3 2 1 Diagnoses by crew Minor errors /diffi- Faulty diagnoses were accurate and culties in diagnoses resulted in timely incorrect control manipulations SCORE ON DIAGNOSIS OF EVENTS / CONDITIONS BASED ON SIGNALS / READINGS:

Satisfactory Unsatisf actory Comments:

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UNDERSTANDING OF PLANT / SYSTEMS RESPONSE DID THE CREW:

(a) LOCATE and INTERPRET control room indicators correctly and efficiently to ascertain and verify the status / operation of plant systems?

3 2 1 Accurate and efficient Minor errors in locating Serious omissions instrument location & or interpreting instruments delays or inaccuracies interpretation by all and displays; some crew made in instrument crew members members required assistance interpretation (b) Demonstrate an UNDERSTANDING of how the plant, systems, and components operate, Jncluding setpoints, interlocks, and automatic actions?

3 2 1 All crew members demon- Minor instances of errors Inadequate knowledge strated thorough due to gaps in crew of system / component understanding of how knowledge of :ystem/ operation resulted in systems / components component operation; some serious mistakes or operate crew members required plant degradations assistance (c) Demonstrate an understanding of how their ACTIONS (or inaction) affected system / plant conditions?

. 3 2 1 All members understood Actions or directives Crew appeared to act the effect that indicated minor without knowledge of, actions or directives insecuracies in under- or disregard to, effect had on plant / system standing by individuals, on plant conditions but actions were corrected by team SCORES CN UNDERSTANDING OF PLANT / SYSTEM RESPONSE:

Satisfactory Unsatisfactory Comment:

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COMPLIANCE /USE OF PROCEDURES AND TECHNICAL SPECIFICATIONS DID THE CREW:

(a) REFER T0 the appropriate procedures in a tit.aly manner?

3 2 1 Crew used procedures Minor failures by Failed +c correctly as required; knew crew to refer to refer to procedures when what conditions were procedures without required, resulting in covered by procedures prompting, but did faulty system operation and where to find them affect plant status (b) CORRECTLY IMPLEMENT procedures, including following procedural steps in correct sequence, abiding by cautions and limitations, selecting correct paths on decision blocks, and correctly transitioning between procedures?

3 2 1 Timely, accurate Minor instances of Importance procedural enactment of procedural misapplication, but steps were not enacted staps by crew, corrections made in correctly, which led demonstrating thorough sufficient time to to impeded and/or slow understanding of avoid adverse impact recovery or unnecessary procedural purposes / bases degradation (c) '. RECOGNIZE E0P ENTRY CONDITIONS and carry out appropriate immediate -

actions without the aid of references or other forms of assistance?

3 2 1 Cons) stent'"accurate Minor lapses or Failed to accurately and timely errors; individual recognize conditions recognition > i crew members needed or execute actions, implementatic- assistance from others even with use of aids ,

to implement procedures  !

l (d) CORRECTLY RECOGNIZE and COMPLY with Technical Specifications and Action  !

Statements of LCO ?

3 2 1 Recognized and Minor difficulties in Failure to recognize /

fully complied with referring to and/or comply with Tech Spec LCOs/ Action Statements applying Tech. Specs.; LCOs crew bad to prompt SRO on TS requirements SCORE ON COMPLIANCE /USE OF PROCEDURES AND TECHNICAL SPECIFICATIONS:

Satisfactory Unsatisfactory Lomments:

10

1 CONTROL BOARD OPERATIONS DID THE CREW:

(a) LOCATE CONTROLS efficiently and accurately?

3 2 1  ;

Controls and Instances of Instances of failure indicators were hesitancy / to locate controls located without difficulty in jeopardized system hesitation by locating controls status individual operators by one or more operators (b) MANIPULATE CONTROLS in an accurate and timely manner?

3 2 1 Smooth manipulation Minor shortcomings Mistakes made in of the plant in manipulations, manipulating controls within controlled but recovery from caused system carameters errors without transients end causing problems related problems (c) 'Take MANUAL CONTROL of automatic functions, when appropriate?

3 2 1 -

All operators took Minor delays and/or Failed to control control, and smoothly prompting necessary automatic systems operatored automatic before overriding / manually, even when syst9ms manually, without operating automatic ample time and assistance, thereby functions, but plant indications existed 1 averting adverse events transients were J avoided when possible l l

SCORE ON CONTROL BOARD OPERATIONS.

Satisfactory Unsatisfactory _

Comments:

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COMMUNICATIONS / CREW INTERACTIONS DID THE CREW:

(a) EXCHANGE complete and relevant information in a clear, accurate, and attentive manner?

3 2 1 Members informed each Communications generally Members did not other of relevant info. complete and accurate, inform each other and actively sought and but some instances of of abnormal indica-listened to info. from needing to be prompted, tions or when others as/when necessary or f ailing to acknowledge performing evolutions; or respond to info. from inattentive when others important info. was requested or provided (b) INTERACT with other regarding issues / circumstances outside of their individual area of responsibility to facilitate safe plant conditions?

3 2 1 Members assumed Members listened to Members were responsibility for each others conversations inattentive to what issues outside their in general; major technical was happening own boards, as errors corrected around them; poor appropriate coordination of -

activities (c) , HAKE TEAM DECISIONS in a timely, effective manner?

3 2 1 All individuals provided Major team decisions Leader or other crew input to decisions. generally included members did not accept Decisions resulted in early, input fram most crew input from others, recuperative action members, but some resulting in incorrect delays or other or untimely decisions /

problems in reaching directives effective decisions SCORE ON COMMUNICATIONS / CREW INTERACTIONS:

Satisfactory Unsatisfactory Comments:

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ATTACHMENT 4 JOB PERFORMANCE MEASURE WORKSHEET Facility:

Task

Title:

Task No.:

Job Performance Measure No.:

K/A

Reference:

Operator:

Evaluator: Date:

Applicable methods of testing:

Simulate performance Actual performance Classroom Simulator Plant READ TO THE OPERATOR I wi,11 explain the initial conditions, which step (s) to simulate or discuss,.

and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.  ;

Initial Conditions:

Task Standards:

Required Materials:

General

References:

l Initiating Cues: l l

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PERFORMANCE INFORMATION (Denote critical steps with a check mark)

Performance step:

Standard:

Comment:

Performance step:

Standard:

Comment:

Performance step:

Standard: .

Comment:

. Performance step:

Standard:

Comment:

Performance step:

Standard:

Comment:

Terminating cue:

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1 VERIFICATION OF COMPLETION Job Performance Measure No. .

l l

Operator's Name:

1 Date performed:

Evaluator:

Number of attempts:

Result: (Denote by an S for satisfactory or a U for unsatisfactory and requires remedial training).

Evaluator's signature and date: _

S 9

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

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ATTACHMENT 5 SYSTEM WALK-THROUGH TEST PLAN Page_ of_

Facility: System Topic: Performance Measurement:

, Question  : KA Rating _

Answer:

l Response /Coments:

Question  : KA Rating Answer:

Response /Coments:

Question  : KA Rating Answer:

Response / Comments:

Question  : KA Rating Answer:

Response / Comments:

16

SYSTEM WALK-THROUGH FOLLOW-UP DOCUMENTATION Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam):

Response (to be completed during exam):

Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam):

Response (to be completed during exam):

Ques-tien Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Quest. ion (to be completed during exam):

Response (to be completed during exam):

Question Derivation (can be completed af ter examination):

Sirulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measurement

2. Question Number Question (to be completed during exam):

Response (to be completed during exam):

17

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c. .

ATTACHMENT 6 BRIEFING CHECKLIST - SYSTEM WALK-THROUGH

1. If the NRC examiner is a visitor, escort responsibility for ensuring compliance with safety, security and radiation protection procedures 1 is the responsibility of the operator escorting the examiner.

4 Plant equipment should not be operated. Mothing the facility or NRC l

2.

examiner says or asks will be intended to s'olate that principle, i l

3. If clarificr ion of questions is needed duri.ig tN walk-through, there should be no hesitation to request the examiner reword or clarify the question. l 4

4. The examiner will be taking notes throughout the test to document operator performance. Frequently an examiner will stop questioning for this purpose.

The amount of note-taking is not dependent upon the operator's level of performance. The examiner must document satisfactory as well as less than satisfactory performance. l S. The walk-through is considered "open book." The reference material in the facility / control room which is normally available to operators is available, including calibration curves, previous log entries, piping and instrumentation

' diagrams, calculation sheets, and procedures. However, operators are respons-ible for knowing from memory the immediate actions of emergency and other

' procedures as appropriate to the facility. .

6. 'The system walk-through has been planned for approximately two hours in length. However, there is no specific time limit for the walk-through.

,The examiner will take whatever time is necessary to cover the areas selected, in the depth and scope required. There will be a minimum of 4

, Job Performance Measures (tasks) evaluated from the control room and 4

. Job Performance Measures evaluated outside of the control room. However, the total number of JPM's will be no less than ten (10).

7. The examiner will explain what tasks are to be completed, which steps to simulate or discuss and provide initial conditions. The operator is to proceed with completing the task as if directed by plant procedures and/or shif t supervision. During the task the examiner will supply the necessary plant conditions and/or parameters needed to simulate the task. The operator should explain each step of the task to the e.aminer v before doing it.

8. When all of the steps for each task are performed correctly, the criteria for the examination will have been completed.

9. If the operator feels the need for a break during the walk-through, the operator should request this from the examiner. The examiner is not allowed to reveal the results of the walk-through at its conclusion.

10. The NRC examiner may ask clarifying questions of the operator at the end of each JPM.

18

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Part B - For tests with simulation facility available

1. The primary responsibility is to operate the simulation facility as if it-were the actual plant.

2. Team work and communication between operators is evaluated. It benefits the exam process to verbalize observations, analysis, and reasons for.

actions more than normally would be done during actual plant operations.

3. If an operator recognizes an incorrect decision, response, answer, analysis, action taken, or interpretation of the team of which the operator is a part but fails to correct, then the examiner may assume that that operator agrees with the incorrect item.  ;

4. A rough los may be kept during each exercise that would be sufficient to complete necessary formal log entries which may be evaluated under admin-istrative topics.

5. A designated facility instructor will act as the auxiliary operators, radiation health and chemistry technicians, maintenance supervisors, plant management, and anyone else needed outside the control room area.

6. The facility examiner will provide a shift turnover before the exercise begins. The shift turnover will include present plant conditions, power history, equipment out of service, abnormal conditions, surveillance due,

'and instructions for the shift.

7. ',The control board switches may be purposely misaligned to enhance a simulated scenario or transient where appropriate and is not part to the evaluation. If misaligned, they should be tagged or otherwise highlighted as appropriate to the facility. The examiner will not misalign switches

• during the scenario as an awareness drill. l Note: The chief examiner has the option to tell the operators that no control board switches will be misaligned on a given scenario or set of scenarios.

If no switches are misaligned, the chief examiner may wish to reduce the l time it takes of the operators to complete the board walkdown and accept i the shift. )

8. Operators will be allowed three to five minutes to familiarize themselver with the status / conditions of the control boards prior to the start of the exercise.

9. The simulation facility part of the examination will consist of a minimum of two exercises lasting approximately 50 minutes each. There will be a short break between exercises to set up the initial conditions for the next exercise.

10. If operators have any questions concerning the administration of the operating 4 test, those questions should be answered prior to the start of the test. I 19

ATTACHMENT 7 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY:

REACTOR TYPE:

DATE ADMINISTERED:

OPERATOR:

% 0F SECTION CATEGORY OPERATOI.'S CATEGORY VALUE SCORE VALUE A Plant Proficiency B Limits and Controls Final Grade 0 8 6

4 20

=

ATTACHMENT 8 JOB PERFORMAk:E MEASURE QUALITY CHECXLIST

1. Supported by facility's job / task analysis.

2. Operatierelly important (meets threshold criteria of K/A 3.5 or as determined by the facility and agreed to by NRC).

3. Designated as either SRO only or both R0/SRO.

4. Time validated (time allowed for task completion indicated on JPM).

Questions related to the task need not be time validated.

5. Either the task itself or the questions that follow require operator problem recognition and diagnosis. Questions require knowledge correct

. actions for abnormal system responses whenever applicable.

6. 'Perforr.ance standards are specific in that exact control and indication nomenclatureandcriteria(switchposition,meterreading)arespecified, even if such criteria are not specified in the procedural step.

7. Critical elements and associated performance standards are identified and agreed to by the facility and the NRC.

8. Performance standards should provide complete and proper system response cues where appropriate such that the exrniner , 'roperly cue the operator when asked.

. l 1

9. Answers to questions at the end of the task are NOT found directly in the procedure just used (i.e., do not ask why a certain caution exists if the l caution itself identifies the answer).

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- -- ,_ _- . . - _ . . - _ _ _ _ , , , , , . _ - - , - , - - . . - , _ _ _ . - - - _ , , , . . - , . - - - . - ..--..-,,-.,1-- . .-

.a a ATTACHitENT 9 Rev. 1 4/15/88 SIMULATOR SCENARIO REVIEW CHECKLIST (Attach separate copy to each scenario reviewed)

REVIEWER:

SCENARIO IDENTIFIER:

1. Scenario contains at least one (1) time-critical crew response.

Time-critical is defined to require affirmative action by one or more crew member (s) in order to prevent or mitigate an event within a limited time.

2. Scenario contains at least one (1) team-dependent crew response.

Team-dependent is defined to require transfer of information between crew members in order to prevent or mitigate an event.

4

'3 . The scenario events involve each crew member.

4. Scenario is composed of related or linked events.

5. Scenario requires the use of: (checkthosethatapply)

Abnormal operating procedures Emergency operating procedures Technical Specifications Emergency plan implementing procedures

2

6. Critical tasks are:

Identified by facility Required to prevent or mitigate event Importance factor 3.5 in K/A Catalog or facility JTA Scenario events have K/A importance factor 3.0 7.

1

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QACHMENT10 GUIDELINES FOR THE DEVELCPMENT AND REVIEW OF OPEN REFERENCE EXAii! NATIONS

1. Introduction l l

The following guidelines are intended fo.* thnse who are involved in the development and/or review of test items for the written portion of the NRC Requalification Examination. As described in ES-601, "Administration of NRC Requalification Program Evaluations," the written examination consists of two sections, one that utilizes the simulator to provide a context for questions I on plant systems and controls, and a second that focuses on plant procedures and administrative controls. Both sections are administered in an "open reference" format. Candidates are allowed to use reference material, including simulator displays, during examination administration. ,

The intent of the change from closed to open reference written examinations, ,

is twofold:

I (1) Examination Yalidity. By permitting the use of references that are '

available to the operator, the conditions and requirements of the written examination more closely approximate those of the actual job. The infonnation provided to the operators in the test items can and should closely parallel the information typically available to them on the job, while the responses elicited by the questions should be similar or identical to the decisions, solutions, and actions required for effective job performance. In other words, the open reference format enhances the match between job demands and test demands -- a cornerstone of examination validity.

1 1

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(2) Level of Knowledge. The open reference fonnat also enhances examination  !

validity by elevating the level of knowledge of the test items. As described later in these guidelines, candidate access to references precludes the use of questions that test for the mere recall of facts and specifics. Instead, open reference test items require test takers to demonstrate that they can apply, analyze, evaluate, or otherwise USE knowledge to handle the problems and issues encountered on the job.

II. Open Reference Guidelines Most principles for effective test ite.a construction apply equally to all types of written questions, regardless of forinat. Therefore, open reference  ;

test item developers and reviewers should consult references such as NUREG )

BR-0122, "Examiners' Handbook for Developing Operator Licensing Exarinations,"

1 INP0's "Principles of Training System Development Addendum I, Test Item Development," and NUMARC's "Guidelines for Developing Written Test items for the NRC Requalification Exam." The guidelines below are those that have been l found to be especially pertinent to the creation of open reference test items. These ,

I guidelines are divided into five categories:

~

(1)SelectionofTestTopics (2) General Guidelines for Sections A & B (3) Specific Guidelines for Section A, "Plant Operations" (4) Ideas for Open Reference Formats (5) Open Reference Test Item Review Checklist (1) Selection of Test Topics Test item topics for the NRC requalification examination should be selected based on the following criteria.

A. Requalification Training Prograrn Curriculum. Test topics should be based on the curriculun. of the most recent operator requalification program training cycle. However, NRC may substitute up to 20% of the examination topics selected by the facility with subjects not emphasized during the requalification cycle under 10 CFR 55.59.

j B. Performance Basis. Like the requalification program itself, test topics should be drawn from a job-task analysis (JTA) of the operator and senior operator positions. The facility should validate their test items by demonstratinc a link between each item and the following JTA products:

- important operator tasks as identified by the JTA

- important K/As (rated 3.0 or higher) as identified in the NRC K/A Catalog (NUREG 1122/1123) or a facility-specific K/A catalog

- facility learning objectives identified as important to safety C. Adequacy of Test Coverage. The facility's proposed sampling plan (or curriculum evaluation plan) should by checked to ensure that it provides balanced, cocprehensive coverage of the topics covered during the requalificaticn training cycle. Facility test item topics may be revised if subject areas are found to be under or over-represented in the sampling plan relative to their coverage in the requalification program. In addition, 20% may be substituted by the NRC. Recentsafety-relatedissuesandevents(e.g.,relevantLERs) should be addressed in the sampling plan.

(2) heneral Guidelines The following guidelines should be followed in the construction and review of test items for both parts of the written examination. These guidelines are l intended to supplement, not replace, the good practice criteria found in l NUREG BR-0122 and related documents.

I A. Operational Orientation. As discussed earlier, examination validity is enhanced to the extent that the demands of the test match the demands of the job. Therefore, in addition to being derived from important K/As and testing objectives, the context and stipulations of test items should mirror the situations encountered in the work setting. The following example illustrates effective and ineffective ways to design test items from K/As and learning objectives.

K/A: Knowledge of the design attributes of the Turbine Driver Auxiliary Feedwater Pump Differential Pressure Controller.

Task: Operate the TDAFWP controls during all modes of plant operation.

Terminal Learning Objective: The student will be able to operate the TDAFWP Differential Pressure Controller without error during a loss of feedwater event.

Enabling Objective: Upon completion of this lesson, the student will be able to explain the operation of the TDAFWP Differential Pressure Controller.

Poor Test Item: State the parameters used by the TDAFWP Differential Pressure Controller.

Better Test Item: Prior to isolating the "C" steam generator (per EPP11), it was noted that the transducer-fed auxiliary feed flow indicators for the "C" steam generator were reading greater than the flow indicators to the "A" and '.

"B" steam generators. What is the reason for this flow deviation?

4 Notice that the second test item requires the candidate to demonstrate mastery of the knowledge by applying it to an actual job situation. In developing items, it may be useful to ask oneself "why is the K/A important to satisfactory job performance?" and "in what situation will be operator need this K/A?" The answers to these questions can provide a basis / context for test items.

B. Level of Knowledge. The operational orientation required of test items on the open reference examinations, as well as the candidates' access to controlled documents, precludes the use of questions that test for mere recall or memorization. Rather than requiring candidates to simply recognize or recall facts and specifics, open reference test items should have the I

candidates demonstrate understanding by requiring them to use their knowledge to address real-life situations and problems. A test item at the

, .- \

higher level of knowledge requires candidates to determine or identify the appropriate fact, rule, or principle to a novel situation and then correctly apply it. A description of each level of knowledge, along with common verbs and example questions, is found in Table 1.

C. Realistic Context. To provide additional assurance of examination validity, the situation or problem posed in the open reference test item should be as similar as possible to the actual situations that candidates encounter or. the job. Situations described in the questions should not only be realistic, but should also be free of common "context" problems, including "backwards logic" and "window dressing."

Backwards logic questions provide candidates with information they normally have to produce, while asking them for information they normally receive. For example:

K/A: Ability to calcu. ate shutdown margins.

Backward Logic Iten: Given a shutdown margin is 5.5%, how long has the unit been shut down?

Better Iter: The unit has been shut down for x hours. Calculate the shutdown margin.

Questions with window dressing have additional, unnecessary information, typically in an attempt to make a memory level item more operationally oriented. For example:

Item with Window Dressing: The plant has tripped due to the effect of a j I

tornado crossing the site boundary. You, as Shift Supervisor, direct the

)

phor.e talker to complete the 15 minute notifications. He informs you that the nomal notification network is inoperable. What method do you direct him to ,

use for completing the 15 minute notification?

