ML20198C038
| ML20198C038 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/24/1991 |
| From: | Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AGM-NUC-91-096, AGM-NUC-91-96, NUDOCS 9106280020 | |
| Download: ML20198C038 (35) | |
Text
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' isuun SACRAMENTO MUNICIPAL UTILITY DISTRICT P
O. Box 15830. See ramento C A 95852-1830,1916) 452 3211 AN E L EC T RIC SYS TUd SLHVING Tiil HE AR r Of C ALif 0HNIA AGM/NUC 91-096 June 24, 1991 U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk W shington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 RANCHO SECO OPERATOR TRAINING PROGRAM Attention:
Seymour Weiss In accordance with your letter dated June 5,
1991, the District hereby provides Revision 1 to Appendix A,
and Revision 2 to Appendix B, of the proposed Rancho Seco Operator Training Program (RSOTP).
These revisions add training requirements regarding maintaining mechanical components in a
non-degraded
- status, responding to a loss of offsite power, and controlling radiological effluents.
The revisions to these appendices also delete any reference to the Permanently Defueled Technical Specifications (PA 182).
All activities and procedures will be performed in accordance with the Technical Specifications applicable in the defueled condition.
Members of your staff with questions requiring additional information or clarification may contact Steve Redeker at (916) 452-3211, extension 4699.
Sincerely, jffYu2bt !
7,.
3 Dan R.
Keuter Assistant General Manager Nuclear cc:
S.
W.
Brown, NRC, Washington, DC J.
B. Martin, NRC, Walnut Creek C.
Myers, NRC, Rancho Seco 9106?90020 910624 PDR ADOCK 05000312
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DISTRICT HEADOUARTERS O 6201 S Street, Sacramento CA 95817-1899
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ATTACHMENT A PART 55-OPEllATOltS' I.lCENSES: SUHPAllT E WittlTEN EX\\MINATIONS AND OPEllATING TESTS 55.41 WitITIEN EXAMINATION: O PEll ATOltS.
REQUESTED EXEMPTION SECTION Partial Exemption: Testing is limited to those c4mtrol and safety (b)(7)
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safety systems, including instrumertation, signals, interlocks, failure modes, and automatic and manual features.
Partial Exemption: Testing is limited to those emergency systems (b)(8)
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radiological efHuents.
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power, radiological effluents, and maintenance of components in a non-degraded status.
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MMMMI ATTACIIMENT A l'AltT 55-OPEllATOllS' I.lCENSES: SUllPAllT E-WRIITEN EXAhllNATIONS AND OPEl{ATING TESTS 55.45 OPEllATING TFXTS.
REOUESTED EXEMPTION SECTION (a)(1)
Perform pre.startup procedures for the facility, Total Exemption: Since the nuclear fuel shall remain in the Spent Fuel including operating of those controls associated with Pool, testing of these sections is inapplicabic.
plant equipment that could affect reactivity.
l (a)(2)
Manipulate the console controls as required to operate l
the facility between shutdown and designated power j
levels.
l l
Partial Exemptior. Testing limited to those annunciators and
(
(a)(3)
Identify annunciators and condition-indicati.ig signals instrumentation spie s associated with fuel in the SFP, loss of off-l and perform appropriate remedial actions where site power, and radiologLal emuents.
appropriate.
(a)(4)
Identify the instrumentation systems and the significance of facility instrument readings.
8
ATTACIIMENT A PAllT 55-OPEllATOltS' I.lCENSES: StillPAltT E WillTI'EN EXAMINATIONS AND OPEllATING TESTS 55..t5 OPEftATING TESTS.
RVf 1UESTED EXEMPTION SECrlON Partial Exemption: Te<,ing limited to those operations related to the (a)(5)
Observe and safety control the operating behavior defueled ctmdition, ftt.1in the SFP and maintenance of comp (ments in characteristics of the facility.
(a)(6)
Perform amtrol manipulations required to obtain a non-degraded star s.
a desired operating results during normal, abnormal, and emergency situations.
Partial Exemption: Testing is limited to those sptems which impact the (a)(7)
Safely operate the facility's heat remosal systems, including primaty coolant, emergency coolant, and maintenance of a safe shutdown cimdition in the SFP and those decay heat removal systems, and identify the relations auxiliary systems which could affect release of radioactive materials to the em-ironment.
of the proper operation of these systems to the operation of the facility.
