ML20214Q016
| ML20214Q016 | |
| Person / Time | |
|---|---|
| Issue date: | 10/15/1986 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20214P901 | List: |
| References | |
| NUDOCS 8612040465 | |
| Download: ML20214Q016 (137) | |
Text
UNITED STATES N
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NUCLEAR REEULATORY COMMISSION REGION I t1D_
,E 031 PAftK AVEMUE o,
%, * *...,e,a KING OF PMUS$1A.PENNSVLVANIA 19408 15 0CT 1986 MEMORANDUM FOR:
R. W. Starosteckt, Deputy Director, Office of Inspection and Enforcement FROM:
Samuel J. Collins, Deputy Director, Division of Reactor Projects
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SUBJECT:
DIFFERING PROFESSIONAL OPINION - PEER REVIEW GROUP (DP0 86-04)
In response to your memorandum of September 15,1986, (attached) the Peer Review Group consisting of Messrs. L.A. Reyes, E. G. Greenman and myself will convene at the Technical Training Center during the period of October 21 through 23, 1986. We understand that per NRC Manual Chapter-4125, our charter is to provide an independent review, evaluation and written comments on,the substar.ce of the OP0 issue (s).
The current schedule to provide these recommendations to yourself is as follows:
October 21-23, 1986 - meeting at TTC October 27-31, 1986 - finding assessment and report documentation November 6, 1986 peer review group report presentation By copy of this memo the OP0 originator is appraised of the peer review groups actions to date.
I h
Sim:
ns, eputy Director Division of Reactor Projects
Enclosure:
As Stated cc w/ enc 1:
L. A. Reyes, RII E. G. Greenman, RIII K. A. Raglin, TTC C. D. Evans, TTC R. M. Scroggins, RM 861204046S 861128 PDR ORG NIED PDR
'IO AIL EMPLOYEES Form NRC-489 '
(1 76)
U. S. NUCLEAR REGULATORY COMMISSION NRC MANUAL TRANSMITTAL NOTICE f
CHAPIER NRC-4125 DIFFERI?U PROFESSIONAL' OPINICNS SUPERSEDED:
TRANSMITTED:
Number Date Number Date 4100-92 TN Chapter NRC-4125 9/19/80 Chapter IEC-4125 7/23/85 Page Page Appendix NRC-4125 9/19/80 Appendix NRC-4125 7/23/85 REMARKS:
This issuance provides all IEC enployees with the recently Cmmission-approved revision to Chapter lac-4125, Differirg Professional Opinions (DPO). During the process of revision, both the Camission and the EDO reaffinned their continued full support for the DPO Policy and Process.
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In addition, they stressed the need for lEC management to act objectively in handling Differing Professional Opinions.
This revision reflects the evaluation and report of the Special Review Panel as well as requests from NRC management and reconmerriations of the Office of Irispector arri Auditor, ard includes:
1.
more snphasis on the establishnent of timely procedures for the resolution of differing professional opinions (DFO's).
2.
requirenent for Office Directors arri Regional Administrators to provide for maintenance of written reconis to provide accountability for actions taken to resolve DPO's and to place ccmpleted cases in centrally located office files.
3 statements of responsibilities for Regional Administrators ard for the Office of Resource Management concerning the processing and resolution of statenents of differing professional opinions.
4.
provision for the Office of Resource Management to submit to the Cmmission an annual, rather than a quarterly, report on DFO's ani actions taken to achieve their resolution.
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5 statement iMicating that IM maintains a file of all initial and final DPO's handled'by NRC; and requirement that the Director, RM, will notify the EDO of any DPO's that are not being resolved within the prescribed schedule.
t 6.
statement that managers advising snployees to file DPO's will inform the employees' management of_ that action.
7 addition of a sumary and schedule of the DPO resolution process.
8.
requirenent for Office Directors ard Regional Administrators to obtain a control number for each DPO from RM.
9 highlighting of methods to address alleged retaliation for having filed a DPO.
- 10.. requirement for the Director, Office of Administration, to provide an overview of the DF0 program in orientation of new employees.
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l TO ALL EMPLOYEES l Form NRC-489 (1 76)
U. S. NUCLEAR REGULATORY COMMISSION
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NRC MANUAL TRANSMi~ ~ ^ L NOTICE CHAPTER NRC-4125 DIFFERING PROFESSION L 0' PINIONS SUPERSEDED:
TRANSMITTED:
Number Date Number Date 4100-41 TN
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NRC-4125 9/19/80 Chapter Chapter Page Page Appendix Appendix NRC-4125 9/19/80 REMARKS:
This chapter and appendix define NRC policy, objectives, procedures, responsibilities, and basic requirements and definitions established to provide for the expression and resolution of differing professional
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opinions concerning matters related to the agency's mission.
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L U.S. NUCLEAR REGULATORY COMMISSION NRC MANUAL 1
Volume:
4000 Personnel Part :
4100 Federal RM CIMRTER 4125. DIFFERING PROFESSIONAL OPINIONS -
4 4125-01 COVERAGE This chapter and appendix comprise NRC policy, objectives, procedures, responsibilities and other basic. requirements and definitions established to provide for the expression and -resolution of differing professional opinions i
concerning matters related to the agency's mission.
4125-02 POLICY AND OBJECTIVES 021 Policy.
It is the policy of the Nuclear Regulatory Commission, and the responsibility of all NRC supervisory and managerial personnel, to maintain
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a working environment that encourages employees to make known their best professional judgments even though they may differ from a prevailing staff-view, disagree with a management decision or policy position, or take issue with proposed or established agency practices.
Each-differing professional opinion of an NRC employee will be evaluated on its own merit. Further, each differing professional opinion will be pursued to resolution and the employee's statement of differing professional opinion, together with the agency's final response, will be made available to the public to ensure the openness of NRC decisions that may affect the public.
It is not-only the right but the duty of all NRC employees to make known their best professional judgments on any matter relating to the mission of the -
Moreover, both the general public and the Nuclear Regulatory Com-agency.
. mission benefit when the agency seriously considers NRC employees' differing professional opinions that concern matters related to the agency's mission. This policy is intended to assure all employees the opportunity to express differing professional opinions in good faith, to have these opinions heard and considered by NRC management, and to be protected against retaliation in any form.
022 Objectives.
To define differing professional opinions.
a.
b.
To distinguish between differing professional opinions and the differences of views and opinions routinely raised and resolved among staff members in the ordinary conduct of agency business.
Approved:
July 23,1985
NR C-4125-03 DIFFERING PROFESSIONAL OPINIONS
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To provide a primary channel for submitting differing professional c.
opinions.
d.
To specify the recommended content of a statement of differing professional opinions.
To provide reasonable time and reasonable administrative assistance e.
to help employees develop and document their differing professional opinions.
f.
To provide for acknowledgment of receipt of statements of differing professional opinion and for advising originators of planned actions for their resolution.
g.
To provide accountability by requiring a written record of all actions taken on differing professional opinions.
h.
To provide for resolution within the agency of differing professional opinions, if at all possible.
i.
To provide alternative channels for expressing a
differing professional opinion either on the record or anonymously.
j.
To provide disciplinary sanctions against employees who take f
retaliatory actions that affect the originators of, or employees who
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support, differing professional opinions.
k.
To prevent intentional misuse of these procedures.
1.
To provide for periodic assessment to ensure that implementation of th'ese procedures accomplishes the stated objectives and to recom-mend appropriate changes.
m.
To provide recognition to the originators of differing professional opinions if their opinions contribute significantly to achieving the agency's mission.
4125-03 RESPONSIBILITIES AND AUTHORITIES 031 The Executive Director for Operations (EDO):
a.
assures that a written record is maintained to provide accountability for all subsequent actions taken to resolve the differing professional opinions.
b.
ensures that differing professional opinions which are not resolved within four calendar months after their submission are resolved by the responsible office director as promptly as is practicable.
c.
annually appoints a Special Review Panel to evaluate and report on the functioning of the differing professional opinion procedures.