Revised Iter: If the normal notification network is inoperable, what method do you direct the phone talker to use to complete the 15 minute notification after the plant has tripped?

Another comon problem when constructing questions with realistic contexts is that quite often "real world" situations have more than one ccrrect solution or response. Check the question and references over carefully to ensure that each' test item has only one correct answer.

D. duestion Novelty. One of the most effective ways to ensure that cand.idates have higher levels of knowledge is to present them with novel l

situa'tions and recuire them to both realize what information is relevant and how to apply it. If test questions do not contain unique or varied circu.mstances compared to that which was presented in training, the item will ,

be reduced to simple recall. Review the training material to ensure that l questions do not include overly familiar conditions. Keep in mind, however,  !

that all conditions and situations should be reasonable, realistic, and safety.related.

E. Use of References. References should be considered tools that candidates use to solve problems. It should be the proper use of these tools that is tested during the open reference examination, not the recall of facts and specifics. Purely "look up" questions should not be included in the examination; rather, questions should be restricted to those that test to see if candidates can identify, locate, or select appropriate reference infomation to produce organized responses and satisfactory solutions to job related problems and issues. For example:

o l ,... .........................................................................

Pure "Look up" Item: In the event that a safety limit is violated, the reactor shall be:

a. placed in a hot shutdown coadition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

b. placed in a hot shutdown condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

c. placed in a coid shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

d. placed in a cold shutdown condition within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Better Use of

References:

While operating at 100% power, VCT and pressurizer alarms and indications show decreasing pressurizer level. Also, the blowdowr and main stean radiation monitors have alarmed. While following the appropriate Abnormal or Emergency Procedures, you as the Shift Supervisor must evaluate the existing condition.

Based on this information, the following emergency classification should be declared:

,a. Notification of Unusual Event Alert

'b.

c. Site Area Emergency

d. General Emergency F. Difficulty Level. It is not unusual for test constructors to believe, erroneously, that open reference test items should be more difficult, to compensate for the candidates' access to reference material. Frequently, this increased difficulty is in the form of requiring knowledge of more obscure or otherwise unnecessary information. Both open and closed reference examination items should have the same standard of difficulty; that is, difficulty should be based on the ,)b demands and responsibilities of operators.

G. Tire Limits. Relative to closed reference examinations, candidates take considerably longer to answer open reference test items. (Weakercandidates especially have been found to spend an appreciable amount of exam time

.~

cor,sulting references versus writing responses). It is impertant to provide candidates an ample amount of time to complete the examination, although not so much time as to allow less than competent operators the opportunity to locate answers without prior familiarization. The following guidelines should be used to determine the appropriate length of the examination:

1. Each two hour examination section should be constructed to take a competent operator an expected I hour 15 minutes to complete.

2. Wher, possible, the response tine of each question should be estimated by having a subject matter expert attua11y answer the question, including searching through references.

H. Correct Mode of Measurement. No matter how high their importance ratings or operational relevance, certain operator knowledges, skills and abilities are not amenable to written testing. For example:

Arrange the major steps in the proper sequence to start, parallel, and ioad00-2:

l Use Governer Control to increase DG-2 KW Raise DG Speed to 900 RPM Press start button on AI30B Match Voltage with Bus 1A2 Voltage Close Breaker IAD2.

............................................................s..................

Despite its operational orientation, the underlying skill addressed in the above test item would be better assessed by having the candidate simulate or step through the steps during either the simulator or walkthrough portions of the operating examination. Table 2 provides an overview of the best uses for each test mode. Make sure that the K/As and leirning objectives selected for the written examination can be effectively measured during the written testing.

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(3) Specific Guidelines for Section A, "Plant Operations" The followins guidelines are specific to the Plant Operations section of the written examination, performed on a static simulator. These guidelines are divided into two sections, Question Development and Simulator Setup.

Question Development

a. To ensure that the operators' knowledge of plant operations is adequately evaluated, Section A of the written examination should address a mix of normal, abnormal and emergency modes of operation,

b. Questions should require the operators, to the extent possible, to refer to control room indications in formulating their responses, as in the following example:

.....i........................................................................

Whi:h one of the following describes the location of the steam break?

(a) Inside containment, upstream of the steam line flow transmitters

('b ) Inside containment, downstream of the steam line flow transmitters (c) Outside containment, between "C" MSIV and "C" main steam line check valve.

(d) Outside containment, between "C" MSly and "C" main steam line containment penetration.

c. The number of scenarios used should be minimized due to the extensive amount of time necessary to set up, run and check the transients,

d. The number of malfunctions / failures for each scenario should be limited. In general, the scenario should contain one major failure (e.g.,

LOCA, SGTR, steam line breaks, ejected control rods, loss of all AC power).

In addition to the major failures, no more than four minor failures should be used (e.g., failure of a safety related pump to start, failed pressurizer  !

pressure meter indication, nuclear instrumentation failure). In many cases, one major failure and 2-3 minor failures will provide sufficient effects to test a wide range of objectives,

e. Questions may be used that do not relate to the transient but use the simulator as a frarre of reference only, provided the candidates are eware of this lack of relationship to the transient,

f. Special attention should be given to ensure that multiple questions stermiing from one event do not suffer from double jaopardy. The candidate should be able to be understand and correctly answer eac.. question based only on the information given in the question, rather than on the answer to a previous question.

Simulator Setup gl Prior to the test, the simulator recorders should be rotated to provide clean readings, and the recorders should be checked for proper operation. -

h. All indications should be checked (e.g., bulbs, meters, manual loader indications, etc) to ensure they are in proper working order, i.. When the simulator has been frozen, the chart recorder drive power ,

should be secured, if necessary.

j. Prior to administering the test, the simulator indications should be 1 verified proper based on expected question responses,

k. Any "first-out" annunciators that would normally blink to announce first-out conditions should be frozen and provided to candidates.

1. If a transient is stabilized by use of plant procedures, the step at which the simulator is frozen should be noted and this information recorded on the simulator operations sunnary sheet. Progress of the l procedure step in effect should also be given to the examinees as necessary.

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(4) Ideas for Open Book Formats.

Table 3 provides a list of sample formats to assist question developers in generating performance-based, open reference test items.

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TABLE 1 l i

LEVEL OF KNOWLEDGE DESCRIPTIONS AND EXAMPLES l

1. MEMORY The memory level involves the recall of facts and specifics, the recall of methods and processes, or the recall of a pattern, structure, or setting.

For measurement purposes, the recall situation involves little more then bringing to mind the sppropriate material. Appropriate verbs include:

To define To develop To distinguish To outline

. To recall To identify .

To recognize To list

.}

For the operator licensing examination some examples include:

State the basis for a procedural step or caution.

State the basis for a procedural change.

State the purpose of a specific procedure.

Items that require only memorization or recall are not permitted on open-reference examinations.

2. COMPREHENSION i

Comprehension represents the lowest level of true understanding. It refers to a type of understanding such that the individual knows what is

- l being communicated and can make use of the material without necessarily l relating it to other material or realizing its fullest implications. Appropriate I verbs hiclude: l 1

l To translate To estimate To prepare To differentiate To comprehend To explain  !

To interpret To sumarize To grasp To demonstrate by example To distinguish To see implication effects, and contee.uence l Questions based at this level and above are permissible to ask on an  !

open-reference examination.

3. APPLICATION These types of questions require candidates to apply the knowledge to various c'oncrete situations. The knowledge may be in the form of general ideas, rules of procedures, or generalized methods. Appropriate verbs include:.

To apply To predict To employ To use To relate To develop 1

For the operator licensing examination examples of this cognitive level would include:

Calculation of plant parameters.

Use of referen:e snaterial such as graphs, charts, curves, etc.

4. ANALYSIS l

The analysis level involves the breakdown of a comunication into its constituent l elements or parts such that the relative hierarchy of ideas is made clear i

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and/or the relations betteen the i m .. expressed are made explicit.

Appropriate verbs include:

i To discriminate To categorize .

To analyze To chvose To Cetect To discover >

To infer To select

5. SYNTHESIS Synthesis involves the putting together of elements and parts so as to fonn a whole. Appropriate verbs include:

To create To perceive To propose To organize To integrate To prepare l To plan To compile '

To design To incorporate j l To synthesize To visualize ,

6. EVAL.UMION The evaluation level involves judgment about the value and methods for given  ;

purposes. Appropriate verbs include: '

To judge To evaluate To assess To decide To compare To determine To appraise Evaluation is the optimum level of open-reference procedures questions.

Typically questiens at this level would propose a situation and require the operator to use analysis and synthesis to fonnulate judgments / decisions about appropriate actions.

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l l EXAMPLES I

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A knowledge level question, requiring the operator to respond from memory on the basis of a caution:

l A caution at the beginning of FRP-H.1 requires RCS bieed and feed to be I started at STEP 9 if ANY S/G wide range level decreases to less than 60% i

[631). Which item below is the basis for this caution? l A) Steps 1 through 8 deal only with diagnostic evaluation of the event and may be time consuming.

B) Steps 1 through 8 consist of a "loop" that is difficult to exit from.

C) Wide range level is not calibrated (therefore not accurate) for 60%[6d7].

) This level assumes S/G dryout is imminent and RCS bleed and feed must be started immediately for core cooling.

A comprehension level question, requiring the o:erator to differentiate  ;

i between types of turbine runbacks.

Indicate what type of turbine runback occurred: LOAD LIMIT, LOAD REFERENCE or BOTH.

1 I

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

W Thefollowingquestionfallsintotheapplicationlevel(i.e.,applyinga procedure).

HBR Unit #2 is at 100% power, steady state. The NP.97 calculator in the control room is 005. Based on the values given below, determine the "QUADRANT POWER TILT" as defined in Technical Specifications.

NORMAL UPPER DETECTOR CURRENTS N.41 = 230 N.42 = 235 N-43 = 232 N.44 = 236 NORMAL LOWER DETECTOR CURRENTS N-41 = 233 N-42 = 238 N-43 = 231 N-44 = 240 PRESENT INDICATED DETECTOR CURRENTS UPPER LOWER N-41 232 236 .

'N.42 238 243 h'-43 235 234 N.44 239 243 The following question is at the analysis level, it requires the operator analyze conditions and discriminate an idea' Determine the posting required for a room using the results of the following radiological survey:

1. AIRBORNE ACTIVITY: 6.34E-9uci/cc(Co-60)

2. FLOOR SHEAR: Beta. 610 dpm/cm squared; Alpha- 4dpm/cm squared

3. EQUIPMENT SMEAR: Beta.1800 dpm/cm squared: Alpha- 16 dpm/cm squared

4. GENERAL RADIATION LEVEL: 110 mr/hr

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The following question represents the synthesis / evaluation level -- putting together of elements and parts to form a whole:

Determine if plant conditions satisfy the requirements of foldout "B" S1 TERMINATION CRITERIA. Justify your answer with specific values of any required plant parameters, i

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. . o 0 I TABLE 2 OVERVIEW OF THE BEST USES FOR EACH 1EST MODE Written:

- Knowledge and abilities that are difficult to infer from behavior alone.

- Knowledge of factual inforention.

- Paper & pencil abilities and skills (e.g., calculations)

- Responses requiring information that can be supplied on paper

- Interpretation of reference, if open reference Walkthrough:

- Areas needing interpretation

- Areas needing props

- Kn ledge of locations

- 1 ;erpretation of references

- Administrative requirements Simulator:  :

- Overall ability to operate

- Integrated use of knowledge and abilities Conmunications Team Interactions

- Time-critical ,

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TABLE 3 EXAMPLE FORMATS FOR OPEN REFERENCE QUESTIONS PROVIDE THE OPERATOR WITH: REQUIRE THE OPERATOR 70:

1. Plant / System /Corponent Diagnose cause of the problem (s)

Condition (s)/ Problem (s)

2. Plant / System / Component Identify location of problem (s)

Condition (s)/ Problems (s)

3. Plant / System / Component Indicate a Condition (s)/ Problem (s) action (s)ppropriate(recuperative)

4. Plant / System / Component Indicate actions to achieve conditions specified effect

5. Plant / System / Component Identify precipatory events /

Conditions actions 6.Pl[ ant / System / Component Classify / Categorize or Conditions / otherwise indicate if conditions meet specified criteria

7. Proposed / Hypothetical Coment on Appropriauness/

course of action /recomendation Acceptability of these actions /recomendations

8. Plant conditions and operator Indicate purpose of/ reasoning actions / procedural steps behind these actions / steps

9. Requisite data Computation of parameters

10. Plant conditions and/or Predict expected plant /

operator actions system /componentresponse(s)

11. System / Component status Indicate effect on same or othersystem(s)/ component (s)

12. Plant / System / Component Indicateproperprocedure(s)/

Conditions references to turn to.

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. 1 ATTACHMENT 11 ,

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NRL CHECKLIST FOR OPEN REFERENCE TEST ITEMS  !

Item level

1. Does each test item have a documented link to important operator tasks, l K/As, and/or facility learning objectives? ,

2. Is each test item operationally oriented, i.e., is there a match between job demands and test demands?

3. Is the question at least at the "comprehension" level of knowledge? l l

4. Is the context of the questions realistic and free of window dressing cod backwards logic?

5. Does the item require an appropriate use of reference material, i.e., is it free of "look up" questions?

6. Is the item at the correct level of difficulty for the job position?

7. I,s the item appropriate for the written examination and the selected written exam format (e.g., shcrt answer; multiple choice)? I

8. I's an appropriate mix of operating modes presented in the scenarios in .'

S.ection A "Plant Operations?" I

9. Do questions in Section A take advantage of the simulator control room setting?

10. I's the item free of double jeopardy? ,

1

11. I's the item clear, precise and easy to read and understand?

12. Is there only one correct answer to the question? l

13. Does the item pose situations and problems other than those pr&sented during training?

Test Level

1. Does the facility sampling plan adequately cover the requalification topics?

2. Does the facility sampling plan ensure comprehensive, balanced coverage of the requalification program topics?

3. Can the test be completed in the time allotted?

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REQUALIFICATION  !

PILOT EXAMINATION SCENARIO GUIDE 6 - . . . . - . . .. . - ~

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T NUMBER RPE-01A

Critical Tasks or steps within a Simulator Scenario deal with CRITICAL SAFETT FUNCTIONSI those functions needed to control reactivity, remove core heat, provide for an ultimate heat sink, and contain radioactivity.

Examples includes -

a. Inability to manipulate critical controls.

b. Failure to actuate a reactor trip when required. l

c. Failure to ensure ECCS/ESF Systems inject / actuate when required.  !

d. Failure to initiate SLC when required. l

e. Failure to depressurise when required.

f. Violation of Technical Specifications

g. Failure to take action to protect the public health and safety.

1 Critical Items are identified with an asterisk (*):

s. If the critical item is not performed by the time / temp pressure /etc. the crev fails that item. .

b. If a critical task is specifically assigned to an individual, ,

and that task does not get completed, by someone in the crew, then the individual fails.

c. If a critical' task is not addressed by the SRO vith the Control Roon Command Function, then that SRO fails.

i

d. Critical Items with no designated time / parameter vill be cause I for failure if not completed by the end of the scenario.

e. The Shift Supervisor must classify the events to pass, only if he  ;

) is informed of the plant conditions. j l

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Part 1. SCENARIO GUIDE COVER SHEET l

NUMBER RPE-OlA .

SCENARIO GUIDE REFERENCES ONI-N27. Rev. 3; TCN-5; ONI-Cll-1, Rev. 3, TCN-2; ARI-Hl3-P680, Rev. 2, TCN-1; ONI-C71-1, Rev. O, TCN 'l; PEI-Bl3, Rev. I, TCN-6; PEI-D23-2, Rev. I, TCN-6; PEI-D23-3. Rev. 1, TCN-1; PEI-E12, Rev. I; PEI-G42, Rev. 1; EPI-AI, Rev. 3; PHPP Technical Specificat ions i i

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APPROVAL PREPARED BY M . 'S H ins /C. E. n DATE / d!/FM PTS REVIEW N. H. Johnson 774(d' mv -DATE #"8~88 l

OPS PEYlEW D. R. Gardner MO *~ #

D AT E, O. , 9, ,

MRC REVIEW DATE t.. .

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simulator Exam Briefing Checklist

1. The primary responsibility is to operate the facility as if it re the plant.

2. Team work and communication between operators is evaluated. It benefits the exam process to verbalise observations, analysis, and reasons for actions more than normally would be done during actual plant operations.

3. The operator recognises an incorrect decision, response, answer, analysis, action taken, or interpretation of the team which the operator is a part of but fails to correct, than the examiner may assume that that operator agrees with the incorrect items.

4. A rough los may be kept during each exercise that would be sufficient to complete necessary formal log entries which may be evaluated under administrative topics.

5. A designated facility instructor will act as the auxiliary operators, radiation health and chemistry technician, maintenance supervisors, plant management, and anyone else needed outside the control room area.

6. The facility examiner vill provide a shift turnover before the exercise begins. The shift turnover will include present plant conditions, power history, equipment out of service, abnormal conditions, surveillance due, and instructions for the shift.

7. Control board switches may be purposely misaligned to enhance a simulated scenario or transient where appropriate and is not part of the evaluation.

If misaligned, they should be tagged or otherwise highlighted as appropriate to the facility. The examiner will not misalign svitebes during ths scenario as an awareness drill.

Note: Chief examiner has the option to tell the operators that no control board switches will be misaligned on a given scenario or set of scenarios. If no switches are misaligned, the chief examiner may wish to reduce the time it takes for the operators to complete the board walk-down and accept the shift.

8. Operators will be allowed three to five minutes to familiarine themselves with the status / conditions of the control boards prior to the start of the exercise. *

(

i 9. The simulation facility part of the examination vill consist of two exercises

! l lasting approximately 50 minetes each. There vill be a short break between exercises to set up the initial conditions for the next exercise.

10. If the operators have any questions concerning the administration of the operating test, those questions should be answered prior to the start of the test. . l l .

_ , _ , . _ _ _ . _ . . _ . - _ _ _ - - - - . - - - - - - - - - - - - - - - '* ~ ~ ~-- -l

i

- NUMBER RPE-OlA LIST OF MALFUNCTIONS MALFUNCTION NO. TIMG TO 00 M ALFUNCTION TITLE

' 0498 Active CRD Pump B Trip 0601 Active HFP Trip o3 .

04 05 06 07 08 09 10 11 12 13 14 15 l

1a l 3e 3a da 1 l

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NUMBER RPE-0IA p

INTENTIONALLY BLANK --

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1 PTS SCENARIO GUIDE OBJECTIVES m ma -

- c SCENARIO NLHABER: RPE-01A 4

1 A. TERMINAL OBJECTIVE:

The operator, acting as a member of a shift operating crew, must demonstrate competence in performance of license duties required to protect the public health and safety while operating the plant !n accordance with approved instructions and procedores.

B. ENABLING OBJECTIVES: i l

1. Following a pre-shift brief, each crew member vill be able to provide a l detailed plant status report to includes i

a. Operating equipment

b. Inoperable out-of-service equipment

c. Any applicable daily instructions

d. Evolutions in progress / planned

2. Using plant installed instrumentation, plant instructions and system resonse, as well as information obtained by operating personnel outside j the Control Room, the operating crev vill correctly diagnose plant j problems.

3. The RO/ BOP vill be able to perform the immediate operator actions, from I memory, in response to the following plant transients. l a '. Feedvater Pump Trip l

b. CRD Pump Trip / Inability to move control rods

c. Recirculation Seal Failure

d. Reactor Scram

4. The Unit Supervisor vill be able to use appropriate ONI's to ensure completion of immediate actions and direct those supplemental actions as required to interface with Plant Emergency Instructions and Emergency Plan Instructions.

5. When using I0I's, SOI's, ARI's, ONI's, or PEI's the Control Room operators vill be able to ,

PTS OBJECTIVES RPE-OlA SCENARIO NUMBER:

a. Locate proper section of the instruction.

b. Follov instruction correctly.

c. Locate and observe installed instrumeatation.

d. Analyze system response,

e. Direct plant operators.

f. Inform US vhen complete.