(a)(S)
Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the em ironment.
(a)(10)
Demonstrate knowledge of significant radiation Partial Exemption: Testing in this section limited to those normal and abnormal radiation hazards associated with maintaining the nuclear hazards, including permissible levels in excess of those fuel in the SFP, maintaining the plant in a defueled condition, and authorized. and ability to perform other procedures to reduce excessive levels of radiation and to guard maintaining com[xments in a non-degraded status.
against personnel exposure 9
PART 55-OPERATORS' I.ICENSES: SUllPART E. WRITTEN EXAMINATIONS AND OPERATING TESTS ATTACIIMENT A 5 5.-85 OPERATING TFKTS.
SECTION REQUESTED EXEMPTION i
l (b)
Implementation-(t) Administration. The operating Defueled Condition Comnliance: Operating tests to be administered in test will be administered in a plant walkthrough and a plant walk-through and limited in scope to duties applicable to a in either--
defueled condition, with fuel in the SFP, and the maintenance of components in a non-degraded status.
i 1
(b)(1)-(5)
A simulation facility which the Commission has Total Exemption: SMUD letter AGM/NUC 89-176 dated Dec.12.
approved for use after application has been made by 1989, was sent to the NRC requesting exemption from the the facility licensee, or requirements of this section and the exemption was granted by the A simulation facility consisting solely of a plant-NRC by letter dated May 16,1990.
referenced simulator which has been certified to the Commission by the facility licensee.
I 10 4
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ATTAC11 MENT A PART 55-OPERATORS' I,ICENSES: SUltPART l' I.ICENSES 55.53 CONDITIONS OF I.ICENSE&
REOUESTED EXEMPTION SECTION If a licensee has not been actively performing the Partial Exemption: Based on the nuclear fuct remaining in the SFP, functions of an operator or senior operator. the exemption from the requirements of an operating facility is requested.
(e) licensee may not resume activities authorized by a license issued under this part except as permitted by paragraph (f) of this section. To maintain active The requirement shall be that the licensee shall actively perform the status, the licensee shall actively perform the functions functior.s of a senior operator or operator consistent with a defueled of an operator or senior operator on a minimum of condition, fuct in the SFP, and maintenance of components in a non-seven 8-hour or five 12-hour shifts per calendar degraded status for a minimum of four hours per calendar quarter in quarter. For test and research reactors, the licensee order to maintain an active status.
shall actively perform the functions of an operator or senior operator for a minimum of four hours per calendar quarter.
Partial Exemption; Based on the nuclear fuel remaining in the SFP, (f)
If paragraph (e) of this section is not met, before exemption from the requirements of an operating facility is requested.
resumption of functions authorized by a license issued under this part, an authorimi representative of the facility licensee shall certify the following:
(1)
That the qualifications and status of the licensee are De requirement for the completion of one shift under the direction of an operator or a senior operator is required to regain an active current and valid; and (f)(2)
That the licensee has completed a minimum of 40 operator status.
hours of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned. The 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> must have included a complete tour of the plant and all required shift turnover procedures. For senior operators limited to fuel handling under paragraph (c) of this section, one shift must have been completed. For test and research reactors, a minimum of siy hours must have been completed.
I1
~
4 PART 55-OPERATOllS' l.ICENSES: SUllPART F-I.lCENSES ATTACHMENT A 55.59 H EOUAI.lFICATION.
SECTION REOUESTED EXEMPTION (a)
Requalification requirements. Each licensee shall-t (a)(2)
Pass a comprehensive requalification written examination and an annual operating test.
(a)(2)(i)
The written examination will sample the items Exemptions shall be the same as those requested in part 55.41 and specified in 55.41 and 55A3 of this part, to the extent 55.43.
applicable to the facility, the licensee, and any
' f limitation of the license under 55.53(c) of this part.
(a)(2)(ii)
De operating test will require the operator or senior Exemptions shall be the same as those requested in part.55.45(a)(2) operator to demonstrate an understanding of and the through (13) inclusive.
ability to perform the actions necessary to accomplish a comprehensive sample of items specified in 55.45(a)
(2) through (13) inclusive to the extent applicable to the facility.
j 12
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I ATTACHMENT A PAltT 55 OPEllATOltS' l.lCENSES: SUllPART F-f.ICENSf3 55.59 REOUAI.IFICATION.