Approved: July 23.1985
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DIFFERING PROFESSIONAL OPINIONS NRC-4125-032 032 Directors of Offices and Regional Administrators:
a.
determine actions to be taken on statements of differing professional opinion (DPO).
b.
obtain a unique control number from RM to place on the original DPO and all subsequent correspondence and documentation on that DPO.
c.
within 10 days of its submission, forward the differing professional opinion either to the appropriate manager within his or her own office or to the director of the office with basic responsibility for the issues raised in the differing professional opinion with copies to the EDO and Director, Office of Resource Management.
d.
convene an impartial peer review group to address the substance of the issues raised either when requested by the originator or~when he determines that the complexity of the issues raised justifies such a review.
e.
inform the Atomic Safety and Licensing Board Panel and the Atomic Safety and Licensing Appeal Panel of any differing professional opin-ion that relates to issues pending before them or scheduled for their consideration.
f.
assure that every effort is made to expedite the resolution of differ-
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ing professional opinions within the time frame specified in Appendix 4125, Section G.2.a.
g.
provide the originator with a copy of the peer review group's -
report h.
inform the EDO of reasons for delay and submit, for EDO approval, a proposed plan for resolution.of DPO's not resolved wittiin four calendar months after submission.
i.
provide the originator with written notification of the resolution of his differing professional opinion with a copy to the Director, Office of Resource Management, and the EDO, and access to all documents generated in connection with its resolution.
j.
after the issue is resolved and the case closed, complete files on the DPO will be maintained centrally by the cognizant office.
k.
provide the Office of Resource Management with an annual Differing Professional Opinion Status Report.
(See Appendix 4125, Section G.4.)
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Approved:
July 23,1985
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NRC-4125-033 DIFFERING PROFESSIONAL OPINIONS f
033 The Director, Office of Resource Management (RM):
a.
provides the Commission with an annual report identifying all differing professional opinions submitted and specifying the actions that have been taken to achieve their resolution.
b.
assigns a unique control number to each DPO at th'e tide the offices initially provide documentation to RM on the origination of a specific DPO.
c.
maintains a file of all initial and final DPO's handled by NRC.
d.
advises the immediate supervisors of originators of DPO's of the requirements to maintain a written record to provide accountability for all subsequent actions taken to resolve the differing professional opinions.
(See 4125-036 h.)
e.
notifies the EDO of any DPO's currently under review that are not anticipated to be resolved within 30 days after initial submission.
034 The Director, Office of Administration (ADM), requires all of the Headquarters and Regional personnel offices to include an overview of the DPO program in the orientation for new employees.
035 The Advisory Committee on Reactor Safeguards:
appends comments to all referred statements of differing professional a.
opinion and forwards them for resolution to the appropriate office director, if the differing professional opinion relates to a potential safety, issue within their purview.
b.
responds to appeals by an originator if the differing professional opinion concerns matters of public health or safety.
036 Immediate Supervisors:
a.
advise and assist employees in administratively preparing adequate written statements of differing professional opinion and aid them in identifying related information.
b.
in consultation with their managers, determine the amount of the ori-ginator's work time and administrative support to be provided in response to the originator's request for assistance, receive signed statements of differing professional opinion from the c.
originator.
d.
within five working days of receipt acknowledge receipt of statements of differing professional opinion by memoranda to the originators.
A copy of the acknowledgment memo and the DPO statement is forwarded to the EDO and the Director, Office of Resource i
Management.
- Approved: July 23,1985 l
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DIFFERING PROFESSIONAL OPINIONS NRC-4125-037 e.
return to the originator any statement excluded from the definition of a differing professional opinion together with a memorandum citing i
l the specific exclusion with a copy to the EDO and Director, Office of Resource Management.
f.
forward statements of differing professional opinion", via their chain-of-command, to his or her office director for action with a copy to the EDO and Director, Office of Resource Management.
g.
assure that statements of differing professional opinion are incorpo-rated into the receiving organization's normal work tracking system.
h.
maintain a written record to provide accountability for all subsequent actions taken to resolve the differing professional opinion while the DPO is active.
i.
when the DPO is completed or withdrawn, forwards the complete file to the office director's office, where it will be centrally maintained.
037 All Employeers:
a.
make known their best professional judgments on any matter relating to the mission of the agency by submitting to their immediate supervisor a signed statement of differing professional opinion when appropriate.
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b.
before submitting a statement of differing professional opinion, should consult with their immediate supervisor who will aid them in identifying related information and assist them, if requested, in clar-ifying the issues.
c.
may request an OpasCD6or meeting with any manager to discuss their
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views,
d.
may request that' their differing professional opinion be presented to an impartial peer review group for review, evaluation, and comment.
e.
may communicate a differing professional opinion concerhing a poten-tial safety issue directly to the chairman or any member of the ACRS.
f.
may ' appeal the resolution of their differing professional opinion to a higher level of NRC management.
4125-04 DEFINITIONS 041 Differing Professional Opinion.
A conscientious expression of pro-fessional judgment as contained in a written, signed statement submitted to one's immediate supervisor, or submission of an unsigned anonymous statement Approved: July 23,1985 l
DIFFERING PROFESSIONAL OPINIONS NRC-4125-042 (see NRC Appendix 4125, Section H.1) which, on any matter relating to NRC's mission or organizational activities, differs from the prevailing staff view within an organization, disagrees with a management decision or policy position, or takes issue with a proposed or an established agency practice.
Differing professional opinions may involve technical, management, legal, or policy issues and are not limited to the originator's area.of expe,rtise. Matters that are subject to employee grievance in accordance with Chapter NRC-4157 and matters covered by the negotiated grievance procedure do not qualify as differing professional opinions.
042 Manager.
An employee who directs the work of an organization, is held accountable for specific line or staff programs or activities, and whose primary duties are managerial.
043 Peer Gmu'p. A group of NRC staff with expertise in the area encompassed by a given DPO, convened for the purpose 'of addressing the:
substance of the issues ~ raised by the DPO. r 4125-05 BASIC REQUIREMENTS 051 Applicability. These procedures for the expression and resolution of differing professional opinions are for the use of all NRC employees including supervisors and managers.
The procedures supplement other stated rights, duties, and safeguards applicable to all Federal employees who make their views known either within or outside their agencies, including:
the independent right of free speech provided by the First Amend-a.
ment to the U.S. Constitution.
b.
the right of government employees to petition the Congress (5 USC 7102).
the rights of employees to communicate directly with the Congress as c.
outlined in the Code of Ethics for Government Service (10 CFR 0.735 Annex A).
d.
provisions of the 1978 Civil Service Reform Act dealing with pro-hibited personnel practices and the regulations of the Merit System Protection Board.
052 Appendix 4125.
This appendix provides procedures for the expres-sion and resolution of differing professional opinions.
l Approved: July 23,1985
DIFFERING PROFESSIONAL OPINIONS NRC Appendix 4125 CONTENTS
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PaSe A.
Normal Differing Views vs. Differing Professional Opinions.........
1 B.
Primary Channel for Expressing Differing Professional Opinions....
1 C.
Content of a Written Statement of Differing Professional Opinion...
2
- D.
Resources to Assist Originators of Differing Professional Opinions.
2 E.
Acknowledgment of Differing Professional 0 pinions..................
2 F.
Written Record of Actions on Differing Professional Opinions.......
3 G.
Resolution of Differing Professional 0 pinions......................
3
- 1. Definition of Resolution.......................................
3 2.'
Resolution Process.............................................
4
- 3. Appeal.........................................................
6
- 4. Reports to the Commission......................................
7 5
H.
Alternate Channels for Expressing Differing Professional...........
7 0 pinions...........................................................
- 1. Open Door Po1 icy................................................
8
- 2. The ACRS........................................................