6. While operating in accordance with Plant Emergency Instructions, the US will

a. Appoint an individual to be responsible for the control of reactor power, level, pressure, or Containment parameters.

b. Specify the plant systems to be used to cc. trol pit.nt parameters.

c. Evaluate changes in plant conditions against current actions being taken and make corrections as necessary.

d. Keep plant operators up-to-date on recovery plan.

7. When directed by the Unit Supervisor to perform actions in accordance with PEI's, the So vill:

a. Utilize tha systems designated by US.

b. Monitor system performar.ce, i.e. pressure, flov, etc.

c. Inform the US immediately when a system becomes unavailable for further use.

d. Inform U3 of plant trends in response to actions taken.

8. Given a set of plant cor.ditions, the Unit Supervisor vill be able to comply with the requiresents of Technical Specifications and Administrative Procedures.

9. The Shift Supervisor vill be able to utilize the EPI's to properly:

a. Classify events

b. Complete paperwork

c. Make timely notifications

10. The Shift Technical Advisor vill asssist the operating crew as requested in accordance with 1AP-0101 and EPI's tot

a. Verify proper identification of Off-Normal Events, proper sequence, and recommend actions to mitigate / terminate the event.

b. Verify proper classification of Emergency Events, and recommend actions to mitigate consequences of the event, and assist in completion of required paperwork.

c. Assist / clarify Technical Specifications applicable due to events.

l 1

A. NARRATIVE

SUMMARY

MPP h. Ian .

RPE-01A SCENARIO NUMBER The Unit is operating at ~ 94% power, 101-3 at step 4.3.30, sequence A, all rods out.

- MPP tagged out.

- NCCV B Pump tagged out.

- CRD Pump B tagged out.

- RPS MG Set A out of service, RPS 'A' on alternate due to EPA problems.

RFPT 'B' trips causing entry into ONI-N27. During recovery, CRDB Pump 'A' trips causing an inability to move control rods and entry into OHI-C11-1.

The loss of CRD to RR Pump seals causes a slow RR Pump seal failure. The reactor is scrammed at 20 minutes since CRD accumulators fail causing entry into ONI-C71-1. The RR pump seal fails shortly after the scram causing a LOCA and entry into various PEI's and EPI's.

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~7-I

i NUMBER CPE-ola I

B. INSTRUCTOR PAGE., ~

l INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE I. Initialize the Simulator to 10-36.

- Insert the following malfunctions:

-- 0498 CRD Pump B Trip ~N

-- 0601 MFP Trip

- Place a red cap on CRD Pump 'B' and the NFP.

- Place the Simulator in RUN, ensure that all annunicators acknowledged and the plant is stable. 1

- Allow the operators to enter the room, provide them with a turnover and allow them to walk- l down panels.

Note PPO inadver- II. RFPT Trip tantly tripped pump during OJT a. Insert malfunction 0600, RFPT 'B' dtmonstration. trip.

b. Reactor Recirculation Response.

c. Event Recognition.

d. ONI-N27, Immediate Actions

e. ONI-N27, Supplemental Actions: ,

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

NUMBER RPE-OlA l STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES i

I. Operators familiarine themselves with l the current plant conditions. l I

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1 II. RFPr Trip

a. RO/ BOP, using alarms and indications 259001-A3.10 determine that RFPT *B' has tripped. 3.4/3.4 259001 - GEN 8 3.5/3.4

b. R0/ BOP, using alarms and indications, 202002-A3.01 determine that the Reactor Recire 3.6/3.4 Flow Control valves run back.

c. Unit Supervisor informed that: 259001-GEN 1 3.8/4.0

- RFFT 'B' tripped.

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d. Unit Supervisor should enter ONI-N27 259001-GEN 15 based on the RFFT trip and directs / 3.6/3.8 verifies the following:

- Steam flow and feed flow determined 259001-A2.01 to be equal and water level stable 3.7/3.7 in normal band,

e. Unit Supervisor may direct recovery 259001-GEN 1 acti,ons per ONI-N27 as follows: 3.8/4.0

a.

i hjljh4BEli RPE-OlA INSTRUCTOR PAGE J-

- >m INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE NOTE: Resetting RR System runback not a priority until power increase required.

NOTE: Feed pump restart may be accomplished but the scenario is nnt dependent on restoration of the RFPT. The crev should continue restor-ation actions until other actions take priority.

III. Loss of CRD sie Step III.d a. Using NTI, insert malfuentions 1280, and 0497,

)21ov. There annunciator for CRD oil pressure lov and trip should be a 2 minute of CRD Pump 'A'.

time delay between

he pump trip in step NOTE: This simulates an oil line rupture.

II.a and the start if accumulator b. Event recognition.

! cults in Step

II.d. l

c. ONI-C11-1 Immediate Actions l

l 'OTE: Once the d. ONI-C11-1 Supplemental Actions scond accumulator

ult is active, - Using NTI, insert the following malfunctions

o to step IV. two (2) minutes apart.

450 Accumulator fault 452 Accumulator fault 454 Accumulator fault 451 Accumulator fault 453 Accumulator fault

• NOTE: The critical item of these steps are to ensure that 20 minutes from second Accumulator Fault, the Tech. Spec. actions are taken (Mode Svitch to Shutdown).

10

NUMBER RPE-Ol^

STUDENT PAGE ,

STUDENT DIRECTION INSTRUCTOR NOTES

- Reset of RR System flow control valve 202002-A2.07 runback. 3.3/3.3 i

- Restart RFPT per ONI-N27, Section 4.1 or 259001-GEN 13  ;

S01-N27 as appropriate. 3.6/3.7 l

III. Loss of CRD

a. RO/ BOP respond to the annunciator 295022-GEN 5 l and dispatch an operator to invest- 3.3/3.4 tigate and respond to pump trip. 295022-AA2.02 3.3/3.4 j

b. Unit Supervisor informed of CRD Pump 295022-GEN 11 j trip - no CRD operating. 3.9/4.0 l i

l i c. The Unit Supervisor should enter ONI- 295022-GEN 12 l C11-1 and direct / verify the following: 3.3/3.9 I

- Maintain plant parameters steady. 295022-GEN 10 3.7/3.5

- Monitor accumulators. 295022-AA2.01 3.5/3.6

d. ONI-C11-1 Supplemental Actions 201001-GEN 14 R0/ BOP acknowledges / resets accumulator 3.7/3.4 resets accumulator faults and notifies the Unit Supervisor of each subsequent fault received.

• Unit Supervisor orders placing the Mode 201001-GEN 11 Sviteh in Shutdovn within 20 ainutes of 3.4/4.2

rece'ipt of the second Accumulator Fault if CRD not restored.

11

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1 NUMBER RPE-OlA )

INSTRUCTOR PAGE  :-

- >m INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE Alarm at 160 F. IV. RR Pump Seal Failure Operatgrsmusttrip at 180 F. a. Insert malfunction 1445 Recirc A/B Point 9 and 21 on Temperature High - indicating that both l

H13-P614 Recorder. seal cavities read 165' F and  ;

increasing.

3 - 50 for inner b. Insert malfunction 0399 and using pushbutton isal.

42 increase until 10 then insert staging i flov alarm, malfunction 1407.

50 - 100 for outer usal. V. Reactor Scram, ist Step VI.c for

• NOTE: The reactor scram may be initiated with instructor actions RPS Manual Scram Pushbuttons, the critical item is t lf crev isolates that the Mode Svitch be in Shutdown to meet Tech (R loop. Spec Action Statement.

a. .ONI-C71-1, Immediate Actions l

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natructor cue for VI. Loss of Coolant Accident his step is scram rcnsient complete.

12

NUMBER 'tPE-O

. lA STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES l

IV. RR Pump Seal Failure

a. RO/ECP, utilizing alarms and indications, 201001-GEN 12 ,

determines the cause for the high temp- 3.6/3.3 l erature and actions to be taken per ARI-680-4-D8.

b. RO/ BOP using ARI and indications determines 202001-A2.10 that RR Pump 'A' inner seal is degrading. 3.5/3.9 V. Reactor scram initiated by the RO, when directed 295022-GEN 11 by the Unit Supervisor based on meeting the 3.9/4.0 Techniel Specification Action Statement.

• - RO places the Mode Switch in Shutdown. 212000-A4.01 4.6/4.6

s. ONI-C71-1 entered by the Unit Supervisor who directs / verifies the following actions:

- Mode Switch to Shutdown. 212000-A4.01 4.6/4.6

- Verify power decreasing. 295006-AA2.01 4.5/4.6

- Verify pressure in conttol. 295006-AA2.04 4.1/4.1

- Verify water level under control. 295006-AA2.03 4.0/4.2

- Trips Main Turbine when psver < 4%. 295006-AA2.05 4.6/4.6 295006-AK3.05 3.8/4.0 VI. Loss of Coolant Accident.

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NUMBER RPE-OlA INSTRUCTOR PAGE a-w nn l

INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE- l

a. When the initial scram transient is complete, the Immediate Actions of ONI-C71-1 are complete and the plant is stable, using pushbutton 42, increase RR Pump seal failure to 100%.

NOTE: An additional step may be required to achieve the desired LOCA. If required, insert malfunction 0704, Variable Rate LOCA, and increase "one quick click."

I I

NOTE: Drain cooler b. Recognition TTo~v greater than 5 gpa.

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c. If crev diagnoses LOCA as RR Pump seal failure it may be necessary to give another "quick click" to ensure DV pressure continues to increase.

Steps VII through XI may be per-formed concurrently, since these are all VII. PEI-D23-2 parallel paths the crev should be taking:

• a. Page FV, lines 12, 13 PEI-D23-2 bypass switches for PEI's.

PEI-D23-3 PEI-B13 PEI-E12 b. 14, 15, and 16 PEI-G42

• bypass svitches for PLI's.

c. N/A VIII. PEI-D23-3

• a. Page FV for PEI bypass switch remote functions bypasses switches for PEI's.

NUMBER RPE-OlA STUDENT PAGE STUDENT DIRECTION . INSTRUCTOR NOTES I

a. R0/80F, using alarms and indications, 295024-EA2.01 determine that RR pump 'A' outer seal has 4.2/4.4 failed and that a LOCA has occurred.

295010-AA2.02 3.8/3.9 295010-AA2.05 3.3/3.3 295010-AA2.06 3.6/3.6

b. Unit Supervisor informed of increasing 295024-GEN 11 Dryvell pressure causing the following: 4.3/4.5

- ECCS initiation 295010-GEN 11

- Containment Isolation 4.2/4.5

c. No action, but if crev decides leak is from RR seal, they ray isolate the loop by j closing the suction and discharge valve after tripping the pump.

VII. Unit Supervisor enters PEI-D23-2 based on 295024-GEN 12 I high Dryvell pressure and directs / verified 3.9/4.5 l the following:

• a. Restore NCCV/ Instrument Air to the 223001-A2.01 Containment /Dryvell for Drivell 4.3/4.A Cooling.

• b. R'e store Containment Cooling. 223001-A2.01 ,

4.3/4.4 l l

c. Monitor Dryvell/ Containment pressures 29502-EA2.01 and maintain within specifications. 4.2/4.5 295024-EA2.09 4.0/4.1 VIII. Unit Supervisor enters PEI-D23-3 based on 295028-GEN 11 high Dryvell Temperature and directs 4.2/4.4 the following:

'

• a. Restore NCCV/ Instrument Air to' Containment / 295028-EA1.03 Dryvell for Dryt 11 Cooling. 3.9/3.9

,,___,,,,-,,--,,n. , , , . , _ , , , , . , _ _ _ , _ , _ , , , , , , , _ _ _ , _ , _ , _ , _ , _ , , , , , , _ , , _ _ , _ , _ _ _ , , _ , , , _ _ , , _ _ _

w- - , _ -m. - - . , , . _ _ , - _ ,,

F NUMBER RPE-OlA

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INSTRUCTOR PAGE  :-

rue nn INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE IX. PEI-B13 NOTE: This instruction may be entered as a result of a FAST RX SHlTTDOVN initiated as a result of increasing Dryvell pressure.

NOTE: This instruction entry may be subtle or even non-apparent due to no immediate concern for power, pressure, or level and priority being given to DV and CNTHNI parameters.

a. Section 3.0 NOTE: Mode switch may be in shutdovn due to a FAST RX SBLITDOVN.

NOTE: Hydrogen Analyzers not Simulated.

b. Section 3.1 NOTE: This step may be subtle or non-apparent due to the successful scram.

c. Section 3.2 NOTE: This step may be subtle or even non-apparent due to pressure under control on bypass valves.

d. Section 3.3 NOTE: This step may be subtle or even non-apparent due to level under automatic control of feedvater system.

16

1 NUMBER RPE-OlA j l

STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES

b. 295028-EA2.01 Monitor maintainDryvell Dryvell temperature Temperature trend,*

< 330 F. 4.0/4.1 295028-GEN 3 3.1/4.2 IX. Unit Supervisor enters PEI-B13 based on high 295024-GEN 11 Dryvell pressure and directs / verifies the 4.2/4.3 following actions. I l

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a. Section 3.0

- Mode switch to shutdown. 212000-A4.01 4.6/4.6

- Hydrogen Analyzers started. 223001-A1.05 3.1/3.1

b. Section 3.1

- Power verified to be < 4% 215005-A1.01 and IVE step used to test exit 4.0/4.0 from section, l

c. Section 3.2

- Pressure verified to be less than 241000-A3.08 1033 and being controlled. 3.8/3.8 d .' Section 3.3

- Level verified 185" - 215" 259002-A3.05 and being maintained.

3.4/3.4 3

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NUMBER RPE-01A . )

l INSTRUCTOR PAGE '

Ad9 787i INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE X. PEI-G42 I NOTE: HPCS and RCIC Systems shift suction i source to the Suppression Pool on high  ;

Suppression Pool level. RCIC may be placed

, back on the CST for up to one hour.

NOTE: This PEI may be entered nov or later due to priority being given to PEI-D23-2/3 for control of Dryvell and Containment parameters.

XI.

/./ PEI-B12 u

g~ ~h

\

j Wsh

• NOTE: Entry into this instruction may be

% (N, subtle, but Suppression Pool Cooling should be directed when Suppression Pool temperature w reaches 90 P., and Suppression Pool temperature

= , , ,

.,.,.,,,= = = = = - I l' must not exceed the Heat Capacity Temperature Limit

" (HCTQ.

-. O*"""x- =,

XII. Eme.rgency Plan Actions 1

• - NOTE: Declaration of the event may be I recommended by any crev member.  ;

Classification in a conservative direction is not cause for failure of this step.

i 1

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18

NUMBER RPE-0IA I STUDENT PAGE l m

STUDENT DIRECTION INSTRUCTOR NOTES X. PEI-G42

- The Unit Supervisor should enter this 295029-GEN 11 instruction when Suppression Pool level 4.2/4.5 reaches 18.5 feet and direct / verify the following steps:

- Lover Suppression Pool level using any 295029-EK3.02 of the systems listed in the PEI (G42 3.6/4.0 is primary).

XI. PEI-E12enteredwhenSgppressionPool 295026-GEN 11 temperature exceeds 90 P. Actions directed / 4.4/4.6 verified by the Unit Supervisor. 295026-GEN 12 3.8/4.5 laer a loop of RHR into the Suppression 295026-EA1.01 19o1 Cooling mode of operation when temp- 4.1/4.1 erature exceeds 90' P.

• Suppression Pool temperature maintained 295026-GEN 3 les than the UCIL. 3.2/4.3 XII. Emergency Plan Actions l 1

• - The Shift Supervisor vill declare an 295024 GEN 2 UNUSUAL EVE:fr or ALERT per EPI-A1. 3.1/4.4 )

J 295031 GEN 2 3.1/4.6

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. - - . 1 NUMBER RPE-OlA I INSTRUCTOR PAGE  :.  !

m nn INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE  !

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t l

XIII. END OF SCENARIO

a. When the reactor is shutdown with  !

vater level under control and pressure  !

being maintained or intentionally lowered, aj vith the Dryvell/ Containment parameters {

1 improving or under control, and the Shift i Supervisor has addressed the E-PLAN actions, perform the following:

- Place the Simulator in FREEZE.

- Conduct end of session critique to include  !

the following items: l

-- Standard critique items.

-- PEI-E12/G42/B13 entries and priorities related to a LOCA.

-- Twenty minute clock requirements for loss of CRD.

-- RR Pump limitations per ARI's. 4 I

-- RFPT fast restatt instruction. I i

l l

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20

NUMBER RPE-01A i

STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES

- The Shift Supervisor should ensure that 294001-A1.16 paperwork completed per EPI-B1/A2/A3. 2.9/4.7

- The Shitt Supervisor should ensure that 294001-A1.16 initial notifications meet the 15 minute 2.9/4.7 recommended time frame.

XIII. END OR SCENARIO .

A. Operators participate in the end of session critique.

9 21

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

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REQUALIFICATION PILOT EXAMINATION

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SCENARIO GUIDE h .- . - - -= -- - . .. -.- -

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1 Critical Tasks or steps within a Simulator Scenario deal with CRITICAL l SAFETY FUNCTIONS: those functions needed to control reactivity, remove core heat, provide for an ultimate heat sink, and contain radioactivity.

Examples includes

a. Inability to manipulate critical controls.

b. Failure to actuate a reactor trip when required.

j c. Failure to ensure ECCS/ ESP Systems inject / actuate when required.

d. Failure to initlite SLC when required.

e. Failure to depressurize when required.

f. Violation of Technical Specifications

g. Failure to take action to protect the public health and safety.

Critica) Items are identified with an asterisk (*):

a. If the critical item is not performed by the time / temp pressure /etc. the crev fails that item.

b. If a critical task is specifically assigned to an individual, and that task does not get completed, by someone in the crew, then the individual fails.

1

c. If a critical task is not addressed by the SRO with the control Room Command Function, then that SRO fails.

d. Critical Items with no designated time / parameter vill be cause for failure if not completed by the end of the scenario. l

e. The Shf*t Supervisor must classify the events to p.es, only if he is informed of the plant conditions.

e 1

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Part I. SCENARIO GUIDE COVER SHEET NUMBER _ RPE-OlB .

SCENARIO GUIDE REFERENCES ONI-B21-1. Rev. 2. TCN-3: ONI-C71-1. Rev. O. TCN-1: PEI-E12. Rev. I:

PEI-C42, Rev. 1; PEI-Bl3, Rev. I, TCN-6; PNPP Technical Specifications; I EPI-Al. Rev. 3 EPI-A2. Rev. 4; EPI-A3. Rev. 3. TCN-4; EPI-Bl. J. 5.

TCN-5

)

l APPROVAL PREPARED BY Anrk $4 M.S.Haskins/C.E.fersson DATE / f /9 M PTS REVIEW N. H. Johnson Nh 'T DATE OPS REygw D. R. Gardner h(A ^ M D AT E ' E E .

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Simulator Exas Briefing Checklist

1. The primary responsibility is to operate the facility as if it were the plant.

2. Team work and communication between operators is evaluated. It benefits the exam process to verbalize observations, analysis, and reasons for actions more than normally would be done during actual plant operations.

3. The operator recognizes an incorrect decision, response, answer, analysis, action taken, or interpretation of the team which the operator.is a part of but fails to correct, than the examiner may assume that that operntor agrees with the incorrect items.

4. A rough log may be kept during each exercise that vould be sufficient to complete necessary formal log entries which may be evaluated under administrative topics.

5. A designated facility instructor vill act as the auxiliary operators, radiation health and chemistry technician, maintenance supervisurs, plant management, and anyone else needed outside the control room area.

6. The facility examiner vill provide a shift turnover before the exercise begins. The shift turnover will include present plant conditions, power I history, equipment out of service, abnormal conditions, surve111snee due, and instructions for the shift.

? Control board switches may be purposely misaligned to enhance a simulated scenario or transient wher, appropriate and is not part of the evaluation.

l If misaligned, they should be tagged or otherwise highlighted as appropriate l to the facility. The examiner vill not misalign switches during the scenario as an awareness drill.

Note Chief examiner has the option to tell the operators that no control board switches vill be misaligned on a given scenario or set of scenarios. If no switches are misaligned, the chief examiner may wish to reduce the time it takes for the operators to complete the board valk-down and accept the shift.

l

8. Operators will be allowed threo to five minutes to familiarise themselves l vith the status / conditions of the control boards prior to the start of the l exercise. )

9. The simulation facility part of the examination vill consist of two exercises lasting approximately 50 minutes each. There vill be a short break between exercises to set up the initial conditions for the next exercise.