REOUESTED EXEMPTION SECTION Partial Exemption: Training in this sectio.1 to be limited to the (c)(2)(ii)
General and specific plant operating characteristics.
general and specific plant defueled characteristia.
Partial Exemption: Training in this sectian to 1.e limited to the (e)(2)(iii)
Plant instrumentation and control systems.
shutdown instrumentation and control systerrt and that associated with a loss of off. site power.
Partial Exemption: Training in this section to be limited to the g 42)(iv)
Plant protection systems.
shutdown protection systems associated with the SFP, k>ss of off-site power and radiological effluents.
Partial Exemption: Training in this section to be limited to the (c)(2)(v)
Engineered safety systems.
engineered safety sptems required with fuel in the SFP, for k>ss of off-site power and radiological effluents.
(c)(2)(vi)
Normal, abnormal, and emergency operating Partial Exemption:
Training in this section to be limited to administrative, normal, abnormal and emergency procedures apphcable procedures.
to fuel in the SFP, loss of off-site power radiolocical effluents, and maintenance of components in a non-degraded status.
Partial Exemption;_ Training in this section to be limited to the (c)f 2)(viii)
Technical Specifications.
Technical Spedfications applicable in the defueled condition.
14 1
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PAltT 55-OPEllATOltS' LICENSES: SUllPART F-I.ICENSES ATTACHMENT A 55.59. ItEOUALIFICATION.
SECTION REOUESTED EXEMPTION (c)(3)(iv)
Each licensed operator and senior operator reviews the Partial Exemption: Training in this section is limited to the abnormal contents of all abnormal and emergency procedures on and emergency procedures applicable to maintaining safe storage of the a regularly scheduled basis.
fuel in the SFP, loss of off-site power and control of radiological effluents.
(c)(3)(v)
A simulator may be used in meeting the requirements Total Exemption: Total exemption was requested from the of paragraph (c)(3)(i) and (3)(ii) of this section, if it requirements of this section based upon the request for total j
reproduces the general operating characteristics of the exemption from section (b)(1)(i) and (b)(1)(ii) of part 55.45 by SMUD facility involved and the arrangement of the letter AGM!NUC 89-176 dated Dec. 12, 1989. The exemption was instrumentation and controls of the simulator is similar approved by NRC letter dated May 16,1990.
to that of the facility involved. If the simulator or simulation device is used to administer operating tests for a facility, as provided in 55.45 (b)(1), the device approved to meet the requirements of 55.45 (b)(1) l must be used for credit to be given for meeting the requirements of paragraphs (c)(3)(i) (G through AA) of this section.
(c)(4)(ii)
Written examinations which determine licensed Partial Exemption: The examination required by this section is limited operators' and senior operators' knowledge of subjects to the testing of the senior operators and operators' knowledge of covered in the requalification program and provide a subjects and procedures covered in the Defueled Operator basis for evaluating their knowledge of abnormal and Requalification Training Program.
emergerry procedures.
19
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ATTACHMENT B DEFUELED REQUALIFICATION TRAINING PROGRAh!
FOR NRC LICENSED OPERATORS REVISION 2 6/13/91 l
l
l ATI'ACHMENT B Rev. 2 DEFUELED REQUALIFICATION TRAINING PROGRAM FOR NRC LICENSED OPERATORS TABLE OF CONTENTS PAGE 1.0 PURPOSE 3
2.0 REFERENCES
3 3.0 DEFINITIONS 3
3.1 Controls 3
3.2 Examination 3
3.3 Facility 4
3.4 Operator 4
3.5 Senior Operator 4
3.6 Requalification Training Cycle 4
3.7 Shall, Should, May 4
3.8 Simulate 4
4.0 PROGRAM REQUIREMENTS 4
4.1 Schedule 4
4.2 Lectures 5
4.3 On-the-Job Training 6
4.4 Procedure Review Training 6
4.5 Other Areas of Training 6
4.6 Alternative Training Methods 7
4.7 Evaluation and Observation 7
4.8 Conditions of Licenses 9
4.9 Records and Documentation 11 4.10 Senior Operator Trainees 1I 4.11 Instructor Qualifications 11 2
4 ATTACHMENT B Rev. 2 DEFUELED REQUALIFICATION TRAINING PROGRAM FOR NRC LICENSED OPERATORS 1.0 PURPOSE The purpose of this program description is to define the training requirements for the requalification of NRC Licensed Senior Operators and Operators at the defueled Rancho Seco Nuclear Generating Station, Unit 1.