9 I.
Prevention of Retaliation Against Individuals who Express or Support Differing Professional 0 pinions............................
9
~J.
Prevent Intentional Misuse of Procedures for Differing Professional 0 pinions........................................:.....
10 K.
Special Review Panel for Follow-up on Functioning of Differing i
Professional Opinion Procedures....................................
10 L.
Recognition of Originators of Significant Differing Professional 11 0 pinions...........................................................
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i Approved: July 23,1985
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DIFFERING PROFESSIONAL OPINIONS NRC Appendix 4125 l
PROCEDURES FOR THE EXPRESSION AND RESOLUTION OF DIFFERING PROFESSIONAL OPINIONS A.
Normal Differing Views vs. Differing Professional Opinions A normal differing view, developed in the fie'e 'and'.open discussion of work matters, becomes a differing professional opinion only when the originator brings it to NRC management attention in accordance with these procedures.
In the free and open discussion of work matters, professional differences of opinion are common.
Employees may also develop critical views con-cerning matters other than their personal work assignments, such as is-sues under consideration in another part of NRC or relating to an agency practice or position that is neither currently under review nor in the agency's decisionmaking process.
In both these instances employees nonnally ~ try, and should be encour '
aged, to resolve their concerns through -discussions with their co-workers and immediate supervisors. 'In some cases, such discussions may lead to the submission of a suggestion as part of the NRC suggestion program (Chapter NRC-4154).
However, these informal discussions may ~ not ' resolvet the matter and an' employee may be convinced that the agency' and the public would be bdt-
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ter served if another opinion prevailed.
To further pursue such con-cerns using these procedures, an employee should _ submit La. Ewritten' statement of differing professional opinion in accordance with' ~ these proceduresa With the submission of this statement, the employee's dif-fering view becomes a differing professional opinion.
An employee may not use these procedures for differing professional opinions without submitting a written statement.
The employee may, how-ever, express any concerns orally or in writing to the ACRS and may also discuss these concerns with any NRC manager as provided in the Open Door Policy. (See Section H).
B.
Primary Channel for Expressing Differing Professional Opinions These procedures are invoked when employees submit to their immediate supervisor a written statement of differing professional opinion.
As indicated in the statement of policy, it is not only the right but the duty of all NRC employees to make known their best professional judgments on any matter relating to the mission of the agency.
Before submitting the statement, employees should consult with their im-mediate supervisor who will aid them in identifying related information and assist them, if requested, in clarifying the issues.
Originators of differing professional opinions may request agency resources for prepar-ing adequate written statements of differing professional opinion and such j
requests shall include estimates of the resources required.
1 Approved: July 23, 1985
NRC Appendix 4125 DIFFERING PROFESSIONAL OPINIONS After registering a DPO, an individual should be prepared to describe his backgn>undrash it relates to the issue raised, since the initial credibility-given his; opinion mayf rest, in part, on that background. - e C.
Content of a Written Statement of Differing Professional Opinion A written statement of differing professional opinion, while theing brief, should in all cases include the following:
17 a summary of the originator's perception of the prevailing staff view, existing management decision or stated position, or the proposed or established agency practice.
27 a description of the originator's opinions and how they differ from any items discussed in 1. above.
a statement of the originator's assessment of the resulting conse-3J quences if the differing professional opinion is not adopted by the agency.
D.
Resources to Assist Originators of Differing Professional Opinions To assist originators in preparing adequate written statements of differing professional opinion, NRC management will allow a reasonable amount of the originator's work time and administrative support.
If called to testify I
before a Licensing Board or an Appeal Board, the employee may receive, upon request, assistance from the staff legal office in preparing testimony or other documents to be filed with the Board.
Such assistance will be solely for the purpose of facilitating the filing of the necessary documents and will not. constitute legal representation of the employee by the legal staff.
The originator's immediate supervisor, in consultation with his or her manager, will determine the amount of the originator's work time and administrative support to be provided in response to the originator's request for assistance.
E.
Acknowledgment of Differing Professional Opinions The immediate supervisor shall, upon receiving a written statement of differing professional opinion, discuss the statement with the originator if this has not previously been done.
In addition, the immediate supervisor must, within five working days, acknowledge receipt by a memorandum to the originator with a copy to the EDO and a copy to the Director, Office of Resource Management.
This memorandum will also indicate the actions that will be taken to resolve the differing professional opinion.
Upon receipt, statements of differing professional opinion will be incor-porated into the receiving organization's normal work tracking system.
This tracking should assure that the status of each differing professional opinion is regularly reviewed, aid in its prompt resolution, and provide a systematic basis for keeping the originator informed.
Approved:
July 23,1985 2
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' DIFFERING PROFESSIONAL OPINIONS NRC Appendix 4125 i
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Written Record of Actions on Differing Professional Opinions Once a differing professional opinion has been submitted, a written. record" must be maintained by the immediate supervisor while the DPO is active to provide accountability for. all subsequent actions taken to - resolve that d
differing professional ~ opinion on its merits.
This record will consist of signed notations. of all supervisory.and managerial determinations and actions based. upon the differing professional opinion.
Changes in the original -documentation that are requested by the originator will also be made a part of this written record.
Copies of the initial and the final DPO documents will' be sent to. the Directoi, Office of Resource Management, and the. EDO.
All pertinent documentation.will be retained by the supervisor while the DPO is active and centrally by the office director for a period of ten years after the DPO becomes~ inactive.
G.
Resolution of Differing Professional Opinions 1.
- Definition of Resolution A: differing professional opinion is considered resolved by the.lfRC7 when:
al NRC management adopts the views expressed in the originator's written statement of differing professional opinion; or bd NRC management adopts a' part of the judgments expressed in the originator's written statement of differing professional opinion and informs the originator of the-reasons for not adopting the remainder; or c.( The responsible office director determines that evaluation of the
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differing professional opinion fails to justify modification of a-management decision, policy position, or a proposed or an existing agency practice; or di The responsible office director determines that the impact of the potential consequences stated in the differing professional opinion is insufficient to justify a detailed evalization of the differing professional opinion; or eT The differing professional opinion is withdrawn by the originator.1]
i 1/In such cases, NRC management may elect to pursue the matter further based on its merit even though it is no longer considered to be a differing professional opinion.
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3 Approved: July 23,1985
NRC Appendix 4125 DIFFERING PROFESSIONAL OPINIONS In _ each of the preceding cases, the resolution process is complete-only when5 the eriginator has been informed of the decision or action of NRC management and.. consistent with security classification policy, both the statement of differing professional opinion and the response of NRC management have been placed in NRC's Public Document Room.
2.
Resolution Process Summary and schedule of resolution process:
a.
Originator submits DPO to immediate supervisor; (Within five working days of receipt) innediate supervisor forwards DPO to office director with comments of all others in chain-of-command appended; (Within 10 working days of submission) office director forwards DPO to appropriate manager for action
[If transferred to another office, DPO must be assigned to responsible program manager within 15 working days after submission by originator. ];
(Within 15 days after submission) office director informs ASLBP and ASLAP of any DPO that relates to issues pending before
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them or scheduled for their consideration; (Within 30 working days after assignment to responsible manager) DPO normally resolved; (Four calendar months after submission) if DPO not resolved, responsible office director informs the EDO of reasons for delay and submits, for EDO approval, a proposed plan and schedule for completing resolution.
b.
When ' submitting a differing professional opinion, the originator may request that it be presented to an impartial peer review group for review, evaluation, and comment.
If such request is i
not made' by the originator, and if the responsible office.
director determines that such review is justified by the coanplexity or the potential significance of the issues raised, he' sheFconvene an impartial peer review group to address the substance of the issues raised in the differing professional opinion:
In either case, the responsible office director will assure that members of the peer review groups convened for this purpose are specifically selected for their impartiality and professional competence concerning matters discussed in each differing professional opinion.