10. If the operators have any questions concerning the administration of the operating test, those quertions should be answered prior to the start of the tast.

9 a

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I I

NUMBER RPE-OlB LIST OF MALFUNCTIONS

. 1 l

l MALFUNCTION NO. TIME TO 00 MALFUNCTION TITLE l

\

0498 0 CRDH Pump B Trip 0707 0 Tail to SCRAM

~

'8 0856 0 Failure of ARI Capability 1128 0 Annunciator os 06 07 os 09 10 11 12 ,

l 13 14 15 la 2a 3a 4e ,

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PTS SCENARIO GUIDE OBJECTIVES PWP leo. 7Ma l

l SCENARIO NUMBER. RPE-01B l

A. TERMINAL OBJECTIVE:

1 The operator, acting as a member of a shift operating crew, must I demonstrate competence in performance of license duties required to protect I the public health and safety while operating the plant in accordance with l approved instructions and procedures.

I l

B. ENABLING OBJECTIVES:

1. Following a preshift brief, each crev member vill be able to provide a detailed plant status report to includes

a. Operating equipment.

b. Inoperable out-of-service equipment.

c. Any applicable daily instructions.

d. gvolutions in progress / planned.  ;

2. Using plant installed instrumentation, plant instructions, and system response, as well as information obtained by operating personnel outside the Control Room, the operating crev vill correctly diagnose plant problems.

3. The R0/ BOP will be able to perform the immediate operator actions, from j memory, in response to the following plant transients.  ;

i a. Inadvertent / Stuck Open SRV.

b. Reactor Scram / Failure to Scram.  ;

4. The Unit Supervisor vill be able to use appropriate ONI's to ensure completion of immediate actions and direct those supplemental actions as required to interface with Plant Emergency Instructions and Emergency Plan Instructions.

5 .' When using 10I's, SOI's, ARI's, ONI's, or PEI's, the Control Room, opetators vill be able to l

--...--..-.-_-_-----..-_.-.-......--...._i

PTS OBJECTIVES ,

RPE-01B SCENARIO NUMBER:

a. Locate the proper section of the instruction.

b. Pollow instruction correctly.

c. Locate and observe installed instrumentation.

d. Analyze system response.

e. Direct plant operators.

f. Inform Unit Supervisor when complete. ,

6. While operating in accordance with Plant Emergency Instructions, the Unit Supervisor vill:

a. Appoint an individual to be responsible for the control of reactor power, level, pressure or Containment parameters.

b. Specify the plant systems to be used to control plant parameters.

c. Evaluate changes in plant conditions against current actions being taken and make corrections as neces:ary.

d. Keep plant operators up-to-date on recovery plan.

7. When directed by the Unit Supervisor to perform actions in accordance with PEI's, the So vill:

a. Utilize the systems designated by Unit Supervisor,

b. Monitor system performance, i.e. pressure, flow, etc.

c. Inform the Unit Supervisor when a system becomes unavailable for further use,

d. Inform Unit Supervisor of plant trends in response to actions taken.

8. Given a set of plant conditions, the Unit Supervisor vill be able to comply with the requirements of Technical Specifications and Administrative Procedures.

9. The Shift Supervisor vill be able to utilize the EPI's to properly:

a. Classify events,

b. Complete paperwork.

c. Make timely notifications.

10. The Shift Technical Advisor vill assist the operating crew as requested in accordance with the TAP-0101 and EPI's.

a. Verify proper identification of Off-Normal Events, proper sequence and recommend actions to mitigate / terminate the event. (

b. Verify proper e:lassification of emergency events, r commend actions to mitigate consequences of the event, and assist in completion of required paperwork.

c. Assist / clarify Technical SpeMfications applicable due to events.

~ _ _ _ . . . _ . _ . . _ . _ . . _ _ _ _ . . . _

A. NARRATIVE SUMM ARY PfP M73 1 1 l

SCENARIO NUMBER RPE-01B Unit is operating at ~ 94% power, I0I-3 at Step 4.3.30, sequence A, all rods l out.

- NCCV 'B' Pump tagged out

- CRD 'B' Pump tagged out

- RHR 'B' loop not filled and vented vill bo in one hour A SRV pops open and sticks open causing entry into ONI-B21-1. After the actions are taken, the SRV la still open. PEI-E12 entered at 90' F.

Suppression Pool Temperature increasing. A Fast Reactor Shutdown must be performed prior to reaching 110' F. Suppression Pool temperature. A failure )

to scrau and a failure of ARI causes entry into PEI-B13. As soon as SLC is  ;

initiated, the SRV closes. Scenario ends in PEI B13 with reactor shutdown j in progress using SLC and rods.

l I

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1 l

l l

NUMBER RPE-OlB l

B. INSTRUCTOR PAGE . ...

l l

INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE l l

l I. Initialize the Simulator to IC-36.

- Insert the following malfunctions:

-- 0707 Failure to Scram

-- 0856 Failure of ARI

-- 1128 RHR Pump B Disch Press Hi/Lov

-- 0498 CRDH Pump B Trip

- Remove the RED solenoid light bulb from B21-F051C and replace it with a burned out bulb.

- Place RED tag on CRDH Pump 'B'. I

- Place the Simulator in RUN, and ensure annunciators cleared, and plant stable.

- Allow operators to enter, provide a turnover, and allov them to familiarize themselves with the j current conditions.

II. SRV Opens / Sticks NOTE: H13-P614 A. Insert the following malfunction to temperature for simulate SRV opening and sticking open:

F051C reads 310' F.

l

-- 0535 SRV F051C Falls Open B. Event Recognition l

l C. ONI-B21-1, Immsdiate Actions NOTE: The R0 and/or the BOP should perform

the immediate actions from memory with the l concurrence of the Unit Supervisor. The Unit l Supervisor should verify / direct these actions l l as regulged to ensure that they are performed. j l

l

NUMBER RPE-OlB i

STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES l

I. Operators familiarize themselves with * '

the current plant conditions.

l II. SRV Opens / Sticks A. R0/ BOP Actions

- Observes the following alarms: 239002-A4.01 4.4/4.4

-- H13-P601

-- SRV Open

- H13-P614 SRV Leakage

-- Determines SRV is open B. Unit Supervisor informed that SRV is 239002-GEN 1 OPEN inadvertently. 3.8/4.0 C. Unit Supervisor shculd direct and/or 239002-GEN 15 verify the following Immediate Actions per 4.2/4.3 ONI-B21-1. 239002-GEN 14 4.1/3.9

- Sound (simulate) plant Emergency Alarm. 294001-K1.05

_ 3.2/3.7 9

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l . ..

FJLJhABEFI RPE-OlB l

INSTRUCTOR PAGE

- i m nn INSTRUC TOR NOTES SIMULATOR SCENARIO GUIDANCE  :

I INSTRl80 TOR: DO NOT PULL FUSES (Remote function) j but after 2-3 minutes, inform S0 that fuses are removed if requested to do so.

D. ONI-B21-1, Supplemental Actions.

I NOTE: Tech Specs may be referred to nov, ,

or later if E-Plan takes precedence. l NOTE: The R0/B0P should be instructed to monitor temperature and/or level. If no action taken nov, action must be taken during STEP III.

E. Emergency Plan Actions

• NOTE: Declaration of the event may be recommended by any crev member by referring to ONI-B21-1. Classifications of a Conservative nature Do Not constitute a failure.

10

NUMBER RPE-Ois r

STUDENT PAGE STUDENT DIRECT.lON , INSTRUCTOR NOTES l

- Evacuates the containment. 294001-K1.05 3.2/3.7

• - Cycles the SRV control switch. 239002-A2.03 4.1/4.2 (SRV switch must end up in the OFF position.)

- Mcy remove solenoid fuses (lack of RED 239002-K2.01 solenoid light may make this item N/A). 2.8/3.2 1 1

D. Unit Supervisor should direct these actions 239002-A2.03 and/or ensure someone is assigned to monitor 4.1/4.2 critical parameters.

-- Unit Supervisor should refer to Technical 295026-GEN 8 Specifications. 3.6/4.5

-- RO/ BOP should monitor the Suppression Pool 239002-A4.04 temperature and the Soppression Pool level. 4.3/4.3

-- thit Supervisor notified of Suppression Pool 295026-GEN 3 temperature by 90' F. average temperature. 3.2/4.3 295026-EA2.01 4.1/4.2

-- Unit Supervisor should enter PEI-E12 when 295026-GEN 11 Suppression Pool temperature reaches 90' F. 4.4/4.6 average (STEP III).

-- Unit Supervisor notified of Suppression Pool 295029-EA2.01 level > 18.5 feed. 3.9/3.9 295029-GEN 3 3.1/4.1

-- Unit Supervisor should enter PEI-G42 when 295029-GEN 11 Suppression Pool level reaches 18.5 feet. 4.2/4.5 (STEP VII) l l

E. Emergency Plan Actions l

• -- The Shitt Supervisor vill classify the event 239002-GEN 3 as an UNUSUAL EVENT per EPI-A1. 3.2/4.5

- the Shift Supervisor should ensure paperwork 294001-A1.02 complete per EPI-B1/A2. 4.2/4.2 Il  !

! _ _ . _ ,._ ._a_.__.__..___..__....____ - _ . . . - _ _ - - _ . . _ _ _ _ _ _ _ __

NUMBER RPE-OlB INSTRUCTOR PAGE -

94+ hn INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE JII. PEI-E12 Actions i I

I

• NOTE: This may only be verified at this I time due to being done when SRV opened f.ni t ially. The Suppression Pool should not exceed 110' F. with the mode switch in RUN.

I l

NOTE: Fast Reactor Shutdovn consists of reducing I recire flov to minimum or until APRH upscales in, then ARHING and DEPRESSING the RPS Hanual Scram Pushbuttons, and perform ONI-C71-1 concurrently with PEI-B12.

IV. Technical Specification Requirement TSI 3.6.3.1 requirement NOTE: The critical item is to ensure that the plant can be shutdown with control rods prior to teading BIIT limit per EPG's. Some flexi-bility alloved in 110' F. limit. Also, Suppression Pool Cooling should be done already-but is a Technical Specification requirement at

> 110' F. only.

\

12

NUMBER RPE-OlB STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES

-- The Shift Supervisor should ensure initial 294001-A1.16 notifications meet the 15 minute recommended 2.9/4.7 time.

III. PEI-E12 entered when Suppression Pool Temperature exceeds 90' F. Actions direct / verified by the Unit Supervisor.

• - Loop 'A' of RHR should be directed to be placed 295026-GEN 12 in Suppression Pool Cooling before average 3.8/4.5 temperature exceeds 110' F.

• - R0/ BOP places Loop 'A' in Suppression Pool 295026-EA1.01 Cooling mode. 4.1/4.1

- Unit Supervisor notified of Suppression Pool 295026-GEN 11 average temperature of 110' F. 4.4/4.6

- The Unit Supervisor should direct a Fast 295026-GEN 12 Reactor Shutdown be performed pr*.or to 3.8/4.5 reaching 110' F.

1

- The RO should perform a Fast Reactor Shutdown 202002-A4.08 directed by the Unit Supervisor.

3.3/3.3 IV. Technical Specification Requirement

• - The Unit Supervisor vill direct the Reactor Mode 295026-GEN 8 Svitch to be placed in SHIFrDOVN vhen Suppression 3.6/4.5 Pool average tenperature exceeds 110' F. (i.e.

111' F.)

- The Unit Supervisor should ensure Suppression 295026-GEN 8 Pool Cooling established. 3.6/4.5 13

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

l NUMBER RPE-OlB l

INSTRUCTOR PAGE  :-

- ,m INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE -

V. Failure to Scram

• - NOTE: Critical item is that the Unit Supervisor is informed that the Unit Failed to Scram by someone, even if he notices it himself.

- NOTE: RO may suggest the ections to be taken on the failure to scram up to tripping the Reactor Recirc Pumps.

VI. PEI-B13 Actions A. Section 3 g0

• NOTE: Mode Switch should already be in shutdown may not be called out here.

NOTE: liydrogen analyzers not simulated.

B. Section 3.1 l

• - Pushbuttons on H13-P680.

l l

l

- Jith power > 6%, BIIT is 110' P. Since this l vas an entry level to the PEI to begin with, the 110' F. may be exceeded prior to starting ( i SLC.

14

NUMBER RPE-OlB l

STUDENT PAGE STUDENT DIRECTION INSTRUCTOR NOTES V. Failure to Scram

• - The RO notices the failure to scram when RPS 212000-A3.all Manual Scram pushbuttons depressed. 4.4/4.4 i

- RO/ BOP notifies the Unit Supervisor.

- RO places the Reactor Mode Switch in SHUTDOVN. 212000-A4.01 4.6/4.6 i I

- RO does NOT trip the Main Turbine. 295037-EK3.06 l 3.8/4.1

- Unit Supervisor should enter PEI-B13 on 295037-GEN 11 fail to Scram and power > 4%. 4.4/4.7 VI. PEI-B13 Actions should be directed / verified 295037-GEN 12 by the Unit Supervisor. 3.9/4.6 A. Section 3.0

• - Mode switch to Shutdown. 212000-A4.01 4.6/4.6

- Hydrogen Analyzers started. 223001-A1.05 3.1/3.3 B. Section 3.1

• - ARI initiated. 212000-A4.16 4.4/4.4

- Reactor Recirc Pump tripped (may require 202001-A4.01 PCV runback to minimum prior to or after 3.7/3.7 tripping pumps).

- Monitors Suppression Pool average temper- 295026-EK3.04 ature and reactor power to determine BIIT. 3.7/4.1 295037-EA2.04 4.0/4.1 295037-EA2.01 4.2/4.3 295037-EA2.05 4.2/4.3 1

15 l

NUMBER RPE-OlB INSTRUCTOR PAGE  :-

nernn INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE .

l

)

NOTE: DELETE item

• NOTE: The critical item is to monitor for BIIT 0535 as soon as SLC and SLC directed to be initiated when it is noticed la inTtiatedt-- that BIIT is exceeded. BITT for > 6x power is 111' F. Since PNPP key control does not have SLC keys inserted, evaluator discretion is required for time to start SLC.

NOTE: Any rod sequence may be used and any method of insertion can be used.

C. Section 3.2 NOTE: This step may be subtle or even non-apparent due to pressure under control on Bypass valves.

D. Section 3.3 NOTE: This step may be subtle or even non- l appe. rent due to level under control on feed-water system.

l VII. PEI-G42 Actions

- NOTES: HPCS System and RCIC System suction sources shift on high Suppression Pool level.

- RCIC Suction may be placed back on CST for up to one hour. .

- The scenario may be slov enough to allov entry into the PEI for a non-emergency priority. PEI-B13 is priority 1 until the reactor is in cold shutdovn.

16

1 l NUMBER RPE-OlB l

STUDENT PAGE l l

STUDENT DIRECTION INSTRUCTOR NOTES i

l

• - Unit Supervisor orders SLC initiated 295037-GEN 12 when BIIT exceeded (111' P.) i l

• - RO/ BOP initiates Standby Liquid Control 295037-EA1.04 trains A and B. 4.5/4.5

- Unit directs the Lov Power Setpoint by- 295037-GEN 12 passed, to continue to insert control 3.9/4.6 1 rods. )

1

- R0/B0P continues to insert control rods 295037-EK3.07 rapidly with either of the following: 4.2/4.3

-- In-timer skip pushbutton.

-- Normal insert pushbutton.

C. Section 3.2 l 1

- Pressure verified under 1033 and being 295037-EA2.06 l controlled. 4.0/4.1 D. Section 3.3

- Level verified 185" - 215" and being 295037-EA2.02 mainteined. 4.1/4.2 VII. PEI-G42 Actions 295029-GEN 11 4.2/4.5

- Suppression Pool level > 18.5' causes entry 295029-GEN 11 I by Unit Supervisor. 4.2/4.5 l

. Suppression Pool level may be lowered 295029-EK3.02 using any of the specified systems (G42 3.6/4.0 is primary).

17

P NUMBER RPE-OlB INSTRUCTOR PAGE  :-

rws nn i

INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE i

l V::II. Emergency Plan Actions

• - NOTE: Critical item is to upgrade to an ALERT 1 eventually, but until plant shutdown, the crev )

should concentrate on PEI-B13 actions as Priority 1.

Evaluator (s) discretion must be used to )

determine if this task should be evaluated during the scenario.

i

- Follow up after Scenario should be required due to time limitations.

XI. END OF SCENARIO  ;

h. When efforts are in progress to shutdown the plant with SLC and/or control rods, power i

< 4%, and the Shift Supervisor is addressing '

the ALERT actions, perform the following:

- Place the simulator in FREEZE.

- Conduct End of Session critique to include the following items:

-- Standard critique items.

-- PEI-G42 entry / priority and general actions.

-- Technical Specifications for HPCS/RCIC and relation with SRV inoperable.

-- Difference in actions if SRV stayed open vice closing.

18

l NUMBER RPE-OlB STUDENT PAGE l STUDENT DIRECTION INSTRUCTOR NOTES VIII. Emergency Plan Actions

• A. Shilt Supervisor upgrades the Emergency 295037-GEN 11 classification to an ALERT based on: 4.4/4.7

-- Failure to Scram 294001-A1.16 ,

SLC Initiated 2.9/4.7 1

- Actions same as described in Step j II.E.

XI. END OF SCENARIO A. Operators participate in End of Sesslor.

Critique.

l 1

4 1

3 0 19

NUMBER RPE-OlB l

INSTRUCTOR PAGE -

N9 7872 INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE

-- INTENTIONALLY BLANK --

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PILOT EXAMINATION

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Critical Tasks or steps within a Simulator Scenario deal with' CRITICAL SAFETY FUNCTIONS those functions needed to control reactivity, remove core i heat, provide for an ultimate heat sink, and contain radioactivity.

l Examples include:

a. Inability to manipulate critical controls.

b. Failure to actuate a reactor trip when required.

c. Failure to ensure ECCS/ESF Systems inject / actuate when required.

d. Failure to initiate SLC when required.

e. Failure to depressurize when required.  ;

f. Violation of Technical Specifications )

g. Failure to take action to protect the public health and safety. j l

critical Items are identified with an asterisk (*):

a. If the critical item is not performed by the time / temp pressure /etc. the crew fails that item. j

b. If a critical task is specifically assigned to an individual, and that task does not get completed, by someone in the crew, l then the individual fails. {

1

c. If a critical task is not addressed by the SRO with the Control Room Command Function, then that SRO fails.  !

l

d. Critical Items with no designated time / parameter vill be cause  !

for failure if not completed by the end of the scenario.

e. The Shift Supervisor must classify the events to pass, only if he l 1s informed of the plant conditions. l I

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t Part 1. SCENARIO GUIDE COVER SHEET l l ,

NUMBER RPE-03B

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SCENARIO GUIDE REFERENCES l ONI-N62, Rev. 3; ONI-C71-1, Rev. O, TCN-l; PEI-Bl3, Rev. 1, TCN-6; PEI-D23-2. Rev. 1. TCN-6: PEI-D2?-3 Rev. 1. TCN-l: PEI-E12. Rev. I:

PEI-C42. Rev. I: PNPP Technical Socci ficat ions: EPI-AI. Rev. 3: EPI-A3.  ;

Rev. 3. TCN-4 . EPI-B l . Rev . 5. TCN 5 l

1 1

APPROVAL PREPARED By M. S k s/C. E P son DATE / N /kM j PTS REVIEW N. H. Johnson 88 E'// DATE I

~

OPS REVIEW D. R. Cardner clAC N D AT E -- *'.

j

• *, . .. 1 NRC REVIEW DATF i se l

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t .

Simulator Exam Briefing checklist

1. TheprimaryresponsibilityistooperatethwfacilityasifitSire'the plant.

2. Team work and communication between operators is evaluated. It benefit.: the exam process to verbalise observations, analysis, and reasons for actions more than normally would be done dering actual plant operations.

3. The operator recognises an incorrect decision, response, answer, analysis, action taken, or interpretation of the team which the operator is a part of but fails to correct, then the examiner may assume that that operator. agrees with the incorrect items.