This program is established to meet the requirements of the l
applicable parts, as exempted by the NRC, of Subpart F of 10CFR55 necessary for renewal of licenses in accordance with Section 55.57 of 10 CFR 55.
This Defueled Requalification Training Program is subject to approval by the Nuclear Regulatory Commission. In accordance with 10 CFR 50.54 (i-1), no changes shall be made in this program to reduce the scope withaut prior approval by the NRC.
2.0 REFERENCES
2.1 ANSI /ANS 3.1-1978, Selection and Training of Nuclear Power Plant Personnel 2.2 10 CFR 50,-Domestic Licensing of Production and Utilization Facilities j
2.3 10 CFR 55, Operators' Licenses 2.4 ANSI /ANS 3.1-1981, American National Standard for Selection and Training of Personnel for Nuclear Power Plants l
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ATTACHMENT B Rev. 2 1
3.0 DEFINITIONS The following terms are defined for uniform interpretation of this docun ent.
3.1 Controls - When used with respect to nuclear fuel in the Spent Fuel Pool (SFP), means apparatus and mechanisms, the manipulation of which directly affects fuel movement.
3.2 Examination - A test used to measure knowledge, skills, or achievement in one or more subjects. An examination may be a written test or an operating test.
3.3 Facility - Means the Rancho Seco Nuclear Generating Station, Unit 1.
3.4 Operator - An individual licensed by the NRC who manipulates the controls of this facility. An operator is deemed to manipulate a control if the operator directs another to manipulate a control.
3.5 Senior Operator - An individual licensed by the NRC who manipulates the controls of this facility or directs the licensed activities of licensed operators on this facility.
3.6 Requalification Training Cycle - A period of time equal to one shift rotation and not to exceed 12 weeks.
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ATl'ACHMENT B Rev. 2 3.7 Shall. Should. May Shall is used to denote a requirement or commitment.
Should is used to denote a recommendation.
May indicates permission, neither a requirement nor a recommendation.
3.8 Simulate - The training /cvaluation method whereby an individual performs a walk-through of actions to be taken, using the control panel involved, discussing each step without actually operating any controls.
4.0 PROGRAM REQUIREMENTS 4.1 Schedule 4.1.1 The Defueled Requalification Training Program shall be conducted for a continuous period, not to exceed twenty-four months in duration.
4.1.2 Successive Defueled Requalification Training Programs using generally the same format and schedule shall follow the first in a continuous cycle of twenty-four month duration programs.
4.2 Lectures 4.2.1 The Defueled Requalification Training Program shall include preplanned lectures to be given throughout the twenty-tour month period.
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ATTACHMENT B Rev. 2 4.2.2 Films, video tapes, programmed instruction and other effective training aids may be used to supplement lectures and their use shall be limited to less than fifty percent of the total classroom training; however, an instructor shall be available to answer questions, lead discussions, and monitor class performance.
4.2.3 Lecture content shall take into considerntion the following:
4.2.3.1 Theory and principles of defueled operation to include reactor theory, heat transfer, fluid flow and thermodynamics.
4.2.3.2 General and specific plant defueled characteristics.
4.2.3.3 Shutdown instrumentation and control systems and that associated with a loss of off-site power and radiological effluents.
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4.2.3.4 Shutdown protection systems associated with the SFP, loss of off-site power and radiological effluents, i
4.2.3.5 Engineered safety systems required with fuel in the SFP, loss of off-site power and radiological effluents.
4 4.2.3.6
- Normal, Abnormal, Emergency Operating, and Administrative Procedures applicable to fuel in the SFP, loss of off-site power, radiological effluents and maintenance of components in a non-degraded status.
4.2.3.7 Radiation Control and Safety.
d 4.2.3.8-Technical Specifications applicable in defueled condition.