The responsible office director Approved:
July 23,1985 4
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.pIF5ERING' PROFESSIONAL OPINIONS NRC Appendix 4125 willicdefullys consider peer review group recommendations in 2
the resolution of applicable differing professional opinions.and willVprovide. the; originator with a copy of the ' peer review group's' report.
c.
Upon receiving a statement' of, differing professional opinion from the originator, the immediate supervisor will forward it, via the chain-of-command, - to his or her office director ~ for action with copies to the. EDO and the Office of Resource Management.
The' immediate supervisor and all others in the chain-of-command shall append their views concerning matters discussed in the differing professional opinion.
The differing professional opinion, with comments appended, shall be provided to. the office director within five working days after its submission by the originator.
Copies of these comments,
together with all other ' documents generated in response to the differing professional opinion', shall be made available to the originator as they are generated.
At his option, the originator may submit written comments for the record concerning views expressed. by his immediate supervisor or others in the chain-of-command, or views expressed by intermediate NRC management personnel in the course of resolution of the.
differing professional opinion.
d.
The office director will obtain a unique DPO control number and will. forward the differing professional. opinion, within 10 working days of its. submission by the originator, either to the appropriate manager within his or her own office or to the
' director of -the office that has basic responsibility for the issues raised' in the differing professional opinion,with copiesf to the EDO and Director,: Office of Resource Management.
If transferred to another office for resolution, the differing professional opinion must be assigned to the responsible program manager within 15 working days after its submission tiy the originator.
The responsible manager will incorporate the statement of differing. professional opinion into the organization's normal work tracking system and, until the differing professional opinion has been resolved, shall provide the originator with brief monthly status reports. Copies of these reports shall also be provided to the responsible office director.
The responsible manager will also inform the originator of other differing professional opinions received that are relevant to that submitted by the originator.
e.
The responsible office director will, within 15 working days after its submission by an originator, inform the Atomic Safety and Licensing Board Panel and the Atomic Safety and Licensing Appeal Panel of any differing professional opinion that re-lates to issues pending before them or scheduled for their consideration.
5 Approved: July 23,1985 i
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NRC Appendix 4125 DIFFERING PROFESSIONAL OPINIONS
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f.
Every. effort shall be made to expedite the resolution of differing professional opinions.
Normally,
a differing professional opinion should be resolved-by the responsible office director _within 30 working days after its assignment. to the res'ponsible manager.
An extension of 15 working days will, however, be automatically granted _ upon certification by the responsible manager to the originator that:
(11 resolution of
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the differing professional opinion involves especially complex issues, (2) the workload of managerial personnel involved in resolution of the _ issues is temporarily heavier than normal, or (3) that resolution of the differing professional opinion involves the participation of several levels of NRC management.
Additional extensions of 15 working daysyach may be granted only upon application to and approval by'the responsible office director who will consider. comments of both the managerial personnel involved and the originator with regard to the proposed extension.
g.
If a differing professional opinion is not resolved within four.'
calendar months - after its submission, the responsible office director shall inform the Executive Director for Operations (EDO) of the reasons for the delay and shall submit, for EDO approval, a ' proposed plan and schedule for completing its reso-lution.
The responsible office director shall provide the orig-inator with a copy of the EDO-approved plan and schedule for resolution.
The EDO will ensure that differing professional
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opinions in this category are resolved by the responsible office director as promptly as is practicable.
h.
The -responsible office director shall provide the originator with written' notification of the resolution of his differing professional opiniogf with a copy to the Director, Office of Resource Management, (see Section 4125-03) and the EDO, and access to all documents generated in connection with its resolution. While the DPO is active, the immediate supervisor will maintain the file.
When the DPO is complete or inactive, the office director will centrally maintain the file.
3.
Appeal The originator may appeal the resolution of his differing professional opinion to a higher level of NRC management including ultimately, the Commission.
Normally, it would be expected that appeals by individuals assigned to Program Offices or to EDO Staff Offices would be submitted to the EDO and that individuals assigned to the Commission or to Commission Staff Offices would submit appeals or to the Commission.
- Moreover, if a differing professional opinion concerns matters of public health or safety, the appeal may be forwarded through the ACRS with a request that the ACRS comment on the potential safety implications of the resolution that is being appealed -
Approved: July 23, 1985 6
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DIFFERING PROFESSIONAL' OPINIONS NRC Appendix 4125 These procedures make no provision for further appeal of the reso-e lution by NRC management of a differing professional opinion. How-ever, originators who are dissatisfied with either NRC management's resolution of their differing professional opinion or the results of their appeal of this resolution may further pursue their concerns via the Open Door policy or the ACRS as appropri. ate.
4.
Reports to the Commission The Office of Resource Management (RM) shall provide the Commis-sion with annual reports identifying all differing professional opin-ions submitted and specifying the actions that have been taken to achieve their resolution.
This information shall be provided by the responsible. office directors who shall, within five working days after each calendar year, provide RM with a Differing Professional Opinion Status Report that contains:
a.
A listing and a description of all differing professional' opinions received together with a brief status report of all efforts that have been taken to achieve their resolution.
Items shall be reported and summarized in the following three categories:
(1) Differing professional opinions submitted since the last i
status report.
(2) Differing professional opinions previously received and J
reported but not yet resolved.
(3) Differing professional opinions previously received and reported that were resolved on.the following dates.
b.
Information obtained from the originator of each differing pro-4 fessional opinion resolved during the year which indicates the originator's general reactions to these procedures.
As a mini-mum, this information should include the originator's evaluation of the utility of these procedures for handling his or her dif-fering professional opinion, areas in which these procedures inhibited rather than aided the achievement of their objectives, and comment s or recommendations for improvement of these procedures.
H.
Alternate Channels for Expressing Differing Professional Opinions Two alternate channels are available for employees who prefer not to use the primary channel for expressing their differing professional opinions. Once a differing professional opinion submitted via either of these two channels has been forwarded to the responsible office director, subsequent procedural steps involved in resolution of the differing professional opinion are essentially identical with those prescribed for the primary channel.
The basic difference between the primary channel and the two alternatives discussed below is that
)
the alternatives permit the originator to select the individual manager to whom the differing professional opinion will be submitted and, in i.
7 Approved:,Jyly 23,1985
_ NRC Appendix 4125 DIFFERING PROFESSIONAL' OPINIONS
~
. addition, they mak'e provision for the submission of anonymous
~ differing. professional opinions upon request.
1.
Open Door Policy The Open Door. Policy of NRC provides that.NRC employees may, on their.own initiative, meet with any manager, including a Commissioner or the Chairman of NRC, to discuss any matter i
4 of concern to the. employee.
Employees may request -an Open Door meeting directly with the selected manager's secretary or administrative assistant and there is-no requirement for the approval of requests for such meetings by intermediate management.
An employee's request for anonymity will be honored by any manager contacted via the Open Door. except in two special situations 'that could occur if the manager contacted is an NRC 4
Commissioner.
Each Commissioner is legally required to inform all other Commissioners of any information which he believes to be related to the responsibility or the function of the
' Commission.
(This requirement for mandatory information-sharing applies _only to the Commissioners and does not extend to others within.NRC.)
Subject to this ' constraint, - NRC Commissioners will honor an employee's request for anonymity made in connection with communications via the Open Door.
Therefore, when an employee requests ' anonymity in an Open h
Door contact with a Commissioner, no' Commissioner will disclose to another Commissioner the identity of the employee unless
-(a) as a practical matter it is impossible to convey the 1
substance of the information without making known the identity of the employee, (b) disclosure of the employee's identity to the other Commissioners is essential for determination of the-accuracy and reliability of the information,
or (c) the employee's identity is required to be released by law.
If Open Door discussions disclose that an employee's views constitute a
differing professional opinion,
the contacted manager should advise the employee to submit a signed, written statement of differing professional opinion in accordance with these procedures and should inform the employee's management that he has been advised to prepare such a statement.