4. A rough log may be kept during each exercise that would be suf ficient to complete ;ecessary formal log entries which may be evaluated under administrative topics.

5. A designated facility instructor vill act as the auxiliary operators, radiattom health and chemistry technician, main:enance supervisors, plant management, and anyone else needed outside the control room area.

6. The facility examiner vill provide a shift turnover before the exercise begins. The shift turnover will include present plant conditions, power j history, equipment out of service, abnormal conditions, surveillance due, I

and instructions for the shift.

7. Control board switches may be purposely misaligned to enhance a simulated scenario or transient where appropriate and is not part of the evaluation.

If misaligned, they should be tagged or otherwise highlighted as appropriate to the facility. The examiner vill not misalign switches during the scenario as an awareness drill.

t'o t e : Chief examiner has the option to tell the operators that no control board switches will be misaligned on a given scenario or set of scenarios. If no switches are misaligned, the chief examiner may wish to reduce the time it takes for the operators to complete the board walk-down and accept the shift.

8. Operators will be allowed three to five minutes to familiarise themselves with the status / conditions of the control boards prior to the start of the exercise.

9. The simulation facility part of the examination vill consist of two exercises lasting approximately 50 minutes each. There vill be a short break between exercises to set up the initial conditions for the next exercise.

10. If the operators have any questions concerning the administration of the operating test, those questions should be answered prior to the start of the test.

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l J

6 NUMBER m :RRE-038 -

1 . ,

.,i r n

LIST OF MALFUNCTIONS  !

8 MALFUNCTION NO. TIME TO GO MALFUNCTION TITLE 01 l 0498 0 CRDH Pump B Trip j on 0517 0 HPCS Pump Trip i os  :

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. 04 l 05 I os  !

07 08 i 09 y

10 t 11 f 12 I l

1 13 I I N i

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15 l 1a l

2a  !

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NUMBER RPE-03B i l

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PTS SCENARIO GUIDE OBJECTIVES .

SCENARIO NUMBER: RPE-03B A. TERMINAL OBJECTIVE:

The operator, acting as a member of a shift operating crev, must demonstrate competence in performance of license duties required to protect the public health and safety while operating the plant in accordance with approved instructions and procedures.

B. ENABLING OBJECTIVES:

1. Following a pre-shift brief, each crew member vill be abla to provide a detailed plant status report to includes

a. Operating equipment.

b. Inoperable out-of-service equipment.

c. Any applicable daily instructions,

d. Evolutions in progress / planned.

2. Using plant installed instrumentation, plant instructions, as well as information obtained by operating personnel outside the Control Roca, the operating crev vill correctly diagnose plant problems.

3. The RO/ BOP vill be able to perform the immediate operator actions, from memory, *n response to the following plant transients.

a. loss of Condenser Vacuum.

b. Rector Scram.

4. The Unit Supervisor vill be able to use appropriate ONI's to enstire completion of immediate actions and direct those supplemental actions as required to interface with Plant roergency Instructions and Energency Plan Instructions.

5. When using I0I's, S0I's, ARI's, ONI's, or PEI's, the Control Room operators vill be able to : .

l . .

- 5-

. - - - , - , - . , - , ..g ,, , .--p. - -_y, ,,.r,r--,, ywye, . , . ,% eg e.- - , e,---, .w .

9+-ww-+ ,ve ---r- m.--w.--i e ------+w -

PTS OBJECTIVES SCENARIO NUMBER: apg_o33 i

a. Locate proper section of the instruction.

b. Follov instruction correctly.

c. Locate and observe installed insti- 'ntation.

d. Analyze system response.

e. Direct plant operators.

f. Inform US vhen complete.

6. Vhile operating in accordance with Plant Emergency Instructions the US vill:

a. Appoint an individual to be responsible for the control of reactor power, level, pressure or containment parameters.

b. Specify the plant systems to be used to control plant parameters.

c. Evaluate changes in plant conditions against current actions being taken and make corrections as necessary.

d. Keep plant operators up to date on recovery plan.

7. When directed by the Unit Supervisor to perform actions in accordance '

with PEI's, the S0 ville

e. Utilize the systems designated by US,

b. Monitor system performance, i.e. pressure, fl.ov, etc.

c. Inform the US !mmediately when a system becomes unavailable for further use,

d. Inform US of plant trends in response to actions taken.

8. Given a set of plant conditions, the Unit Supervisor vill be able to comply with the requirements of Technical Specifications and Administrative procedures.

m

PTS OBJECTIVES . .

SCENARIO NUMBER:

9. The Shif t Supervisor vill be able to utilize the EPI's to properly:

a. Classify events.

b. Complete paperwork.

c. Make timely notifications.

10. The Shift Technical Advisor vill Lssist the operating crev as requested in accordance with IAP-0101 and EPI's.

a. Verify proper identification of Off-Normal Events, proper sequence, and recommend actions to mitigate / terminate the events.

b. Verify proper classification of emergency events, recommend actions to mitigate consegrences of the event, and assist in completion of required papervotn.

c. Assist / clarify Technical Specifications applicable due to events.

P i

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A. NARRATIVE

SUMMARY

___ =

RPE-03B SCENARIO NUMBER Unit is operating at 94%, I0I-3 at step 4.3.30, sequence A, all rods out. l NCCU 'B' pump tagged out.

CRD 'B' pump tagged out. ,

HPCS pump tagged out. j 1

An air leak in the 'A' Auxiliary Condenser causes a decrease in Main and  ;

Auxiliary condenser vacuums and entry into ONI-N62. 'A' RPPT may or may l not be secured so that the air leak can be isolated. A small reactor coolant pressure boundary break occurs which causes Dryvell heat up and pressurization while maintaining reactor pressure and level. PEI-D23-2 and 3 entered. Dryvill pressure of 1.688 causes a reactor scram (if a shutdovn not manually performed) and entry into PEI-B13.

The scenario ends when the reactor is shutdown with stable level, and possible lowering pressure due to operator actions, and Dryvell and Containment parameters under control and non-breach threatening.

i 1

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______.-_._.____.____..._.__.I

NUMBER RPE-038 -

B. INSTRUCTOR PAGE , .

INSTRUCTOR NOTES -

SIMULATOR SCENARIO GUIDANCE I. Initialize Simulator to 10-36.

- Insert the following nalfunctions:

-- 0498 CRD Pump B Trip

-- 05U HPCS Pump Trip

- Place Red Tags on HPCS pump motor breaker and CRD B Pump.

- Place Simulator in RUN, ensure annunciators reset and plant is stable.

D01: See belov - Allov operators to enter, provide shift turnover and allow them to walkdown panels.

NOTE: Use TDF to II. Decreasing Condenser Vacuum.

cc*iltor main cond. {

.I

v. uun main 2 22". A. Insert malfunction 0718 variable Aux.  !

Cond. Condenser A Air Leak. Using increase 1 N21 PACAA Aux A pushbutton, set at ' 3. (May need cue from )

N21 PHP CA HP evaluator.) l N21 PIPCA IP N21 PLPCA 1P '

B. Event Recognition.

C. ONI-N62 Immediate Actions I

D. ONI-N62 Supplemental Actions.

1

1 NUMBER RPE-03B I l

STUDENT. PAGE .

1 STUDENT DIRECTION INSTRUCTOR NOTES l

I. Operators familiarise themselves with plant conditions.

l l

II. Decreasing Vacuum.

A. R0/ BOP Actions.

- From alarms / indications determines 245000-A2.03 vacuum is decreasing. 3.5/3/6 ,

B. Unit Supervisor informed of lowering 295022-GEN 11 Condenser Vacuum. 3.7/3.8 C. ONI-N62 Immediate Actions, the Unit 295002-GEN 10 Supervisor should direct / verify completion 3.8/3.7 of the following Immediate Action of ONI-N62.

- Place Recirc Flow control in manual. 202002-GEN 13 3.6/3.4

- Reduce power with Recirc to maintain 202002-A4.08 vacuum. 3.3/3.3 I

D. Unit Supervisor should direct / verify All of the below I the following Supplemental actions of steps are I ONI-N62: 295002-GEN 12 l l 3.4/4.1 l i

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9 l

1 RPE-038 NUMBER I  !

m nn INSTRUCTOR 'PAGE . - -

t INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE off Gas System flow NOTE: Any or all of the Supplemental actions hould show increase .may be performed based on the crew's diagnostic f checked / asked. ability and the constraints of simulator modeling.

i I

E. Feedvater Shifts to allow isolation of

'A' Auxiliary Condenser.

NOTE: This step vill only be evaluated if the crew correctly diagnoses 'A' Auxiliary condenser es the source of the problem and take actions to isolate the problem.

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NUMBER RPE-03B STUDENT. PAGE .

STUDENT DIRECTION INSTRUCTOR NOTES

- Reduce power per 10I-3 to maintain 294001-A1.02 vacuum. 4.2/4.2

- Check operation of Cire Vater System. 295002-AA1.07 3.1/2.9

-AK 2.08 3.1/3.2

- Check operation of Steam Jet Air 295002 AK 3.06 Ejectors. 2.9/2.9

- Maintain Reactor Level. 295002-A3.02 3.4/3.4

- Check Off Gas System. 295002-AA1.02 2.9/2.9

-AK 2.07 3.1/3.1

- Check Steam Seal Evaporator Parameters. 295002-AK2.11 2.6/2.7

- Check Condensate Seal System. --

- Isolation of affected component. 295002-AA2.02 (See step E.) 3.2/3.3 E. Feedvater shifts.

- Unit Supervisor directs / coordinates the following:

• R0/ BOP starts MFP IAV SOI-N27 and C34. 259001-A4.02 3.9/3.7

• RO/B0P places MFP on Master level 259002-A4.03 controller. 3.8/3.6

,

• RO/B0P secure RFPT A, so the Aux. 295001-A4.02 Condenser can be isolated. 3.9/3.7 (See previous Step D.)

1 E

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l NUMBER RPE-o3s INSTRUCTOR PAGE .

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l lNSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE t OTE: Monitor DV [II. LOCA 1 ressure, use remote l unction FU line 1 A. Insert malfunction 0704, variable rate LOCA a nd/or 2 and line 14 and increase size oTTeak with "one quick click."

t o "fine tune" the j s ize of the LOCA.

! tep IV through VIII B. Event Recognition.

s ay all be performed  !

c oncurrently, since t hese are all parallel

aths the crev should i e taking at 1.688 in t he DVI PEI-D23-2 PEI-D23-3 IV. PEI-D23-2 PEI-B13 PEI-E12 PEI-G42 Page FV for remote function for PEI Bypass switches lines 12, 13, 14, 15, 16.

V. PEI-D23-3 Page FV for similar remote fursctions for PEI Bypass switch.

O e h

IduuSmuGE 12

NUMBER RPE-03B STUDENT. PAG E .

STUDENT DIRECTION INSTRUCTOR NOTES III. LOCA A. RO/ BOP notices increasing Dryvell pressure 295024-EA2.01 based on alarms / indications. 4.2/4.4 B. Unit Supervisor ir. formed of increasing 295024-GEN 11 Dryvell pressure causing the following: 4.3/4.5

- ECCS initiation.

- Containment isolation.

IV. Unit Supervisor enters PEI-D23-2 based on 295024-GEN 12 high Dryvell Pressure and directs / verifies 3.9/4.5 the following:

• A. Restore NCCV/ Instrument Air to the 223001-A2.01 l Containment /Dryvell for D;yvell Cooling. 4.3/4.4

• B. Restore Containment Cooling. 223001-A2.01 4.3/4.4 C. Monitor Dryvell/ Containment pressures 295024-EA2.01 and maintain within specifications. 4.2/4.4

-EA2.09 4.0/4.1 V. Unit Supervisor enters PEI-D23-3 based on 295028-GEN 11 on high Dryvell Temperature and directs / 4.2/4.4 verifies the following:

• A. Restore NCCV/ Instrument Air to Containment / 295028-EA1.03 Dryvell for Dryvell Cooling. 3.9/3.9 B. Monitor Dryvell Temperature trend, main- 295028-EA2.01 tain Dryvell temperature < 330' F. . 4.0/4.1 295028-CEN 3 3.1/4.2 13

l NUMBER RPE-035

- ,m INSTRUCTOR PAGE .- -

INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE i i

VI. PEI-B13

~

q Jl I

'l NOTE: This instruction may be entered as a result of a FAST REACTOR SHUTDOVN initiated as a result of increasing Dryvell pressure.

l NOTE: This instruction entry may be subtle or

! even non-apparent due to no immediate concern

for power, pressure, or level and priority being i given to Dryvell and Containment parameters.

f

.! A. Section 3.0 NOTE: Mode switch may be in Shutdown due to j a FAST REACTOR SHUTDOVN.

NOTE: Hydrogen Analyzers NOT simulated.

6 B. Section 3.1 i

NOTE: This step may be subtle or non-apparent due to the successful scram.

I C. Section 3.2

HOTE

This step may be subtle or even non- l

apparent due to pressure under control on bypass valves.

D. Section 3.3 NOTE: This step may be subtle or even non-apparent due to level under auto control of feedvater system.

i 7II. PEI-G42 6

NOTCt HPCS and RCIC Systems shift suction source to the Suppression Pool on high Suppression Pool Level. RCIC may be placed back on the CST for up to one hour.

14

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NUMBER RPE-03B STUDENT. PAGE .

)

STUDENT DIRECTION INSTRUCTOR NOTES l

i VI. Unit f. pervisor enters PEI-B13 based on 295024-GEN 11 1.igh Dayvell pressure and directs / verifies 4.2/4.3 ,

the following actions.

l l

A. Svetion 3.0

- Mode switch to shutdown. 212000-A4.01 4.6/4.6

- Hydrogen Analyzers started. 223001-A1.05 3.1/3.1 B. Section 3.1

- Power verified to be < 4% and IVE 215005-A1.01 step used to test exit from section. 4.0/4.0 C. Section 3.2

- Pressure verified to be less than 241000-A3.08

,1033 and being controlled. 3.8/3.8 D. Section 3.3

- Level verified 185-215" and being 259002-A3.05 maintained. 3.4/3.4 VII. PEI-G42

• i

- The Unit Supervisor should enter tnis 295029-GEN 11 instructicn when Suppression Pool level 4.2/4.5 reaches 18.5 feet and direct / verify the following steps:

15

NUMBER RPE-03B INSTRUCTOR PAGE - '

m nn INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE NOTE: This PEI may be entered now or later due to the priority being given to PEI-D23-2/3

. for control of Dryvell and containment parameters.

~

VIII. PEI-E12 f_ d/

4 /

// / -

m --

l" Whl A %

_-. W NOTE' Entry into this instruction may be subtle, l" ---

gkRs but Suppression Pool cooling should be directed

,, , , , , , , , , C. when Suppression Pool temperature reaches 90' P.

~ unless the US/SS determines that the RHR 1, oops "O"."--.-==- may be needed for adequate core cooling.

IX. Emergency Plan Actions l

l

• NOTE: Declaration of the event may be recommended by any crew member. Classification in a conser-vative direction is not cause for failure of this I step.

)

NOTE: Evaluator or Simulator Instructor (machine operator)

HUST inform the operator that leak rate is 70 gpm.

16 l

_. NUMBER RPE-03B STUDENT PAGE .

STUDENT DIRECTION INSTRUCTOR NOTES I

- Lover Suppression Pool level using any of 295029-EK3.02 the systems listed in the PEI (G42 is 3.6/4.0 primary.

VIII. PEI-E12 entered when Suppression Pool temperature 295026-GEN 11 exceeds 90* F. Actions directed / verified by the 4.4/4.6 Unit Supervisor. 295026-GEN 12 4.1/4.1

- Place a loop of RHR into the Suppression Pool 295026-EA1.01  ;

Cooling mode of operation. 4.!/4.1

• - Suppression Pool temperature maintained 295026-CEN 3 vithin the Heat Capacity Temperture Limit 3.2/4.3 (HCTL).

I IX. Emergency Plan Actions

- The Shift Supervisor and/or the STA should perform the following items:

• -- T1.e Shift Supervisor vill declare an ALERT 295024-GEN 2 per EPI-A1. 3.1/4.4 295031-GEN 2 l 3.1/4.6 '

-- The Shift Supervisor should ensure that 294001-A1.16 paperwork completed per EPI-B1/A3. 2.9/4.7

-- The Shif t Supervisor should ensure that 294001-A1.16 initial notifications meet the 15 minute 2.9/4.7 recommended time frame.

m 17

RPE-038 NUMBER

- ,m INSTRUCTOR PAGE . .

INSTRUCTOR NOTES SIMULATOR SCENARIO GUIDANCE X. END OF SCENARIO A. When the reactor is shutdown with water

. level under control and pressure being maintained or intentionally lowered and with the Dryvell and Containment parameters improving or under control, (DV temperature

> 330' and the Shift Supervisor has addressed the ALERT actions, perfora the following

- Place the Slaulator in FREEZE.

Conduct end of session critique to include the following items:

-- Standard critique items.

-- PEI-E12/G42/B23 entries and priorities related to a LOCA.

-- Fast Reactor Shutdown option if not utilized.

-- Auxiliary condenser isolated option if not utilized. j l

( i 18 w-, -y---wy-e.--q w----e--.-. - p.- - ,-- ---p,. ,,w.,.,-ww - , - - -g-,,wgm%yg-- -

--9-an 3--e4--y----ve-e--vm

• um M y-twvvw-= = - *e-'---

NUMBER RPE-038 STUDENT PAGE .. .

STUDENT DIRECTION INSTRUCTOR NOTES X. END OF SCENARIO A. Operators participate in the end of session critique.  ;

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NUMBER RPE-03B i

INSTRUCTOR PAGE . . .

- nn INSTRUCTOR NOTES ' SIMULATOR SCENARIO GUIDANCE

-- INTENTIONALLY BLANK --

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l 20 -LAST j

m m . sao e . 3ine l

PERRY NUCLEAR POWER PLANT , l JOB PERFORMANCE MEASURE WORKSHEET

= ao. 202m:0101 ,,.. n ,,,,, 1 ,, ,

ll Rev.

O Task No-Task

Description:

Reart Reartne g.,4,, p,,,

1 (3.5) (3.7) '

x/A neference: ' ^'*

( u t> 1123) (J.6) (J./) ^.9)

(3 (3.8)

A1.01, A1.08 GEN 1, GEN 7 (J.b) (3.8) (3.6) (3.7) (3.8)  ;

A3.01, GEN 9 A3.06, A4.01 GEN 9  !

I AP#LICABLE IdETHOD or TESTINC:

Simulate performance Actual performance I

$1eulator I in. Plant Control Room Classroom _

flee for completion 10-15 ainutes (approximate)

PREPAAED $Y:

JM f ,(

AfYlEFED BY; , 4-

, ) , 3ly y l

lastnctJmaj 'tacmclocast este 1 APPRQY[Q Bf; NW dwse fraanary Jrtienctor i <k/G fa,gg

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

i are o. sans nov. N p no, 202002010I page s of 5 operator tvaluater

$$n _ Oate i

License: RO O := l KA0 TO TM GPERAf 0ft

! will explain the initial conditicas, which step (8) to simulate or discuss, and I provide initiating cues. When you (Amplete the task successfully, the objective for this job performance measure will W retisfied.

INITIAL CONDITIONS:

Preparations being made to perform Cold Reactor Startup per 101-1. RPV temperature 85* F. , valve lineup complete for Reactor Recire System per VLI-B33. All necessary instruments in service. HPU startup complete.

Reactor Recirc Pump Seal Cavi t ies vented. Dryvell Closeout per 101-1, Attachment 3 complete.

Machine Operator: IC-1, apen 3A/B and 4A/B, reset using FCV motion inhibit lights / annunciators, start CRDH if not running.

TASK STA@ARDS Reactor Recire Pump A running in Slow Speed IAV $0I-B33.

REQUIRED MATERIgk$:

101-1  ;

SOI-B33 SVI-B33-TI168 Plant Connunication Systems MERAL

REFERENCES:

101-1 SOI-B33 SVI-B33-Tl168 1

INITIATIE CUES, i US orders startup of Reactor Recire Pump A to slow speed. [AV SOI-B33.