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ATTACHMENT B Rev. 2 4.2.3.9 Applicable Portions of Title 10, Chapter 1, Code of Federal Regulations.
4.2.3.10 Applicable industry events and lessons learned.
4.2.3.11 Mitigation of Accidents Involving Spent Fuel Storage.
4.2.3.12 Results of Biennial and Annum Examinations.
4.3 On-the-Job Training 4.3.1 On-the-Job Training shall take into consideration the following as applicable to the defueled plant with fuel in the SFP, the maintenance of components in a non-degraded status, and control of radiological effluents.
l 4.3.1.1 Loss of electrical power (off-site).
4.3.1.2 Loss of SFP cooling.
4.3.1.3 Loss of component cooling system or cooling of an individual component.
4.3.1.4 Fuel cladding failure or high activity in the Srent Fuel Pool or offgas.
4.4 Procedure Review Training 4.4.1-Each operator shall review annually, the contents of the abnormal and i
emergency procedures applicable to maintaining safe storage of the fuel in the SFP, loss of off-site power and control of radiological effluents.
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NITACilMENT 11 Itev. 2 4.4.2 Applicable training methods are described in Sections 4.2 and 4.6.
4.4.3 Training in this area shall be included in the preplanned schedule of the requalification training cycle.
4.5 Other Areas of Training 4.5.1 To ensure each Senior Operator or Operator is cognit :nt of topics that cannot be preplanned, additional areas of training (as applicable to maintaining safe storage of fuel in the SFP, the maintenance of components in a non-degraded status, the control of radiological effluents, and loss of off-site power) shall include the following subjects:
4.5.1.1 Facility Design Changes 4.5.1.2 Procedure Changes 4.5.13 Facility License Changes 4.5.1.4 Apphcable Operating Experiences 4.6 Alternative Training Methods 4.6.1 Acceptable methods used for training to supplement the preplanned lectures may include, but are not limited to:
4.6.1.1 13rief lectures conducted by the Shift Supervisor or other appropriate personnel 4.6.1.2 Staff meetings 8
A'lTACllMFNT B Rev. 2 o
l 4.6.1.3 Written communications to each licensed individual from facility management 4.6.1.4 Explanation of major changes as part of the preplanned lecture series 4.6.1.5 Supenised discussions 4.6.1.6 Operator reading assignments R
4.7 Evaluation and Observation I'
4.7.1 The Defueled Requalification Training Program shall include an evaluation and observation system to obtain the maximum benefits from the program and as a method to determine areas in which retraining is i
needed.
4.7.2 Systematic observation and evaluation of the performance and competency of Senior Operators and Operators sball be made by the Training Supervisor or his designated representative. Such observations shall also include evaluations including actions taken during actual or simulated abnormal and emergency conditions (Refer to Section 4.7.6.1).
4.7.3 Individuals receiving an initial license shall ccmplete their first annual operating examination within thirteen (13) months after the effective L
date of their license.
4.7.4 It is not required that the individual (s) preparing or reviewing the examination (up to a maximum of 3) also take the examination. No individual shall be allowed to prepare examinations more than two (2).
successive times which limits the number of times an individual may be exempted from taking the examination.
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NITACilMENT B Rev. 2 i
4.7.5 Biennial Written Exams 4.7.5.1 Written examinations shall be administered at 23 to 25 month intervals, depending on plant scheduhng.
4.7.5.2 The examination shall follow the guidelines of 10CFR55 Subpart E as applicable and shall be used as a system to determine Senior Operator and Operator knowledge of subjects covered in the Defueled Requalification Training Program; normal, abnormal, j
and emergency procedures; and as a method to determine areas l
in which retraining is needed to upgrade Senior Operator and Operator knowledge.
4.7.6 Operating Examinations 4.7.6.1 Each Senior Operator and Operator shall participate in an annual operating examination with the Training Supervisor or his designated representative.
4.7.6.2 The examination and evaluation shall consist of:
4.7.6.2.1
_ A discussion of required actions during abnormal and emergency conditions.
4.7.6.2.2 A simulation of possible abnormal conditions which can occur while on shift demonstrating each action taken to l
correct the abnormality.