If the employee insists on remaining anonymous but wishes to have his or her views considered as a differing professional opinion, the employee should submit an unsigned statement of differing professional opinion to the manager contacted via the Open Door and that manager will forward the anonymous statement of differing professional opinion to the office director having programmatic responsibility for the issues raised in the 1
differing professional opinion.
Resolution of the differing professional opinion will then be completed in accordance with these procedures.
To protect the employee's anonymity in such
- cases, however, it may not be possible to provide the acknowledgment of receipt of the differing professional opinion Approved: July 23,1985 8
5E DIFFERING PROFESSIONAL OPINIONS NRC Appendix 4125 or the reports on resolution directly to the originator of the differ-ing professional opinion. In such cases, the manager originally con-tacted via the Open Door shall relay to the originator both the ack-newledgnent of receipt and all reports received by that manager con-cerning resolution of the differing professional opinion.
Differing opinions not expressed in writing as required by Section C shall be considered to be normal. differing views as discussed in Section B, and may not be pursued further using the procedures for differing professional opinions.
Open Door discussions between employees and managers may also relate to subjects other than normal differing views and differing professional opinions.
In these cases, the managers contacted will work to resolve an employee's Lconcerns, to answer any questions, and to honor any request for anonymity.
Honoring a request for anonymity may, however, limit a manager's assistance.either to dis-cussions with the employee or to providing advice and counsel on matters of concern to the employee.
1 4
Managers should advise employees of the proper channels to be used for the resolution of concerns that may not be resolved using these procedures for differing professional opinions.
If the. contacted manager believes that others should be notified of issues raised in these Open Door discussions, he should notify offices with program-g matic responsibility, and others (e.g., the Office of Inspector and Auditor).
2.
The ACRS If the differing professional opinion relates to a potential safety issue within the purview of the Advisory Committee on Reactor Safe-guards, an NRC employee may communicate orally or in writing directly with the Chairman or any member of the ACRS.
Such com-munication may be anonymous.
The ACRS will append comments, as appropriate, to all referred statements of differing professional opinion and will forward these statements for resolution to the appropriate NRC office director.
An NRC employee may also appear before the ACRS or an ACRS Subcommittee as deemed appropriate by the Committee.
The ACRS will assure that all such statements that do not constitute a differing professional opinion are forwarded to the appropriate NRC office director for information.
I.
Prevention of Retaliation Against Individuals Who Express or Support Differing Professional Opinions Any NRC employee who retaliates against another employee for submitting j
or supporting a differing professional opinion is subject to disciplinary
/
action in accordance with Chapter NRC-4171 (Discipline. Adverse Actions and Separations).
This applies to retaliatory actions described in the 9
Approved: July 23,1985
L NRC Appendix 4125 '
DIFFERING PROFESSIONAL OPINIONS
(
following paragraph and to all prohibited personnel practices specified in Section 2302, Title 5, U.S. Code, as amended by the Civil Service Reform Act of 1978.
Retaliation consists of injurious actions taken against the originator of a
~
differing professional opinion in which a. motivating factor for such actions derived from the _ submission of a differing professional o~ pinion by the originator.
Retaliation may involve transfer; detail; ostracism; loss of staff assistance, space, or equipment;. physical isolation; the absence of assignments. involving. substantive work; or the. denial of promotion, attendance at professional society meetings, or justified training.
Employees who allege that retaliatory actions.have been taken because of their submission or support of a differing professional opinion may seek redress through the negotiated grievance procedure. or through the grievance procedure described in Chapter NRC-4157 (Employee Griev-ances). This is the formal route. Employees may also use the "Open Door Policy" as described in Section H.1 of this appendix.
In a case. where an employee files a grievance alleging that he/she has been~ retaliated against for having filed a DPO, the grievance may be reviewed initially by the same managers (usually lower level management) who allegedly have. engaged in retaliation.
- However, the agency grievance procedures provide for review of the allegation by higher level management.
In
- addition, grievants under agency practice and f
procedures have the right to present the issue to an independent third '
(
party-from outside the NRC; grievants covered by the negotiated Union Agreement may,. with the concurrence of the. Union, proceed to binding arbitration before a third party arbitrator from outside the NRC.
J.
Prevent Intentional Misuse of Procedures for Differing Professional Opinions No NRC' employee should intentionally misuse these procedures.
Examples of intentional misuse would include but not be limited to frivolous use, attempts to treat a personnel-grievance type action as a differing profes-sional opinion, and repeated attempts to use these procedures to obtain a resolution of views that do not satisfy the criteria for differing professional opinions.
K.
Special-Review Panel for Follow-up on Functioning of Differing Profes-sional Opinion Procedures Annually the Executive Director for Operations will appoint a Special Review Panel to evaluate and report on the functioning of these differing professional opinion procedures.
Four members of the Special Review Panel will be NRC employees (two managers and two nonmanagers), and the fifth member will be chosen from outside the NRC.
Two of the NRC-employee members will be selected from a list of at least five (5) candidates nominated by the National Treasury Employees Union (NTEU).
Membership shall not be limited to scientific or engineering personnel.
All NRC employees will receive a copy of the letter appointing members of the Special Review Panel.
The forwarding memorandum may also solicit Approved: July 23. 1985 10
.a DIFFERING PROFESSIONAL OPINIONS NRC Appendix 4125 employee' comments on these procedures to be considered by the Special Review Panel.
Employee recommendations for membership of subsequent Special Review Panels will also be solicited.
The Special Review Panel will study NRC's experience in handling differing professional opinions; evaluate the functioning. of these differing professional opinion procedures by assessing the degree to which the objectives are accomplished, and make appropriate recommendations for change.
The Special Review Panel may recommend decreasing the frequency of these reviews when evaluations indicate that the NRC procedures for ' differing professional opinions are functioning effectively.
The findings and recommendations of the Special Review Panel will be distributed simultaneously to the Commission, EDO, NRC employees and the public when the panel's deliberations are complete and before any revisions to Chapter NRC-4125 are initiated.
L.
Recognition of Originators of Significant Differing Professional Opinions In addition, the Special Review Panel described in Section K, above, will annually review all differing professional opinions submitted during the prior year to identify employees whose differing professional opinions made significant contributions to the agency or to public safety but who had not been recognized by his or her supervisor for this contribution.
It is anticipated that employees who provide significant contributions to j
the agency or to public health and safety will be recommended for appro-priate awards by their immediate supervisors.
Where award recommendations have not been made, they may be made by this Panel in accordance with provisions of NRC's Incentive Awards Program (Chapter NRC-4154).
Copies of such recommendations for award will be included in the Special Review Panel's written report to the EDO and the Commissioners.
i 11 Approved: July 23,1985
AggedW F e ac
/p oq,,
4 UNITED STATES w
~
. 1.'J : E NUCLEAR REGULATORY COMMISSION
. m i
OFFICE OF INSPECTION AND ENFORCEMENT
)
g,.-,.
/
Washington, D.C. 20555 INSPECTION AND ENFORCEMENT MANUAL DQAVT/DI CHAPTER 1245 INSPECTOR QUALIFICATIONS R
1245-01 PURPOSE To provide guidelines for the qualification of inspectors through regional, formal classroom, and on-the-job training.
1245-02 OBJECTIVES 02.01 To ensure that inspectors meet minimum knowledge and qualification standards.
02.02 To maintain inspector qualifications and training in general conformance to standards for comparable job activities in the nuclear industry.
02.03 To provide a standardized methodology for determining that an inspector has met the minimum training requirements.
1245-03 POLICY Inspector personnel must understand the facilities, processes, and activities for those areas they inspect in addition to the criteria, techniques, and mechanics of inspections.
Newly hired personnel seldom possess all of these required qualifications.
Therefore, formal class-room, self-study, and on-the-job training are needed to ensure that the newly hired inspector obtains the required knowledge and understanding necessary to be considered qualified to implement the IE inspection program.