(Soction 4.1) b

I per c.som nev,um p n,, 2020020101 p., 3 ,, 5 EEBFORMANCE INFORMATION ,

M TC: Critical steps denoted ulth a *C*. Failure to meet the standerde for this stan cenetitutes failurs. Segwnee is asswed wiless abnoted Jn the ' Comments'.

_ l PERFORMANCE STp : Direct PPO to verify the Leak Detection System (E31) is in I

..................... service and that bearing oil levels on the LTMG's are normal, '

@!T.

STANDARD: Without Error I

COMMENTS: PPO is directed and performs, i PEnr0RMANCE ST&: Direct PPO to verify the following switches in normal on )

.......C............. Aux. Relay Panel B33-P00lA: i aj Steam b PowerLine PumpB33-S126A Interlock Suction AT Intik B33-Sl25A )

stanomatx c) Total Feeawater Low Flow Interlock B33-S127A Standard: Without Error COMMENTS:

PPO is directed andperforms.

Only item "b" is critical for pump start to slow speed.

PERrom>ANCE ste : Verify Flux Estimator Bypass switch B33-S128. in NORMAL and

.. ........ ..... . simulate Automatic Flow Demand Limiter set at 100% on Unit Dir. Control Console, H13-P680.

STANDARD: Panel Indication COMMENTS: AFDL not simulated Eut. att.

PERFORMANCE ST&: Operate Recire Loop A Flow Control B33-K603A slide switch

......C... ..,,,, to obtain 0% Valve Travel.

Dif.

$TANDARO: Panel indication COMMENTS:

PERr0RMANCE STU : Perform SVI-B33-Tl168, Idle Recire Loop Temperature and

.....C............. Flow, within 15 minutes of idle pump startup.

, Git.

STANDAAD: Recognizes requirements of step.

COMMENis: Step is verbalized.

TERMINATING CUES:

1 l

PtPP U. 8242 Rev. NJ JPN No. 707&o70f01 P60s 4 ef 5 PERFORMANCE INFORMATION . j h0rt: Critical steps denoted with a *l*, failure to meet the stancurde for thJs its?e cenetitutee \

fafJure. Sequence Js assamed unleas donoted in the 'Casments*.  :

PERFORMANCE STEP: Take Recire Pump A Breaker 3A and 4A control switches on *

........C,,,,,,,,,,,, P680 to CLOSE.  !

atir. ,

STANDARD: Panel indication. l l

COMMENTS:

M. Inri.

PERr0RNANC2 $Ttp: Take Recire Pump A Breaker SA control switch on P680 to

.........9......... START.

mr.

STANDARO: Panel indication.

COMMENTS: May receive Recire A Motor Vibration Hi Alarm during pump I startup. .

.................... l M. fair. '

PtAr0RMANCE sitP: Verify that LFMG A Supply Brkr IA closes, Recire Pump A Stkr

. .. ........ ...... 5A opens when Recire A pump speed (B33-R651A) indicates offt. approx. 1700 rpm, and 1.FMG A Output Brkr 2A closas vnen AIAteNts: Recire A pump speed (B33-R651A) indicates approx. 450 rap.

Standard: Panel indication Cone (MTS:

M. Intr.

1 PERFORMANCE $TEP: Direct PPO to perform independent verification of required eomponents.

)

rNt.

ST ANfd.se: Without Error COMMENTS: PPO is directed and performs M. turr.

PERFORMANCE STEP

• Ot!r.

STANDARD:

Cohe(MT5: l M. arr.

TEAMINATINC tuts: Reactor Recirc Pump A started and running in slow speed.

999 m. 82eX W. P88 m no. 2020020101 P.,e 5 of 5 (LAST)

VERIFICATION OF COMPLETION .

Operator Evalustor

$$N Date Licenu: R0 SAO Number of Attempts Result: O sarrsractoav O unsArisractoar

@ TE: An *Lnsatisfactory* tequires Canaerst std elli requite subsewt remedial ttnining.

COMMENTS / FEED 8ACK

/

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--. _ ,- ,g-- -q -,, -,,-,e -.-,-,,,n, ,,,,--,--,,yg- m , w e

PDtAY MUCLgAR POWUt PLANT

_ m, SYS7EV WA C-l ROUG' "EST P A 4 PAM I of 1 .

Sys g , B33 M NO. 2020020101 \

Start Reactor Recirc Pumps TCPIC/ DESCRIPTION: '

1 l

202002 I O CEN 9 mrts 3,8 / 3. 5 : What actions should be taken if agsta the FCV's will not position to the minimum flow position by normal methods with

_ recire looe temocratures < rated condit ions?

m: Direct I&C to resposition the FCV's to the minimum flow position with the Servo Direct Cable.

CPotSE/t3*OT5:

202001 GEN 11 un* 3.4/4.2 Temperature dif ferentia'.s and agsto 2 o flow rates must be determined IAW SVI-B33-Tl168 prior to startup of an idle recire Innn. kbt time limit is ienosed on these checks?

aso: Must be determined within 15 minutes prior to startup. _

mm T . S . 4 . 4 .1. 4 1

202001 utpc3. 7 / 3. 7 Why does the Reactor Recire pump EISTD 3  : o A4.01 start in FAST speed initially regardless of plant conditions?

m. Fast speed power required for break away torque - LDiG cannot handle startinn amos. I l

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nw mea - a m m, SYS"EV W A'_C- 90UG "ES" >_A 9 j PACE 2 of 7 ,

SYSTEM B33 l D NO. 2020020101 l TOPIC /0ESCRIPTION:

Statt 9eactor Reeire Pen n , i

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202001 3.9/4,2 ,_

4 o A2.15/A2,14 uty 3,7 /3. 9 : If breakers 3A and 4 A fM1pd aISTI>  :

to close when the switch was taken t o CLOSE . what two tries could be orevent ine the cloeure? (SRO ONLY) What are the satooints for these trio circuits?

mse: Foc-RPT-Tcv 6=r -1nenr /T9V cinenr >an? 9tp RRCS - 1083# + APRM upscale + 25 see or Level 2 8C Mr/03* O '3 aISTI) o utDC l

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I coal::mxs GISTIm p utDC ,

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a TEMPC ANGE TEMP ANGE TEMP CHpNGE l TEMP CgANGE OM3As $0I-833 PAGE l 0F 1 PAGE I OF / fAGE d W M f ,

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4. To prevent pecking overheating or excessive bearing wear, minimise stroking Flow Control Valves until aysten flow has,.

been established. ,

9. Starting Reactor Recirculation Punps at reduced reactor water levels may result in a full Reactor Protection Systes p.

actuaction on low reactor vessel level (Level 3).

N 10. Dryvell Cooling (M13) or Containment Vessel and Dryvell Purge I (M14) Systems should be operating to provide adequate heat dissipation when Recirculatfan Pumps are running.

11. Vater in the Reactor Recirculation System is potentially con- T/# -

4 taminated. Its handling and disposal shall be in accordance vith Site Health Physic Instructions.

12. Extended operation on IJMG with the Reactor Recirculation Plov gg-Control Valves less than or equal to 20% should be avoided due to the occurence of excessive oscillation and/or temperature $

stratification between reactor steam dome and botton. head.

13. RCIRC Plov Control Transfer from Master Manual to Automatic N~

Plov Control shall not be performed until the test results 17 covering this mode of operation are approved by PORC.

3.0 PREREQUISITES

1. Valve lineup completed per VLI-833,

2. Verify that applicable instruments vital to the systee are in ,

service for the expected mode of operation.

4.0 STARTUP l All Reactor Recirculation System controls are located on the following panels:

Unit Control Console,1813-P680 NSSS Recorder Panel, 1513-P614 Auxiliary Relay Panel, IB33-P001A, IB, ELEV. 620' Auxiliary Relay Panel, IB33-P001B, IB, ELEV. 620' 4.1 ECIRC Pump A(B) Startup To Slov Speed

1. If required, perform HPU Startup.

2. If seal injection has been secured and system pressure has been less than 300 psig, vent the RCIRC Pump Seal Cavities.

Tce-19

TEMP CgANGE . TEMP CHANGE 7g,y.f 7 YM ' dI l'7 e OM3& 80I-333

/S -

PAGE A 0F 1 p'GE A 3.OF. 1 Page 2a

. . . . . , .. .Rev.: 2 -

3. Verify the following: ,

i

a. Leak Detection System (131) in service. ,

tv. Bearing oil levels on LFMGs are normal.

4. Verify Dryvell Closeout, Attachment 3 to I0I-1, Cold Startup, i or 10I-2, Bot Startup, has been completed. If the Dryvell is  ;

accessible, verify the followings i

I l

O O 1

__4 . - . . .---___,.___,..e..m . _ _ _ , _ , ,-. , _ , . , _ . ,,,-,,.,w.-m.,,,f.w_-- y,c y - e n m ._,-- + , - , _ .'

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l TEMP (Hf.hGE TEMP CHANGE i l.

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p In eU PAGE 1 CF MI- -

OM3a: 50I-B33 Page: 3 j- Rev.: 2 i

a. Nuclear Cid.. .. W g (Pe3) in service supplying cooling '

vater to the k, 't h 'os and motors.

b. Bearing oil lev n r ;he RCIRC Pusp motors are normal'. -

c. Control Rod Drive .es (C11-CRDB) in service supplying 3 l to 5 gpa RCIRC P seal injection.  !

5. Verify the followin switches in NORMAL on Auxiliary Relay Panel, 1B33-P001A(B):

[l r

a. STEAM LINE PUMP SUCTION at DrrLK, iB33-S125A(B).

• 52  !

b. POVER INTERLOCK, 1833-5126A(B).  !

c. TOTAL FEEDVATER LOV FLOV INTERLOCK, IB33-5127A(B). i TC{,, 6. Verify the following on the Unit Control Console, 1H13-P680:

a. FLUX ESTIW.J0R BYPASS switch, IB33A-S128, in NORMAL.

b. AUTOMATIC /LOV DEMAND LIMITER,1833-K651, se t at 100%.

i Tc- 7. Operate RCIRC LOOP A(B) FLOV C0:frROL, IB33-K603A(B), slide l

• CG switch on P680 to obtain 0% VALVE TRAVEL.  !

NOTE: Reactor recirculation system FCV feedback circuits ye, are calibrated at normal RPV operating temperature. l As a result, it may not be possible to position the Ik '

FCVs at the minimum flow position by normal methods  ;

(. vith the recireplation loop temperatures at less than '

rated conditions. If this ocents, have I&C reposition the FCVs in the minimus flow position with the Servo Direct Cable. i

8. Perform SVI-B33-T1168, Idl( Rea,irculation Loop Temperature

• and Flov, within 15 minutes of idle pump startup. *.6M

9. Take the foll'oving control ssitches on P680 to CLOSE: l I

a. RCIRC PUMP A(B) BRXR 3A(B). j

b. RCIRC PUMP A(B) 3RKR 4A(B).

NOTE: RCIRC A(B) MOTOR VIB HI alarm may be received during j pump startup. l

10. Take RCIRC PUMP A(B) BRKR 5A(B) control switch on P680 to START.

11. Verify the following on P680:

a. LFMG A(B) SUPPLT BRKR 1A(B) cic,ses.

b. RCIRC PUMP A(B) BRKR 5A(B) opens when RCIRC A(B) PUMP SPEED on 1B33-R651A(B) indicates approximately 1700 rps,

c. LFMG A(B) OUTPUT BRXR 2A(B) closes when RCIRC A(B) PUMP

( SPEED on 1B33-R651A(B) indicates approxime sly 450 rps.

12. Perform independent verification of the required components.

4.2 HPU A(B) Startup NOTE: HPUs A and B may be started sis.ultaneously.

Syates. Valktheough F;llow-cp Questions Document 3 tion Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify) '

Topic Area Evaluation: 1. Performance Measure - -

2. Question Number -

Question (to be completed during exas):

l

)

Response (to be completed during exam):

J Question Derivation (can be completed af ter examination):

Simulator Evaluation Defic.iency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number _

Question (to be completed during exas):

Response (to be completed during exas):

Question Derivation (can be completed af ter examination): .

Similator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number Question (to be completed during exas):

l l

1 Response (to be completed during exas):

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MfP No. 1245 fEV. JIt0 ,

PERRY NUCLEAR POWER PLANT ,

JOB PERFORMANCE MEASURE WORKSHEET I

i

,)PM No. 2020340101 ne,, 0 page i or _5_

Task No. 2020340101 nev, O Task Deteription: Startup a Reactor Recire FCV HPU frota the  !

Control Room l

x/A

Reference:

202002 Kl.12(3.7/3.9) GEN 7(3.6/3.6)

~

CEN 9 3.8/3.5 apt _ICABLE METHOD Or TE571NC:

Simulate performance X _ Actual perforsence ,

l Classroom Steulator In-Plant Control Roca , X Time for cosoletion 15 minutes (approximate) (Assumes Pump Warmup complete)

PREPAAE0 Bf:

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eOrte 1 REVIEsc GY: h 1 1 1 S ll Instnctional lectnologist inte l

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M'PROYED Bf:

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L4 cense itsL% instrtetot i ck/8Y_

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~PPP peo, $2454 Rev. Stu m no. 2020340101 page 2 o f . 5__,,, j Operator E#elastor Sen Date

• t.icense: O ao O Sao .

l READ TO THE OPERAT,DR 1 mill explain the initial conditions, which step (s) to sisuiste or discuss, and provide initiatinc cues, when you complete the task successfully, the objective for this job performance measure will be satisfied.

l INITIAL CONDITIONS:

Recire HPU's are operable and have been shutdown for two days for maintenance. (Prerequisites completed.) HPU A and B have been verified to be shutdawn. )

l TASK STANDARDS Recirc HPU A operating IAW SOI-833 REQUIRED MATEPJ:4LS:

SOI-B33 * '

Plant Communications System GENERAL

REFERENCES:

SOI-B33 INITIATING CUES:

f US directs SO to startup Recire HPU A.[IAW SOI-B2;. (Section 4.2) h

pier u. stea ne,. was - - "

JPM ne. 2020340101 ps ,e 3 or 5 PERFORMANCE INFORMATION Nort: criticsJ steps doneted eith e 'c'. raffure to meet the diewhtds for this Jtes eenetitutse (sJJwe. soguence Ja essumed wifees duneted Jn the "Cumaants'. -

l Ptw oRMANet STEP: Verifies channel I and qhannel 2 red iights not lit for

.......C............. excessive rate of change lockup on Bl3-P634 (Card K657A, ,

81f- Rack 1, Nest 5, Mark R/C/L) sfANDARD:

CoMMEN": No valve position excessive rate of change lockup indicated (Bl3-P634, Rack I, Nest 5)

...... ... ...... q PtaroRMANCE STEP: Depress simultaneously Subloop I and 2 READY pushbuttons

.......C............. for Reactor Recirc hPU A (P614) mir.

STANDARo: Subloop 1(2) Ready Light comes on  ;

Subloop 1(2) Maintenance Light goes off FCA A(B) Rednt Subloop Inop Alarm on P680 clears (P680-4-A6)

COMMENTS:

PtaroRMAMct sitP: Depress Subloop i Pump Motor Run/ Fan Motor Run Pushbutton

......C,,,,,,,,,,,, for HPU A (P614) air.

STAM3ARo: Subloop 1 Pump Motor Run/ Fan Motor Run Light comes on Subloop I Pump Moqor Sto / Fan Motor Stop Light goes off Subloo i Pressurized Li ht comes on FCV A(p)

B HPu Inop Alarm P680) clears (B-6)

C**E"I8 j Oil pressure may take 30-60 see to reach 1850-1950 psig Oil temperature may increase to oil warm alarm before y,ghil,(dng,,

(120*-140 F.) tvat. mir.

PtRroRMAMet STEP: Depress Subloop i lead pushbutton for HPU A (P614)

......C 3,..,......... .

STANDAno: Lead Pushbutton will backlight (Subloop !)

Subloop 2 will be in Standby.

Co*EMis:

PERroRMAMct STEP: Verify Vress Filter and Return Litae Filter Lights

.................... Extinguish for lead subloop.

017 STANDARo: Without Error COMMENTS: After several minutes (Evaluator - Inform operator "return Line Filter and Pressure Filter lights are out.")

TERMINAf!NG CLES:

^ W- ,,, - , - , - - -

l MPP Ms. No.,J see. NW - .

j i

JPN Mo. 202034010I pop 4 cr 5 1 PERFORMANCE INFORMATION l J

NDft CrjtJceJ stops doneieef yJth a "C'. reiJure to aset the atanderds for thJs J!as censtjtutse raJjure. Seguonce ls assunsef endees dunetosi in the "Consents'. -

' ~

Pt40fewett 3ftP: Continue Pump Warmup ,

........g......... ,

sTAMoAno: 30 minutes or until oil temperature reaches 102* F.

coMMEMis: At examiner discretion, step may be shortened.

(fell operator he is at 120' F.)

PtaronnANCE sitP: Operate Recire Loop A FlowControl Slide Switch B33-K603A

.......C............. (P680) to obtain 0% Servo Error.

Otlf.

STA@AAo: 0% Servo Error obtained COMMENTS:

M. Mr.

PtaroRMAMCE iltP: Take Recire FCV Motion Inhibit Reset Switch.B33A-Sil2

.......C........... to "A" position (P680),

orli.

siamAno: FCV A Motion Inhibit Alarm clears (P680) A-5 Lead Subloop's Operational Light comes on (P614)

CoteetMT5:

tut. 911.

PtRroRxAmet sitP: Direct PPO to verify "proper local operation orit.

STANDARo: Without Error cosestMis: Subloop pressure reservo r1850-1950 tempe ature psig,20-140*F, 1 reservoir fluid levelreturn line filter pressur 40psig,lowandk'ullsub5oopF0 between),

not red fan louvers open. P umpsuqttonv7

1. directed performs.catorrest.t.

cuu indi

- ~ ~g , g, -

e PEAroRMANCE STEP:

STAMDARo:

COMMENTS:

M. MT.

TEMMINATING CLES:

P614 cues: Return Line Filter Light off and HPU A is operating Press filter liah: off Actuator Drain light off Overload /Undervolt 1ight off 4

b f =

l f MPP No. 824% Arv. }lat pH No. 2020340101 Page $ er 5 (LAST)

YEB1FICATION OF COMPLETION operator _ Evalostor

$$N Date l I

License: R0 SAD Number of Attempts ,,_,

Result: SATISFACTORY UN$ATISFACTORY HTTL : An ' Unsatisfactory" requiter Connent and vill requite subsequent remedisi trainirn.

I COMMENTS / FEED 8ACK l

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Osutor's sinturr ,,,

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

1 1 PUtRT W AA POWEA PLANT

. m, SYS"EM W A <- -

ROUG' "ES" 3LA 4 PAGE 1 1 of_ ,

SYSTEM B33 '

JH NO. 20'034010I j

Startup a Reactor Recire from the Control Room TCPICIDESCRIPTI(N: -

I l

202002 SISTp I n CEN 9 Mtpc 3.8/3.5 jf'the 'HPU's have been shutdown ecue,a, j for > 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, what are the oil pumo warmuo reauiremenen a f t ,. e ni1 n ,-n mpo: If HPU's Shutdown 3 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> , contint.e pump warmup for 30 minutes or until oil reservoir temperature reaches 120' F.

g5pog;m SOI-B3 3, St ep 4. 2. 6 202002 afsto 2 o CEN 7 utpc 3.6/3.6 How are HPU trip first hit l

indications on P614 reset ?

l mpo: Simultaneously depress both Subloop 1 and 2 READY pushbuttons.

1 s

E3Posim SOI-B33. Steo 4. 2 not e .

O utpc SISTD MSIO:

IE3PDG/CD*OT5: ,

I TEMPGNANGE TEMP CHANGE e Yb e l' PAGE.l.CF 1 , ,PAGF. % 0F 1 og3A 3o1 333

~

Page: 3 Rev.: 2

a. Nuclear Closed Cooling (P43) in service supplying cooling ' 'l water to the'RCIRC Pumps and' motors. i

b. Bearing oil levels on the RCIRC Pump motors are' normal.

c. Control Rod Drive System (C11-CRDH) in service supplying 3 to 5 gpa RCIRC Pump seal injection. -

5. Ver.fy the following switches in NORMAL on Auxiliary Relay Panel, 1533-P001A(B):

' h

a. STEAM LINE PUMP SUCTION AT INTLK, 1833-S125A(B).