4.7.6.3 Should the performance of the Senior Operator or Operator be deemed unsatisfactory, the Senior Operator or Operator shall i
participate in an accelerated review program tailored to place emphasis where there is clear indication of need.
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I ATTACIlhiliNT 11 Rev. 2 4.7.6.4 Upon successful completion of the accelerated review program, the individual shall be subject to re-examination.
4.8 Conditions of I icenses 4.8.1 All licensed operators shall participate in all of the Defueled Requalification Training Program lecture series. Ilowever, up to 30%
of the lecture series may be missed because of sickness, emergency shift change or other justifiable cause. After returning to a normal work schedule, any training missed shall require, within one requalification training cycle, atisfactory completion of documented self-study, one-on-one instruction, or reading assignments; in
- addition, any examinations missed shall require, within one requalification cycle, satisfactory completion. If the training is not satistactorily completed, within the established time limit, the individual shall be suspended from licensed duties. The requirements established in Section 4.8.5 shall be met prior to the resumption of licensed duties.
4.8.2 The requirement for maintaining an active Senior Operator or Operator license shall be to actively perform the functions of a Senior Operator or Operator consistent with a defueled condition, fuel in the SFP, and maintenance of components in a non-degraded status for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter.
4.8.3 Any Senior Operator or Operator who has not been performing the function of an Senior Operator or Operator as stated in 4.8.2 shall meet the following requirements prior to resuming licensed activities:
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NITACHMENT 13 Rev. 2 l
4.8.3.1 The qualification and status of the licensee are current and valid.
4.8.3.2 The licensee has completed a minimum cf one shift of shift functions under the direction of a Senior Cperator or Operator, as appropriate, and in the positiori to which the individual shall be assigned.
4.8.4 Licensed personnel shall be suspended from licensed duties and subject to the requirements of Section 4.8.5 when:
4.8.4.1 the grade on the biennial written examination is less than 80%
overall.
OR 4.8.4.2 the grade on the annual operating examinations is less than 80%
overall or less than 70% on the questions associated with the job performance measures.
OR 4.8.4.3 an evaluation made by any Operations Supervisor indicates the need for accelerated training.
4.8.5 Resumption of Licensed Duties t
4.8.5.1 Prior to resuming the duties of a licensed operator, the Nuclear Operations Manager shall establish an Operation and Training Review f30ard consisting of an Operations Superintendent and the Operations Training Supervisor / coordinator.
L 4.8.5.2 The board shall evaluate and review the licensed individual's past performance and deficiencies.
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4 NITACllMENT 13 Rev. 2 4.9.5.3 The board may recommend remedial training, a waiver of the suspension or permanent removal from licensed duties.
4.8.5.4 Remedial training and re-examination should be completed within 30 days of the 130ards' recommendation. If remedial training and re-examination is not completed within 60 days, the 130ard shall reconvene and evaluate the circumstances. Approval by the AGM, Nuclear, is required if the 130ard recommends further training and re-examination.
4.9 Records and Documentatiori 4.9.1 Training files sha!! be maintained in a format that is adaptable to verify that retraining is conducted in accordance with this Delueled Requalification Training Program and shall meet the requirements of 10CFR55.59(c)(5).
4.9.2 Records and documentation shall be in accordance with administrative procedures.
4.10 Senior Operator Trainees 4.10.10perators who currently hold active NRC licenses and are enrolled in the Rancho Seco Senior Operator Training program may be exempted from attending the requalification lectures requirements of Section 4.2 and on-the-job training requirements of Section 4.3. Senior Operator trainees shall not be subject to the requirements of 4.8.1 or 4.8.2.
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NITACllh1ENT 13 llev. 2 4.11 Instructor Qualifications 4.11.1 Instructors who teach safety systems, integrated responses, and transients courses shall demonstrate their competency by successful completion of a NRC administered Senior Operator examination, or successful completion of Rancho Seco Senior Operator Certification program.
4.11.2An instructor who meets the requirements of 4.11.1 shall be in attendance during classes taught by instructors who have appropriate experience / expertise in safety systems, integrated responses, and transients courses but do not meet the requirements of 4.11.1.
4.11.3 Senior operator licensed / certified instructors shall be enrolled in the Defueled Requalification Training Program to assure they are cognizant of current operating history problems and changes to procc b res and i
administrative limitations.
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