Each inspector must complete the required training (outlined in Appendix A of this chapter) or verify (through successful completion of a written equivalency examination) thct he/she has the desired level of knowledge in his/her specialty.
The. passing grade for each course, series of courses, or equivalency examination is 70%.
Training activities for new inspectors will be documented in a Regional Training and Qualification Journal which encompasses regulatory, adminis-trative, and technical practices pertinent to each area of inspection.
Completion of a Regional Training and Qualification Journal and formal Issue Date:
AUG 011986
~
training courses- (or equivalency examinations) constitutes the minimum inspector qualification requirements.
Other requirements such as regional training may be used to-supplement or enhance training.
Once an inspector has completed the Regional Training and Qualification Journal and formal training courses, that inspector will be evaluated by an oral qualification board (Board).
Each region will constitute an oral qualification board for this purpose using the guidance in Section 08 of this manual chapter as minimum requirements for the Board.
In a situation where qualification is delayed'as a result of a inspector not being able to schedule certain formal training courses, or for.other
~ time restraint considerations, the Regional Administrator (or his delegate) or Office Director (or his delegate) may provide interim qualification for those areas where the inspector is considered qualified.
Approval author-ity for interim qualification can be delegated to the Division Director level.
Inspectors who are receiving on-the-job training and have not completed qualification can perform inspection activities under the direct instruc-tion of a qualified inspector.
With the exception of inspectors who are receiving on-the-job training, an inspector is expected to be qualified for the area being inspected.
In some cases where an inspector has taken most but not all of the required training, this may require the issuance of interim qualification.
An inspector who changes disciplines, for instance, a change from construc-tion to operations, must meet the training and qualification requirements for the new discipline.
In such cases, it is expected that similar train-b)
C ing requirements between the two disciplines will not have to be repeated.
The requirement for an inspector to be qualified by the process of an oral qualification board applies to those inspectors who have not been qualified by the issuance date of this manual chapter.
Special circumstances (e.g., loss of contracts or lack of instructors) may make it impossible to provide employees with required formal classroom training within the time frames specified in Appendix A.
When this occurs, the Director, Technical Training Center (TTC), will issue a memorandum to i
the regional training coordinators indicating the affected training
)
courses, circumstances involved, and reinstatement dates.
i i
1245-04 DEFINITIONS Course Series.
A progressive sequence of courses in a particular techno-logy for which a composite examination grade is given.
Equivalency Examination.
An examination administered through the Technical j
Training Center or its contractors in lieu of specific course attendance.
Observation Training.
A training / work assignment, for up to 6 months at a j
i utility facility.
On-Site Training.
Required training for resident inspectors designed to
?
V l
thoroughly acquaint these inspectors with specific site
- systems, structures, and management organization.
l Issue Date: g 0 1 N
-I-1245
)
Requirsd Training.
Formal classroom and on-th2-job training repressnting
.the minimum acceptable level of knowledge in a given field.
7 Supplemental Training.
Optional courses, depending'on the inspector's pre-e vious work experience and planned inspection activities that may be re-quired for performing inspections in specific areas.
Refresher Training.
Required training designed to update and maintain qualification.
IE Training and Qualification Journal.
A document that establishes the minimum training requirements for formal classroom -instruction, on-the-job training, local training sessions, and self-study.
This document serves as a guideline for developing regional ' training and qualification journals.
Regional Training and Qualification Journals.
Documents
-developed by regional offices to implement and document the minimum training require-i ments as outlined in the IE Training and Qualification Journal.
Oral Qualification Board..This Board consists of regional management and inspector personnel and meets for the purpose of reviewing and document-ing the qualification of an inspector to ' conduct the prescribed IE inspection program.
Interim Qualification.
Qualification of an inspector by the Regional' Administrator (or his delegate) or Office Director (or his delegate) to conduct independent inspections in specified areas of the inspection pro-gram before that inspector completes all required training.
1245-05 RESPONSIBILITIES AND AUTHORITIES i
05.01 Director, Technical Training Center.
Administers the training pro-gram and implements formal classroom and simulator training outlined in this chapter.
05.02 Directors, IE Divisions.
Assist the TTC in developing and main-taining the IE Training and Qualification Journal and inspector qualifi-cation policy.
05.03 Regional Administrator.
Ensures that inspectors achieve and main-tain qualifications in accordance with the guidelines provided in this chapter.
Develops regional procedures for the establishment and perform-ance of an oral qualification board to review and document an inspector's qualifications.
Certifies that an inspector is qualified to inspect specified areas.
This certification is usually based on the recommendation of an oral qualification board.
1245-06 TRAINING ACTIVITIES 06.01 All inspectors must successfully complete the training require-1 ments for their individual inspection areas as listed in Appendix A.
a.
Written examinations will be used to determine whether inspectors l
have obtained-the required 70% level of knowledge and understanding.
J l
1245 ' Issue Date: AUG 011986
=_-
b.
Inspectors who fail courses will be given the opportunity to acquire the knowledge level required through self-study and reexamination or to repeat the course as described in IE Manual Chapter 1249.
c.
NRC management assumes that inspectors possess the necessary moti-vation and ability to achieve such a level of knowledge and under-standing.
In the rare situation where such is not the case, management will decide what action to take on an individual basis.
~
06.02' Classroom. an'd simulator training are designed to suppiement the inspector's education, experience, and NRC on-the-job training by provid-ing basic theory and knowledge as well as job-related techniques.
1245-07 IE TRAINING AND QUALIFICATION' JOURNAL 07.01 The TTC is responsible for developing and maintaining the IE Training and Qualification Journal (IE Journal).
The use of the IE Journal is described in Appendix B of this chapter.
- 07.02 The IE Journal will provide the regions with a guideline to develop Regional Training and Qualification Journals.
Newly hired inspectors will then have a detailed series of activities and study areas to be completed in a specific period, usually within the first 2 years of employment.
The 1
journals cover self-study and seminars or group discussions in the areas of:
a.
Code of Federal Regulations m
b.
pertinent NRC and IE manual chapters
['/)
c.
technical areas of inspection, methods, and knowledge w,,
d.
schedule of orientation and required training as delineated in Appendix A 07.03 Assistance in development and maintenance of these journals will be provided by the regions and IE Divisions.
1245-08 ORALQUALIFICATIbNBOARDANDCERTIFICATION The oral qualification board (the Board) will be convened for the purpose of reviewing an inspector's completed training records and for determining, by the process of an oral examination, that the inspector meets the minimum knowledge and qualification standards specified in this manual chapter.
After the Board has completed its examination of an inspector, the Board i
i will determine whether or not an inspector meets the minimum qualifications required to be certified.
An acceptable decision by the Board will result in a favorable recommendation to the Regional Administrator.
Concurrence by the Regional Administrator, as certifying official, will be documented and a record kept in the inspector's training file.
This documents certi-fication of the inspector to conduct independent inspections.
The region will be responsible for establishing administrative procedures for the implementation and maintenance of a Board.
08.01 Board Members.
The minimum number of personnel required to consti-tute a Board should be three.
A cross section of qualified regional 4
gl01 M
- 1245 Issue Date:
parsonn21 should be includ d and can range from a pe:3r level inspector to a division director.
Regional management of at least the branch chief level q
should be included on each Board in addition to the inspector's immediate
)
supervisor.
08.02 Board Conduct.
The region should develop a list of review ques-tiens that include all areas of-the Regional Training and Qualification Journal.
These questions should allow and encourage the inspector to verbalize his/her depth of knowledge and-understanding of a given area, rather than questions that require a yes. or.no, type answer.
Major emphasis in questioning should be directed toward thosi situations that require the inspector to demonstrate his/her knowledge of NRC policy and philosophy. as it relates to the licensee and the. implementation of the inspection program.