• 52

b. POVER INTER 14CK,.1833-S126A(B). .

c. TOTAL FEEDVATER LOV FLOV INTERLOCK, .. 1833-5127A(B).

TC- 6. Verify the following on the Unit control Console,1H13-P680s

,,g

a. FLUX ESTIMATOR BYPASS switch, 1833A-S128, in NORMAL.

b. AtTIOMATIC FLOV DEMAND LIMITER,1833-K651, set at 100%.

Tc- 7. Oyerate RCIRC LOCP A(B) FLOV CONTROL, IB33-K603A(B), slide 00' svitch on P680 to obtain 0% VALVE TRAVEL. ,

l NOTE: Reactor recirculation system FCV feedback circuits ye, f are calibrated at normal RPV operating temperature.

As a result, it may not be possible to position the lh  !

FCVs at the minimum flor position by normal methods l vith the recirculation loop temperatures at less than  !

rated conditions. If this occurs, have I&C reposition the FCVs in the miniaua flow position with ,

the Servo Direct Cable. l l

8. Perform SVI-833-T1168, Idle Recirculation Loop Temperature *169.o$

and Flov, within 15 minutes of idle pump startup. *

9. Take the follbving control switches on P680 to CLOSE:

a. RCIRC PUMP A(B) BRKR 3A(B).

b. RCIRC PUMP A(B) BFIR 4A(B).

NOTE: RCIRC A(B) MOTOR VIB HI alarm may be received during l pump startup.

i

! 10. Take RCIRC PUMP A(B) BRKR SA(B) control switch on P680 to i

! START.

11. Verify the following on P680s

a. LFMG A(B) SUPPuT BRKR 1A(B) closes.

b. RCIRC PUMP A(B) BRKR 5A(B) opens when RCIRC A(B) PUMP SPEED on 1833-R651A(B) indicates approximately 1700 rps.

c. LFMG A(B) OUIPUT BRKR 2A(B) closes when RCIRC A(B) PUMP L. SPEED on 1833-R651A(B) indicates approximately 450 rpa.

l L 12. Perform independent verification of the required components.

4.2 HPU A(B) Startup NOTE: RPUs A and B may be started simultaneously.

. =- . . - -- - -

TEMP CHANEE TEMPC ANGE ] 80I-833 e / # _ IT OM3As PAGE_1 0F .L, [ Page: 4

! PAGE

/ CF A- --

Rev. 2

. NOTE: Simultaneously depressing both Subloop 1 and 2 RF.ADY E~

pushbuttons vill reset the HPU trip first hit indicators inside 1H13-P614. . .

1. Prepare the HPU for startup by performing the following: TD"'

}&

a. Verify HPU A(B) is shutdown.

b. If a CHANNEL 1 or CHANNEL 2 red light is on on the VALVE POS CESSIVE RATE OF CHANGE LOCKUP card, K657A(B), (card mark.a R/C/L) in Rack 1(2) Nest 5, of the Recirculation Flow Control'Inatrument Paael,'H13-P634, perform the following:

1) Depress the RESET button located immediately below the on light and observe the red light out.

c. Simultaneously depress the Subloop 1 and 2 READY g.g pushbuttons for Reactor Recirc Hydraulic Power Unit A(B) on NSSS Recorder Panel, 1913-P614, and verify the following:

1) Subloop 1(2) READY light comes on.

2) Subloop 1(2) MAINTEN/ECE light goes of f.

3) PCA A(B) REDNT SUB LOOP IMOP alarm on P680 clears.

2. Momentarily depress Subloop 1(2) PUMP NTR RUN/ PAN MTR RUN pushbutton for HPU A(B) on P614 and verify the following:

a. Subloop 1(2) PUMP MTR RUN/ FAN MTR RUN light comes on.

b. Subloop 1(2) PUMP MTR STOP/ PAN MTR STOP light goes off.

c. Subloop 1(2) PRESSURIZED light comes on. -

d. PCV A(B) HPU INOP alarm on the Unit Control Console, 1H13-P680, clears.

NOTE: After a. prolonged HPU shutdown, oil pressure may take 30 to 60 seconds to reach normal operating pressure (1850 to 1950 psig). Oil temperature may increase to OIL VARM alarm before stabilizing at normal operating temperature (120 to 140'P).

3. Momentarily depress Subloop 1(2) LEAD pushbutton for HPU A(B) on P614. The LEAD pushbutton vill backlight and Subloop 2(1) T/ l'e/

vill be in standby.

O

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TEMF C)}ANGE TEMP CHANGE ,

1. PC p l$ OM3A SOI-833 fM-PAGE 7- 0F A PAGE.l.A OF 1 Page: 4a lg i l Rev.:

2

4. After several minutes, verify'the following lights go 'off on P614 for the LEAD Subloops '

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1

a. FRESS FILTER. -

b. RETURN LINE FILTER.

5. DELETED TTA[-

f

6. If the HPUs have been shutdown for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, continue  ;

pump varaup for .30 minutes or until, oil. reservoir temperature  ;

reaches 120'F.

l

~

. 7. Operate RCIRC LOOP A(B) FLOV CONTROL, IB33-K603A(B), slide switch on P680 to obtain 0% SERVO ERROR.

8. Take RCIRC FCV MOTION INBIBIT RESET switch, IB33A-S112, on F680 to A(B) and verify the following:

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1

. - - - - , , - , - , - - , --w,r

I

. 1 i

1 1

ON3At 301-333 ,

Page: 5 '

Rev.i ,

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a. FCV A(B) MDTION INHIBITED alarm on P680 clears,

b. The LEAD Subloop's OPERATIONAL light on P614 coess on. -

5.0 SYSTEM OPERATION

1. Monitor the following Recirculation Pump. parameters l

a. On the Unit Centrol Console,1813-P680:

Parameters Slow Speed Fast Speed RCIRC A(B) PUMP AMPS, 60-65 amps approx.

133FR609A(B) 300 amps RCIRC A(B) PUMP DIFF approx. approx.

PR , 1833-R605A (B) 10 psid 280 paid RCIRC A(B) PUMP SEAL 1030-1050 1030-1050

• CAV PRESS NO. 1, psig peig

• IB33-R603A(B) *

• 5 RCIRC A(B) PUMP SEAL 510-530 510-530

• CAV PRESS NO. 2, psig psig

• IB3FR602A(B)

• ACIRC LOOP A & B FLOW, 9-10x10 app 5*-

IC51-R614 gpa 38x10 spa RCIRC A(B) PUMP SPEED, approx. approx.

1833-R651A(B) 450 rpm 1800 rpm '

b Number 1 and 2 seal cavity temperatures on NSSS Bacorder

• Panel,1H13-P614, less than 160'F on 1333-TR-601. *5

2. Monitor the following HPU indications and perwterst

a. On P614:

1) RETURN LINE FILTER light off

2) PRESS FILTER lignt off i

3) ACIDATOR IEtAIM light off

4) OVERLOAD /UNDERVOLT light off

. + . , - -

,. -, ,,,e., -e g --,_,..7,, - - , , - . ,..,_,._m,, ..,, _ , , , . . , , , , , , _ , , , , , _ , . , , , , , , , . , , , . _, , , , , _ _ . , _ . , _ , , _ , _ _ , . , __

1 i

l Syaten V2lkthrough F:llow- p Queitions Docusestction j l

Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic. Area Evaluation: 1. Performance Hessure -

2. Ousstion Number .

Question (to be completed during exam):

Response (to be completed during exas):

1 Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number Question (to be completed during exas):

Response (to be completed during exas):

Question Derivation (can be completed af ter examination): ,

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure  ;

2. Question Number Question (to be completed during exam):

I l

Response (to be completed during exas):

PWP No. 8245 i4V. 3III

( . . .

PERRY Nbc' uR POWER PLANT .

JOB PERFORMANCE MEASURE WORKSHEET JPM Ho. 2(, . - 101 nov, ._ 0 page 1 or 5 Terk No. 2050340101 new. O Task

Description:

Startup Suppression Pool Coolirig from Standby Readiness i

(3.8) (3.9) (3.9) (3.9) (3.7) (4.0) (3.5)

K/A

Reference:

219000 Kl.01 K l .03. K l .04 K3.01. K6.06 A l .01. A l .02 (NUREG-1123) (3.7) (3.8) (3.7) (3.5) (4.1) (3.9)

Al.08, A4.01 A4.02, A4.07 A4.12. A4.13 (3.9) (4.0) (4.2) M (4.1)

GEN 1 GEN 7 GEN 9 GEN 13 GEN 15 _

APPLICABLE METH00 0F TESTINC.

Slaulate performance Actuel performance I Classroom Simulator X In PIsnt Control Roon

~

Time for completion 15 minutes (approximate)

PREPARED Bf:

Al.E. Mi@rr h i s/dn 6 Dede REVIEVED Bf: H I

htsttwila1el ladrologist Oste APPROVID Bf:

Cw L**itse itsinity instnetot

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l l

h me. 42434 Arv. If.J pn me. 2050340101 Pege 1_., of 5 Operator tvaluetor

$$N Date ,

License:

R0 SR0 READ TO ThI OPERATDR 1 vill explain the initial con 11tions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance nossore vill be satisfied. l l

INITIAL CONDITIONS: l All RHR System Modes operable. ESW and ECC Lcop A's in cperation. i l

l TASK STAE ARDS RHR A operating in Suppression Pool Cooling Mode IAW SOI-E12, with normal operating parameters of pump flov = 6900-7100 gpm, Putrp Amps = 95-110 amps, and Suppression Pool Temperature = 120 F. ,

1

, REQUIRED MATERIALS:

SOI-212 l l

S01-P45 .

SOI-P42 Plant Communications System ENERAL

REFERENCES:

S01-E12 SOI-P45 SOI-P42 INITIATING CM S:

. US orders R Loop A placed in Suppression Pool Cooling Mode frote Standby Readiness. IAW SOI-E12. {Section4.7)

~Pw P Mo. 824 a Aev. JI J pn No, 2050340101 p.ge 3 er 4 PERFORMANCE INFORMATION .

Mit: Critice) steps nonoted with s *C*. Tallure to meet the standeres for this item constitutes '

fa11ure. Segi.ence is assumed wiless denoted in the ' Comments'. .

PERroRxANCE STEP: Take RHR Pump A E12-C002A control switch to START.

.....9.............

• alt.

STANcAno: Pump start (red indicating lamp)

COMMENTS:

~. . .

(n. Mir.

PERrORMANCE STEP: Hold RHR A Ex's Outlet Valve E12-F003A Control Switch in CLOSE until valve position is 4% to 6% open, alt.

STAxoAno: Panel indication (red /greers indicating lights)

Vaive position meter indication CoMMEN($: This step may be performed simultaneously with the next step.

tw. att.

PEnroRMANCE step: Hold RHR A Ex's Bypass Valve E12-F048A Control Switch in

........... . .. CLOSE until valve is closed, air.

STANDAAD: Panel indication (green indicating lamp)

Valve posit f on meter indication j CowwtNTS: This step may be performed simultaneously with the previous step.

tw. att.

PEnroRMANCE STEP: Take RHR A Test Valve to Suppression Pocl E12-FC24A Control

....$.......... Switch to OPEN.

Ot17.

STANoARD: Panel indication (red indicating lamp) l l

COMMENTS:

, D4. alt.

PERroRMANCE STEP: Throttle open RHR A Hx's Outlet Valve F.12-F003A.

.....S............

Ot11 STANDAAo: Panel indications (red / green indicating lamps) approximately 6900-7100 gpm flow on pump flow meter Valve position meter iridication M NTS: gl2.F064 (Hin flow valve) will close during this step (or previous step). Operator may verbalize this. ,,, ,,,,,,,,,,,,,,,,

IM. alt.

TERMINATING Cuts:

l l

l PW P ks. 82 U Rev. 3/ U 2050340101 5 n %, p., 4 3r PERFORMANCE INFORMATION h0TE: Critical steps denoted with a *C*. failure to meet the statunards for this Stee constitutes raflure. sequence is assmed miess denoted in the e-es'. - '

PEnr0RMANCE STEP: Honitor Suppression Pool Cooling Mode for proper mir.

operation. -

STANDARD:

Flov 6900-7100 gpa, Amps 110 Amps, Temperature o < 120' F.

Without Error COMMENT $:

tvr. Inti.

PERFORMANCE STEP:

Ctli.

STANDAR0:

COMMENTS:

I GA. Ivif.

PERFORMANCE STEP:

Ot!T.

STANDAAO:

COMMENTS:

Dr. IMIT.

PERFORMANCE STEP:

OtJT.

STANDAR0:

COM4ENTS:

64.. IMIT.

PERFORMANCE STEP:

Otli.

5T AICARD:

CoweENTS:

OK. Ik!T.

TERMINATING CUES:

RHR Loop A in Suppression Pool Cooling Hode from Standby Readiness.

I m m. w x w . 1:en i

JPN k o ,

2050340101 5 5 .

Page of (LAST)

VERIFICATION OF COMPLETION

. 1 Operator _ Evaluetor l

$$N Date j License: R0 SR0 l

Nuoter of Attempts '"

l l

Result: C SATISFACTORY C UNSATISFACTORY SCTE: An ' Unsatisfactory

• requitas Comment and will requite subsequent j tenedial training, j l

)

COMMENTS / FEED 8ACK l

m.

l

~

tr: Aster's sfpwture air,

n-T,=um - nur

_ m, SYSTE V WAL <TH90 UGH "ES" PLAN PAGE I of I .

SYSTEM E12 ,

M NO. 2050340101 Startup Suppression Pool Cooling from Standby Readiness TOPIC / DESCRIPTION: .

State the maximum average GIST!> 1 u 219000 Al.01 utDc 4.0/4.0 temoerature of an Operable Suppression Pool in Op. Con. 1.

mse: 90 F.

1 69&ltHOTS: T.S. 3.6.3.1 i

l 1

2 a 219000 Al.01 utpc 4.0/4.0 If the plant were operating at 100:

31571>

90wer coerations and the Suporession Pool reached 110 0 F., what actions would the operator take?

Place the Reactor Mode Switch in the Shutdown Position and operate at least wse:

one RHR Loop in the Suppression Pool Cooling Mode.

peg n afcu oTs: T.S. 3.6.3.l 203000 aISTION 3 p A4.03 uroc 3.4/3.4 What would the consecuences be to _

the RHR A System if Test Valve to Suppression E12-F024A were opened prior to startinR the RHR A Pump? Explain.

m5e: Vaterhausser - drain higher elevation RHR piping to Suppression Pool.

e PE90E/CMOTS: _

OM34: 50I-E12 Page: 8 Rev.: 4

2. Por Containment Spray Loop B: -

a. Place CNTMT SPRAY B RI DU PRESS BYP control switch, .

1E12A-S76, on Div 2 Auxiliary Relay Panel (RHR B&C),

1H13-P618, in BYPASS only when directed by the following instructions:

1) PEI-D23-1

~ '~

2) PEI-D23-2

3) PEI-M51/N56

b. Arm and depress CNTNT SPRAY B KANUAL INITIATION button, 1E12-S635, for 35 seconds.

c. Verify Containment Spray Automatic Initiation.

d. If CNTMT SPRAY B HI DV PRESS BYP control switch, 1E12A-S76 on P618 has been placed in BYPASS, place CNTNT SPRAY B BI DV PRESS BYP control switch in NOPRAL.

3. Operate Containment spray per System Operation Section of instruction.

4.7 Suppression Pool Cooling from Standby Readiness <F01460) <P01579)

NOTE: All controls for this sectio 3 are located on ECCS Bench-board , 1813-P601.

NOTE + Suppression Pool Cooling cannot be initiated for a loop that in in Containment Spray Mode.

1. Manually startup Emergency Service Vater System Loop A(B) from Standby Readiness pet SOI-P45.

2. Manually startup Emergency closed Cooling System Loop A(B) from Standby Readiness per S01-P42. .

3. Take RER PUMP A(B),1E12-C002A(B), control switch to START.

4. Hold RRR A(B) HX'S OUILET VALVE, 1E12-F003A(B), control switch in CLOSE until valve position is 4% to 6% open.

5. Hold RER A(B) HX'S BTPASS VALVE, 1E12-F048A(B), control switch in CLOSE until the valve is closed.

6. Take RER A(B) TEST VALVE TO SUPR POOL, IE12-F024A(B), control switch to OPEN.

7. Throttle open RHR A(B) EX'S OUTLET VALVE,1E12-P003A(B), until RER A(B) PUMP FLOV,1E12-R603A(B), is 6900-7100 gps.

0M3A 501-512 l Pages f Rev.: 4 ,

8. Operate suppr'ession pool cooling per System Operation Section of instruction. .

4.8 RER A(B) Flush in Preparation for Shutdown Cooling (F01439) -

NOTE: This instruction should be conducted immediately prior tc-  !

commencing Shutdown Cooling Varmup and Initiation. Any l significant delay in the Vara Up and Initiation of Shut- '

down Cooling Flov section vill result in degradation of the RHR laop vater purity.. ,,

NOTE: All controls for this section are located on ECCS '

Bench- l board, 1H13-P601, unless otherwise noted.

l. Manually startup Emergency Service Vater System Loop A(B) l from Standby Readiness per SOI-P45. .l

2. Manually startup Emergency Closed Cooling Systea Loop A(B) from Standby Readiness per SOI-P42.

3. Place RHR A(B) OUT OF SERVICE switch, 1E12A-543t(B), in IHOP.

4. RHR A(B) Loop flush is not required provided bot.h the following conditions are met:

a. The RHR Loop to be operated han been ?perated in Shutdown Cooling within the last 10 days.

b. The Shutdown Cooling Loop flovpath has been main-tained filled and vented within the last 10 days.

5. If one Loop of RHR is in Shutdovn Cooling and it is  ;

desired to put another loop in Shutdown Cooling, prior to j flushing the second loop, verify RHR A(B) SHUTDOVN CLG l SUCT, IE12-F006A(B), of the loop to be flushed is closed to prevent draining the Reactor Vessel. j 4.8.1 Flush of RHR Loop A(B) when in Standby Readiness Mode.

1. Plush RER Loop with Suppression Pool vater as follows:

a. Hold RHR A(B) HX'S BYPASS VALVE,1E12-PO48A(B), con-trol switch in CLOSE until the valve is closed.

b. Hold RER A(B) HX'S OLTTLET VALVE, IE12-F003A(B), cor.-

trol switch in CLOSE until the valve is 4% to 6%

open.

c. Take RHR PUHP A(B), IE12-C002A(B), control switch to START.

d. Take RHR A(B) TEST VALVE TO SUPR POOL, 1E12-F024A(B),

control switch to OPEN.

-s --

r , e gw-v r-- w-.~'2- ,y-- = rm*--r.---we..-,,-+.,~,--,w-, rm4.+o- ,m-, . - - - . .e,-- , - - . --e.i.-,,em.r -,---,---en-* .--v.--

System V lkthrough Fcilow-up Questions Documentation I Question Derivation (can be completed af ter examination): 1 Simulator Evaluation Deficiency (identify) -

l Topic Area Evaluation: 1. Pstformance Measure . l

2. Question Number I Question (to be completed during exam):

Response (to be completed during exas):

~

l Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number Question (to be completed during exam):

Response (to be completed during exas):

l i

l Question Derivation (can be completed after examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number Question (to be completed during exam):

I l

l Response (to be completed during exam):

i t

M Ms. 8245 REY. Jtes 4

PERRY NUCLEAR POWER PLANT .

JOB PERFORMANCE MEASURE WORKSHEET JPH No. NRC-01 new. O page i or 4 Task No. 22900$PPST new, O Task

Description:

Securine an Ooeratine H Recombiner.

SRO = 3.8 r/A

Reference:

_223001 A2.04 KA Value: RO = 3.7 (NUREG-1123)

@ itABLE METH00 0F fESTINC Sisulate performance X Actual performance C1ssaroos Simulator In Plant X Conttol noon l Time for completion 15 minutes (approximate)

PittrAAED 8f:

USNRC

/

Ornleet hte i REVIEntD Bf:

\\ l ltntMtional TecMelogist Date APPfl0YED 8f:

/

Ucense tralr. Lng Instutor Dett m

Pwr m. 82aw new. Jia

.JPW No. NRC-01 page 2 or 4 Operator Evoluetor ,

SSN ---

• Dete License: RO O sao READ TO THE OPERATOR 1 will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues, when you complete the task sucesssfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

Div. I Hydrogen Recombiner is in operar. ion during a LOCA.