.This should not exclude questions of a technical nature; however, since the inspector has already been tested in this area by the TTC. courses, it should not be a major area of questioning by the Board.
08.03 Board Documentation.
At the conclusion of each Board meeting, the Board should prepare a written recommendation to-the Regional Administra-tor.
The written recommendation will either recommend that the inspector-be certified as qualified or recommend that 'more training be given in a certain area.
This documentation should be entered into the inspector's training file in the region and at the TTC.
1245-09 INTERIM INSPECTOR QUALIFICATION 3'
09.01 An inspector who has not completed all requirements for final
/
certification in one of the areas listed in Appendix A may be qualified to perform independent inspections in specified areas.
09.02 To establish an interim certification, the inspector's supervisor 1
will evaluate his/her qualifications and identify the portions of the i
inspection program for which interim qualification is appropriate.
09.03 A request will then be generated through the individual's manage-ment for interim qualification in the identified areas.
The request l
should be approved by the Regional Administrator or the Office Director.
09.04 Approval of interim qualification will be documented and a record kept in the individual's training file.
END Appendices I
i I
1245 Issue Date: AUG 011986 I
1 I
1
^
}
APPENDIX A TRAINING ACTIVITIES A.
PURPOSE To identify those training activities necessary to ensure that inspectors:
1.
know the NRC role and mission 2.
understand the responsibilities and legal authority of an inspector 3.
know inspection techniques and procedures and are capable of per-forming the inspector function 4.
have the type and. level of technical knowledge needed to adequately perform inspection activities 5.
understand the inspection program
)
B.
BACKGROUND In general, only those inspectors wno have successfully completed the required training will be allowed to perform inspections.
However, if responsible management evaluates the background and performance of an R individual inspector and concludes that the inspector has demonstrated an ability to perform inspections in specific areas, even though the required training has not been completed, the Regional Administrator or Office R Director, as appropriate, can authori e the individual to perform inspec-R
. tions in those areas.
When this approach is used, the successful comple-tion of the training is still required within the time limits specified.
It is not the intent of this chapter to require persons to participate in each of the defined training activities if they already possess the type and level of knowledge that would be acquired by completing training.
If inspectors, when hired, through previous work experience and training, are deemed to possess the appropriate knowledge level, then equivalency exam-ination(s) may be taken and thereoy satisfy the training requirements.
TRAINING REQUIREMENTS C.
Each of the seven sections of this appendix provides the training require-ments for a particular inspection activity as indicated below.
1245 A-1 Issue Date:
AUG 011986
Section Inspection Activity
- I
- Radiological Safety Inspection-
^
II Reactor Operations, Resident and Region-Based Project Inspection III
. Reactor Construction, Resident Inspection
~
' IV Reactor Engineering Support Inspection V
Safeguards Inspectiore VI Vendor Inspection VII Emergency Preparedness Inspection
-VIII Reactor Design Inspection kk J
J p 01 M A-2 1245 Issue Date:
SECTION I
~
RADIOLOGICAL SAFETY INSPECTION TRAINING REQUIREMENTS FOR RADIATION SPECIALIST INSPECTORS A.
APPLICABILITY The training described below is required for all radiation specialist inspectors assigned to perform radiological safety inspection activities at reactor and fuel facilities and material licensees facilities.
B.
TRAINING 1.
Required Regional Training.
This training is conducted in the region using the Regional Training and Qualification Journal.
Regional Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Radiological Safety Inspection Accompaniments 2.
Required Training Courses. This training is coordinated through and
/
conducted by the Technical Training Center or its contractors.
Reactor Health Physics Insoectors (1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R (3) BWR/PWR Radwaste Course (H-302)
(4) Fundamentals of Inspection Course (G-101)
Fuel Facility Radiation Specialist Inspectors (1) Occupational Respiratory Protection Course (H-311)
R (2) Whole Body Counting / Internal Dosimetry Course (H-312)
R (3) Fundamentals of Inspection Course (G-101)
Materials Radiation Specialist Inspectors (1) Medical Uses of Byproduct Material Course (H-304)
R (2) Safety Aspects of Industrial Radiography Course (H-305)
(3) Fundamentals of Inspection Course (G-10'_)
3.
Supplemental Training Courses.
Depending on the inspector's pre-vious work experience and planned inspection activities, those optional courses are required for performing inspections in specific areas.
]
1245 A-3 Issue Date:
AUG 011986
Reactor Health Physics Insptctors-(1).Reactorf ealth Physics Technology Course (H-200)
H
-(2) Radiological Emergency Response Course (H-303) 4 (3) Radiological: Emergency Planning Course (H-306)
(4) Radiological Accident Assessment Course (H-307)
(5) Transportation of Radioactive Materials Course (H-308)
(6) Occupational Respiratory Protection Course (H-311)
(7) Whole Body Counting / Internal Dosimetry. Course (H-312)
R (8) Advanced Health Physics Course.(H-401)_
4 j
Fuel Facility and Materials Radiationc$pecialist Ingectors (1) BWR Technology Course (R-100 1evel)
R-
~
(2) PWR Technology Course (R-100 level)
.R (3) Reactor Health Physics Technology Course (H-200)
(4) BWR/PWR Radwaste Course (H-302)
(5) Radiological Emergency Response Course (H-303)
(6) Radiological Emergency Planning Course (H-306)
-(7) Radiological Accident Assessment Course (H-307)
(8) Transportation of Radioactive Materials Course (H-308)
(9) Advanced Health Physics Course (H-401)
R
^
i
, 4.
Refresher Training.
Appropriate refresher training for each inspec-R tor will be determined by regional management and will be documented R through the' Individual Development Plan'(IDP) process.
Reactor R Health Physics Inspectors are required to complete the Advanced R Health Physics Course (H-401).
R sn.
C.
EXCEPTIONS ALLOWED f'
i
%J 1.
Personnel assigned as radiation specialists after January 1,1984,
- must complete the training / qualification requirements for self-study, on-the-job training, and required training identified in the Regional Training and Qualification Journal.
Zi Inspectors who have been trained / qualified under existing regional journals do not have 'to requalify under the Regional Training 'and Qualification Journal.
3.
At the discretion of regional management, inspectors currently work-ing to complete their training /qualificatiN %1 der existing regional journals may transfer appropriate self" tut c on-the-job, and re-quired training courses to the Regianei Tr ;1ing and Qualification Journal.
D.
. TIME LIMITATIONS FOR COMPLETING TRAINING 1.
Required Regional Training and Training Courses.
All newly hired personnel and assignees are required to complete the required train-ing activities or take and pass equivalency examination (s) wit.hin the first 24 months after being assigned.
2.
Refresher Training.
Inspectors are required to co'plete refresher R m
training courses within 4 to 5 years after completion of required R training courses and every 4 to 5 years thereafter.
R
.s Mf A-4 1245 Issue Date:
SECTION 11 REACTOR-OPERATIONS, RESIDENT AND REGIONALLY-BASED PROJECT INSPECTION TRAINING REQUIREMENTS FOR'BWR OPERATIONS INSPECTORS A.
APPLICABILITY The training described below is required for all resident and regionally based project inspectors assigned to perform preopera'tional testing, start-up testi.1g and/or operational inspection activities at BWR facilities.
B.
TRAINING 1.
Required Regional Training.
This training is to be conducted at the site or in the region using the Regional Training and Qualification Journal.
Regional and/or Site Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Onsite Training Power Plant Inspection Accompaniments 2.
Required Training Courses. This training is coordinated through and conducted by the Technical Training Center or its contractors.
(1) BWR Technology Course Series (R-200 level, R-300 level, or R-400 R-level; R-500 level; and R-600 level)
(2) Fundamentals of Inspection Course (G-101)
(3) Radiation / Contamination Protection Course (G-102) or equivalent plant training 3.
Supplemental Training Courses.
Depending on the inspector's pre-vious work experience and planned inspection activities, these op-tional courses are required for performing inspections in specific areas.