(lH51-P094 located in Control Complex 620' elevation) l I

TASK STANDARDS Simulate securing H2recombiner l

l REQUIRED MATERIALS:

PEI-M51/M56, Rev. O, Hydrogen Control (i.e. See page 15)

PEI-M51/M56, Rev. 3, Page 15,'fection 6.3, Combustible' Gas Control System ard Hydrogen Ignite c (Unit 1)

GEERAL

REFERENCES:

PEI-M51/M56 SOI-M51/M56 INITIATING CtKS:

Primary Containment 2H concentration is 5.5% ara is increasing steadily.

US directs SO to shutdown the Recombiner.

(See NOTE in SOI-M51/M56, Sect. 6.3 requiring H2 recombiner shutdown at an H 2 concentration of 6%) __

y--y-.,w, ,y - - - 3y-w.-, ,- ,- -y,-, ,--- ,

,,._- , - - - - - . . - - - - , _ , - - _ _ - - .e3- - - - . - --y -9 , , , , - , - . - .

1 Met us. Item Rev. We ,

JPN Me, NRC-01 Pege 3 Cf 4 PERFORMANCE INFORMATION NDrt: Critical steps denoteuf with e T*. PaAJure to aset the stanserde for this Jtes eenetitutes tsJiute. Sequence Ja esow imless denotes Ja the 'Osmaants'. ' ,

PtwasseAMet sitP: Decrease "PWR ADJ" pot.entiometer to zero (000) at .

..................... IH51-P094. ,

all.

STANDAno: Candidate verbalizes that potentiometer knob is turned to obtain a scale reading of zero (000).

caseENTs: None.

M. MT.

PgRronmarect STEP: "PWR OUT" switch is placed in "0FF" at lH51-P094.

..........C...........

alt.

STANDAmo: Candidate indicates that switch must be placed in OFF.

CobedENTS: None M. NT. ,

1 PtarommAMet STEP: Verify red status light on the switch control plate is OFF at lH51-P094.

air.

STANDARO: Candidate verbalizes this verification.

CopesENT5- I l

.................... j M. MT. 1 1

PtwommAMet sitP: j O!!.

STAfeAmO:

caseENTS:

M. Mf.

PtAfonMAMet STEP:

STANDAAO:

ColeqENTS:

M. MT.

ftnMINATIMc cuts: H2 Recombiner secured.

e

. . - . , -_,.__my, ,_,._--_,_..,_-,._v..,_-,--e,r,,m,_,,y.,,..m..,,,ev,,.,m,_,.mym. .,.r,. e.,w., _,_ -,._<

l l

l w no. s24x m. um JPN No. NRC-01 _ _ _ _

e.g. 4 or 4 (LAST) yJAlfjCATION OF COMPLETION ,

Operator Evoluetor SSN - Date License: C R,0 SRO I l

' l Number of Attempts l

I Result: SATISFACTORY UN$AT!!TACTORY I

MW: M *t.hsetisfactory* requires Comment sixt alli tentate subsequent remedial training. \

)

i 1

j COMMENTS /FEEDSACX

{

1 l

l I

/

tralmtor's sivuture o,te

?

i t

nur ,aun ma nua

[

,,,, ,. m , SYS"EN WAL <"H9OUGH "ES" P'_AN 2 l

PAE I of_

H, Recombiner l SYSTEM I M f(). NRC-01 Securing an Operatina H. 'Recombiner 1 TCPIC/DESCRIPTI(N: .

i

)

i l

223001 Hov long does it take to contpletely I o GEN 7 mtpc 3. 7 / 3. 8 :

3157p

.e n v r,m a n ri u n v~ m the H Recombiner?

ange: Six hours. i l

l

)

m;m. SOI-MS1/56 l

223001 utDc 3. 5 / 3. 6 If Hydrogen concentration in the ozsta 2 o A4.06 Con t a in:nent reaches 6%, why must the operator shutdown the H, Recombiner?

ANSWOt: Shutdown the H Recombiner to ereclude Recombiner damace.

l l

IIE3P06Elt34(XT5 223001 m m 3.6/3.7 Explain how flow is established

. o GEN 4 REsip 3 and maintained in the H. Recombiner.

ange: Natural Conveetion.

--- - - - - . , . , - , - - - - - - , , , - .- - , - - - , - , - ,, ---.-,g .-..- w

- mm -

. m, SYS7EV WA' CF 90UG "ES" P _A 4 )

B, Recombiner PACE 2 of 2 ,

SYSTEM

• I M M), NRC-01 ,

Securing an Operatine H Reecehiner TTIC/DESCRIPTICH: .

223001 GEST p 4 .o GEN 4 mtpc 3. 6 / 3. 7_ : Exelain the banic oneratinn of the H, Recombiner.

4 I

g. Heaters will heat the air causine the B. to cothine with n to make water. _

l 1

1 ESP 06EICD*OT5 223001 g GEN 8 utDc 3. 7 / 3. 5 Concerning the CGC System H., Analyzers, gest a 5 what does the Blue Permissive light indication to the operator when it I

illuminates?

a: It indicates that the system has purged and valid data is being transmitted to the recorders.

- ESP 06EICD*OT5 223001 GEST p 6

a GEN 7 mipc3.7/3.8 : State the areas that can be sampled by the H Analyzers,

m. Dryvell Head Region; Upper Dryvell Area: Containment Dome Region; Surytession Pool Area.

K3P06E/CD*OT3

__ _ . _. - - - . - _ _.,_....,7. . _. ... . .. , r-, y _,. _.

TEMP GI.

OM3A MI-M51/56 PME d W { Page: 15 Rev.: 3 .

(~

'6.3 Rydrogen RecombinergB) Shutdavn ', #

• • • • • • • • • • • • • e********************************************************** ,

CAtJTION The Hydrogen Recombiners must be shutdown if hydrogen concentration reaches 6% to preclude recombiner damage. .

1. Decrease PVR ADJ potentiometer to zero (000) at 1E51-P094(P095).

2. Piace the PVR O'Jr SV in OFF and verify the red status light on the switch control plate is 0FF at 1851-P094(P095).

3. Perform independent verification of the required components.

6.4 Bydroge. Igniter Shutdown

...**...e..***.**.....................***.**.******.*****..*********

CAtJTION I The Hydrogen Igniter System shall only be operated as directed by g .,,

PEI-M51/56, Hydrogen Control, or as required per applicable SVI's.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 1

1. Place the DIV 1(0) B IGNITER, IM56-S1(S2) in 0FF.

2 2 Perform independent verification of the required cesponents.

~5

. Backuo Hydrogen p rge Shutdovn

1. Play COM3 GAS DV PURGE OTBD ISOL, IM51-F110, keylock switch to CLOSE.

2. Take COMB GAS DV PURGE INBD ISOL VI.V,1M51-F0H), 7 trol avitch to CLOSS.

3. Perform Backup Purge valve closure verificatica per SVI-M51-T1209.

4 m,, _u_

System Valkthrough FIllow-up Questions Documentation Question Derivation (can be completed af ter examination):

• Simulator Evaluation Deficiency (identify) ,

Topic Aron Evaluation: 1. Furformance Measure

2. Question Number -

Question (to be completed during exas): .

Response (to be completed during ext.m):

Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number ,

Question (to be completed during exas): l Response (to be completed during exam):

Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluatior? 1. Performance Measure

2. Question Number 1

duestion (to be completed dtiring exam):

l l

1

4sponse (to be completed during exam)

l P W Ne, S W E Y, }/88 1

PERRY NUCLEAR POWER [LANT -

JOB PERFORMANCE MEASURE WORKSHEET apu no. 2640210101 new. O pg,ge 1 or 5 Task so. , 2640210101 pey, O Task

Description:

Parallel DG and Bus with Preferred or Alternate Source Trans fer EH il to Preferred Source from Div. I Diesel Generator (Remote).

KtA

Reference:

264000 A4.04 ( 3. 7) A4.05 ( 3.6)

(MJREG-1123)

APPLIEARLE METHob of TESf? g; Simulate performance Actual performance I Classroos _ Simulator I In-Flent Control Room 1

Time for completion 20 minutes (approximate) l l

PRUARED BY: i

% E . M. ~ i hhe

. m.

l afvitato st: Q l

~ 5. 4 i (.  !

Dutut2&m1 rscnnelagne ..e 0 , f/gy LAN18e IT81nitt UntMtut ' / Dett l

a 1

P W m . G43A Rev. Jiu yw me. 2640210101 Page 2 or 5 Operator Kvaluetor ,

$$N Date License: R0 SA0 READ TO T>f QPERATOR

! will explain the initial conditions. shich stop(s) to slaviate or discuss, and provide initiating cusa. When y J complete the task successfully, the objective for this job performance seasure vill be satisfied.

INITIAL CONDITIONS:

Div. I Diesel Generator carrying Bus EHil - Diesel Generator c trol from Control Room.

TASK STANQABQS Bus EHil Transferred to Preferred Source from Div. I Diesel Generator IAW SOI-R43 (Div. 1)

REQUIRED HA,1EEIAL$:

S01-R43 (Div. 1) ,

Plant Comunicatiu . Systems j l

l fgNERAL

REFERENCES:

SOI-R43 (Div. 1)

INITIATItq;;jgS:

US orders Ma to transfer Bus EHil t.o its Prefet ted Sourr a from Div. I Diesel Generator (Remotely \ AW SOI-R43 (Div. 1){ Sect. 5.3)

' FwP no. 82O Asv. IlJ I

.ien me. 2640210101 page 3 er 5 l l

i PERFORMANCE INFORMATION -

w it: Critical steps ennoted with a *C'. Tellutt to meet the stederne for this itee constitutes i failate. Sequence is assuaed uniess donoted in the

• Comments'. }

PERFORMANCE STEP: Place Synch Sel Switch in THI position. .

......C.,,,,,,,,,,

all.

$fANCAA0: Panel Indication, sync scope begins rotation, and syne lights flash on and off COMMENTS: Diesel voltage indicated, ,

Ont. Inst.

PEAroANANCE sitP: Adjust Di2sel Generator Voltage Regulator to match EHil

...C,,,,,,,,,,,,, volts incoming (R22-R02iA) and Running (R22-R022A).

air.

sTANDAAD: Panel Indication COMMENTS: Voltage regulator adjusts incoming voltage reading Or. : nit.

=

PtaromwANCE STEP: Adjust Diesel Generator Governor such that Sychroscope

. .G...... ,,, ,, (R43-R022A) is moving slowly in the FAST direc* ion.

alt.

STANcAmo: Panel indication on R43-R022A ,

COMMENTS:

tva. *rt.

4.a.===:

PERFORMANCE STEP: With Synchroscope R43-R022A moving slow in the FAST

.....C,,,,,,,,,,, direction at approximately 5 min to 12-o' clock position, air. Close Breaker EH1114, Preferred Source Breaker.

STAxoAno: Panel Indications red lamp on breaker illuminat.es, sync scop'-

needle stops at 12-o' clock posir. ion.

l COMMENTS: Indicated Generator Load will decrease.

DA . >11.

)

etaroRMANet stre: Place Synch Sel Switch to 0FF position.

.................... 1 air. l

$TANDAAO: Panel indications COMMENTS: Synch lights go of f ,

3

)

Evnt. 511.

TERMINATING CUES

• l I

twP w. $NB new. JU

pw we. 2640210101 p.g. 4 or 5 PERFORMANCE INFORMATION .

M TE: Critical steps denoted with e *b'*. Tallure to neet the standards for thia itO constitutes~

fsflure. Sequence is sssumed talass denoted in the ' Comments'.

PERr0RMANCE STEP: Adjust Diesel Generator Governor to achieve ~100 KW on .

..................... Kilowatts indication R43-R013A.

Otit.

STANoAAo: Panel it.dication on R43-R013A C0m*.sc. s :

Dr. EMIT.

PEAroRMaNCE STEP: Adjust Diesel Generator Voltage Itegulator to achieve 90 to 100 KVAR's on indicator R43-R012A.

Otli.

STANDARD: Panel indication on R43-R012A COMMENTS:

Ot. IN!T.

PERFCRMANCE STEP: Take Breaker ZH1102, Diesel Generator Breaker to TRIP.

......C...... . ..

Orli.

STAnoARo: Panel indication (green lamp)

COMMENTS:

O K . ! Nil.

PERFORMANCt STEP: Shutdown Div. I Diesel Generator to desired configuration.

Ot!T.

STANDARD: Recognize requirement for this step.

C0w4ENTS: This step is verbalized.

Nr. IMIT.

1 PEAFORMANCE STEP:

Ot!T.

STANDAAO:

COMMENTS:

Em. Inir.

TERMINATImr. ;;tts- Bus EHil powered from Preferred Source with Diesel Generator Breaker open.

. .~ ~ = - .. ..

I M* No. G4X Rev. 3/08 JPN No. 2640210101 p.,, 5 or 5 g337)

VERIFICATION OF COMPLETION Operator Evoluetor SSN Date License: R0 SRO Number of Attempts Result: SATISFACTORY C UNSATISTACTORY NOM: M *Lknatisfactory* TrQuites Canarnt and will requite subsequent teardial training.

CCH4ENTS/ FEEDBACK MM8hSWe

%W G

I t,sla tor s si,neture mer

+ _

PUtRY MUCtf AR POWER PLANT

_ m, SYSTEM WA _(TF ROUGH TEST OLAN '

• R43 PACE 1 cf 2 SYSTEM

,PH NO. 2640210toi TOPIC / DESCRIPTION: Parallel Diesel Generator and Bus with Preferred or Alternate Source -

Trans fer EHil to Preferred Soutee from Div. I Diemel Genernent 264000 gxstry i . u A4.04 urzg 3. 7 / 3. 7 What is the minimum limit on generator reduction when synchronized to the grid and why is this limit required?

w 3:

100 KV - to preven: a generator reverse power condition.

ICiPOGIC34ei3:

264000 l 2 u A4.04 ut:< 3. 7 / 3. 7 If the syne scone was not ooerable.

GIstI>

What indic at ion (s) vould you use to carallel with bus EM-12?

we: Wite lights of f when in phase.

(

1 ESPONSE/N15: l m r-264000 CEN-5 ut:c 3.4/4.1 , wh,t would be the Diesel Generator aKst!ta 3 u test frecuency if there had been two failures in the last twenty valid tests?

SRO ONLY meot: Once per saven days (T .S . Table 4.8.1. t ,2- 1)

ESPWiE/CD80tT5

- - , , , - , , , - ---,w- - , - - - - - - - --e,, . , ..--. n-- n------ - - ~ - , - - - , - - - . ,- ,e-, ,---ww-,e- - - - --..,. -

I l

1 PERRY NUCLEAR P0 set PLANT

_ , , , SYS~EN WALKTHROUGF "EST P _AN '

. PAE 2 of 2 SYSTEM R43 W NO. 2640210101 TOPICl0ESCRIPTION: Parallel Diesel Generator and Bus with Preferred or Alternate l Source - Trans fer EH i l to Pre ferred Faurce from Div. I Diesel (

Generator.

264000 gzsigm 4 u GEN-5 MIINC 3.4 /4.1 : How can the Diesel Generator test frecuency be increased from 7 dava te once eer 31 davn?

SRO ONLY

m. The associated test frequency shall be maintained until seven consecutive failure free demands have been oer formed and the nue),.gg, of f ailures in the last 20 valid demands has been reduced to less than or equal to one. (Note to T.S. Table 4.8.l.1.2-;,)

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0H3At 50I-R43(Div 1)

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b. TE21 - If Brkr EB1115; ALTN PREFERRED SOURCE BRKR,.is.

closed. .

5. Adjust DIESEL GEN VOLTAGE RGLTR to natch BUS E811 VOLTS, INCOMING, 1R22-R021A, and RUNNING, 1R22-R022A.

6. Adjust DIESEL GEN GOVERNOR such that SYNCEROSCOPE, IR43-R022A, is moving slow in the FAST direction.

7. Vith SYNCHR0 SCOPE, 1R43-R022A, moving slov in the FAST direction, at approximately the 5 minutes to 12 o' clock position, perform the following in succession:

a. Take Brkr EH1102; DIESEL GEN BRKR, to CLOSE.

b. Take DIESEL GEN GO'JERNOR to RAISE to achieve approximately 100 KV on KILOVATTS, 1R43-R013A.

8. Place SYNC SEL SVITCH in OFF.

9. If it is desired to operate the Diesel generator in parallel with the grid, (for example, while performing loaded runs) exit this section and operate per the Operations in Parallel 9ith the Grid section.

( 10. Adjust Generator load with the DIESEL CEN GOVERNOR to achieve the approximate loading of Bus EH11 (determined from the Bus EH11 Load Rating attachment) as indicated by KILOVATTS, 1R43-R013A.

11. Adjust KILOVA'tS,1R43-R012A, using DIESEL GEN VOLTAGE RGLTR as necessary to obtain a .98 lagging power factor such that KILOVARS = KILOVATTS x (0.2).

12. Open the applicable closed breaker:

a. Brkr EH1112,; PREFERRED SOURCE ARKR, or,

b. Brkr 181115; ALTN PREFERRED MURCE BRKR.

5.3 Transferring Bus EH11 to the Preferred or Altn Preferred Source from the Diesel Generator (Remote)

NOTE: This section may be performed if under Mechanical Governor Control, operating the DIESEL GEN GOVERNOR ac directed by Diesel Operations Using Mechanical Governor Control.

1. If the Diesel Generator is being controlled locally, perform Transferring Control to the Control Room (Remote Control).

POTE: The following steps are performed at 1513-P877. -

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OM3A 50I-R43(Div 1)

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2. Perform one of the following as applicable:

a. If placing Bus 1811 on the Altn Preferred Source, place SYNC SEL SVITCH in TH21, or, )'

b. If placing Bus EH11 on the Preferred Source, place STNC SEL SVITCH in THl.

3. Adjust DIESEL GEN VOLTAGE RGLTR to match BUS EH11 VOLTS, INCOMING,1R22-R021A, and RUNNING, '1R22-R022A. t

4. Adjust DIESEL GEN GOVERNOR such that STNCHROSCOPE,1R43-R022A, is moving slow in the FAST direction.

5. Vith SYNCHROSCOPE, 1R43-R022A, moving slov in the FAST direction, at approximately the 5 minutes to 12 o' clock position, perform one of the following e.s applicable:

NOTE:

Vhen the Preferred or Alternate Preferred Source i Breaker is closed, the indicated Generator load vill decrease unless using Mechanical Governor Control.

a. If placing Bus EH11 on the Alternate Preferred Source, close Brkr EH1115; ALTN PREFERRED SOURCE BRKR, or, '

b. If placing Bus EH11 on the Preferred Source, close Erkr j

{ E31114; PREFERRED SOURCE BRKR. '

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6. Place SYNC SEL SVITCH in OFF.

7. If it is desired to operate the Diesel generator in parallel i vith the grid, (for example, while performing loaded runs) exit this section and operate per the Operations in Parallel with the Grid section.

8. Adjust DIESEL GEN GOVERNOR to achieve 100 KV on KILOVAITS, 1R43-1013A. . .

Adjust DIESEL GEN VOLTAGE RGLTR to achieve 90 to 100 KVAR on KILOVARS, 1R43-R012A.

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10. Take Brkr EH1102; DIESEL GEN BRXR, to TRIP.

11. Shutdown Div 1 Diesel Generator to the desired configuration.

a. If operation was under Mechanical Governor control, return the Diesel Generator to normal per Recovery from Mechanical Governor control.

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System Valkthrough F;llow-up Questions Documentation Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

• Topic Area Evaluation: 1. Performance Measure

2. Question Number -

Question (to be completed during exas):

Response (to be completed during exas):

Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure

2. Question Number Question (to be completed during exas):

Response (to be completed during exas):

Question Derivation (can be completed af ter examination):

Simulator Evaluation Deficiency (identify)

Topic Area Evaluation: 1. Performance Measure ,

2. Question Number Question (to be completed during exas): __,

Response (to be completed daring exas):

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