(1) BWR Technology Course (R-200 level)
R (2) BWR Simulator Course (R-600 level)
R (3) GE Nuclear Engineering Course (R-801B)
(4) Reactor Health P,hysics Technology Course (H-200)
(5) Power Plant Engineering Course (G-110)
(6) Quality Assurance Inspection Course (G-303)
R (7) PRA Basics for Inspection Applications Course (G-500)
(8) Observation Training 4.
Refresher Training.
Refresher training will be conducted using a simulator or classroom course of the same vendor design as the 1245 A-5 Issue'Date: AL)G 011986 i
[
reactor to which the resident inspector is assigned.
If a simula-tor for.that specific design is not available for training, regional management will determine what available -refresher training is appropriate.
(1) BWR Simulator Refresher Course (R-700 level) or R
(2) GE Nuclear Engineering Course (R-801B) or (3) BWR Technology Course (R-200 level) or R
(4) BWR Advanced Technology Course (R-500 level)
R C.
EXCEPTIONS ALLOWED 1.
Regionally based project inspectors can satisfy BWR training re-quirements by successfully completing the required regional training identified in Section II.B.1(BWR) (this appendix) and the following training activities:
(1) BWR Technology Course (R-200 level or R-300 level)
(2) Fundamentals of Inspection Course (G-101)
(3) Radiation / Contamination Protection Course (G-102)
R (4) Those construction technology courses identified in Section III.B.2 (this ' appendix) that are pertinent to the inspector's area of inspection.
When individuals complete only the above-defined training activi-ties, they are restricted to assignment as regionally based project e
inspectors.
When assigned as a resident inspector, the training
[*)
identified in Section II.B.2(BWR) (this appendix) must be com-pleted.
If a new employee will eventually be assigned as a resident inspector, it is recommended that the training requirements identi-fied in Sections II.B.1 and 2(BWR) (this appendix) be completed as soon as'possible.
2.
Personnel assigned as resident or regionally based project inspec-tors at BWR facilitie's after October 1,1983, must complete the training / qualification requirements for self-study, on-the-job training, and required training identified in the Regional Training and Qualification Journal.
3.
Inspectors who have been trained / qualified under existing regional inspector journals do not have to requalify under the Regional Training and Qualification Journal.
4.
At the discretion of regional management, inspectors currently work-ing to complete their training / qualification under existing regional inspector journals may transfer appropriate self-study, on-the-job, and required training courses to the Regional Training and Qualifi-cation Journal.
5.
Inspectors who, through prior experience and education, possess suf-ficient knowledge to meet minimum requirements may validate a course by requesting an equivalency examination.
This request, from J
g 01 M A-6 1245 Issue Date:
~
i
'4 g
2 ths.-inspIctor's supervisor to the Dirrctor, TTC, should 'includ2 a
- summary of the relevant experience and education.
The Director, TTC, will determine if an' equivalency examination is appropriate.
t D.
TIME LIMITATIONS FOR COMPLETING TRAINING
' 1.
Required Regional' Training and Training Courses.
All newly hired personnel and new assignees are required to complete the required-training activities or take and pass equivalency examination (s) within the first 24 months after being assigned.
~
- 2.
Refresher Training.
Reactor operations resident and regionally-based project inspectors are required to attend refresher -training 24 to 30 months after completing required training and every 24 to 30' months thereafter.
This requirement must be met as long as the inspection ~ activities identified in Section II. A(BWR) (this appen-dix) are assigned.
TRAINING REQUIREMENTS FOR PWR OPERATIONS INSPECTORS A.
APPLICABILITY The training described below is required for all resident and regionally based project inspectors assigned to perform preoperational testing, start-up testing, and/or operational inspection activities at PWR facilities.
B. TRAINING 1.
Required Regional Training.
This training is to be conducted at the site or in the region using the Regional Training and Qualification Journal.
Regional and/or Site Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Onsite Training Power Plant Inspection Accompaniments 2.
Reauired Training Courses.
This training is coordinated through and i
conducted by the Technical Training Center or its contractors.
(1) PWR Technology Course Series (R-200 level, R-400 level, R-500 R
level, and R-600, level)
(2) Fundamentals of Inspection Course (G-101)
(3) Radiation Contamination / Protection Course (G-102) or equivalent plant training.
1 3
.1245 A-7 Issue Date AUG 011386 I
r
'3.
Supplemental Training Courses.
Depending on the inspector's pre-
~
. vious work experience and planned inspection activities, 'these op-tional. courses are required for performing inspections in specific areas.
(1) PWR Technology Course'(R-200 level)
R (2) PWR Simulator Course (R-600 level)
R~
-(3) Reactor Health Physics Technology Course (H-200)
R
.(4) Power Plant Engineering Course (G-110)
~
(5) Quality Assurance Inspection Course (G-303)
R (6) PRA Basics for Inspection Application (G-500)-
-R (7) Observation Training
- 4.
Refresher Training.
Refresher training will be conducted using a
-simulator of the same vendor design as the reactor to which the resident inspector.is assigned.
If a simulator for that specific design is not available for training,- regional management will determine if available refresher training is appropriate.
(1) WR Simulator Refresher Course (R-700 level) or R
(2) PWR Technology Course (R-200 level, R-300 level,or R-400 level)
R (3) PWR Advanced Technology Course (R-500 level)
R C. EXCEPTIONS ALLOWED 1.
Regionally based project inspectors can satisfy PWR training re-quirements by successfully completing the required ' regional train-ing identified in Section II.B.1(PWR) (this appendix)'and the following training activities:
(1) PWR Technology Course (R-200 level, R-300 level, or R-400 level) R (2) Fundamentals of Inspection Course (G-101)
(3) Radiation / Contamination Protection Course (G-102)
R (4) Those construction. technology courses identified in Section III.B.2 (this appendix) that are pertinent to the inspector's area of inspection.
When individuals complete only the above-defined training activi-~
ties, they are restricted to assignment as regionally based project inspectors.
When assigned as resident inspectors, the training identified in Section II.B.1(PWR) (this appendix) must be com-
.pleted.
If a new employee will eventually be assigned as a resident inspector, it is recommended that the training requirements identi-fied in Sections II.B.1 and 2(PWR) (this appendix) be completed as soon as possible.
2.
Personnel assigned as resident or regionally based project inspec-
-tors at PWR facilities after October 1,1983, must complete the
. training / qualification requirements for self-study, on-the-job training, and required training identified in the Regional Training and Qualification Journal.
~
J
~
g0}W 1245 Issue Date:
33
3.
Inspectors who have ban trained / qualified undar existing regional inspector journals do not have to requalify under the Regional m
Training and Qualification Journal.
.)
4.
At the discretion-of regional management, inspectors currently work-ing to complete their training / qualification under existing regional inspector journals may transfer appropriate self-study, on-the-job training, and required training courses to the Regional Training and Qualification Journal.
5.
Inspectorswho,throughpriorexperienceandeducatkon,possesssuf-ficient. knowledge to meet minimum requirements, may validate a
~
course by requesting an equivalency examination.
This request, from the inspector's supervisor to the Director, TTC, should include a summary of the relevant experience and education.
The Director, TTC will determine if an equivalency examination is appropriate.
D.
TIME LIMITATIONS FOR COMPLETING TRAINING 1.
Required Regional Training and Training Courses.
All newly hired personnel and new assignees are required to complete the required training activities or take and pass' equivalency examination (s) within the first 24 months after being assigned.
2.
Refresher Training.
Reactor operations resident and regionally R based project inspectors are required to attend refresher training R 24 to.30 months after completing required training and every 24 to R 30 months thereafter.
This requirement must be met as long as the R 3
inspection activities identified in Section II.A.(PWR)
(this appen-R
/
dix) are assigned.
)
1245 A-9 Issue Date:
AUG 011986
,J~,n-w
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SECTION III REACTOR CONSTRUCTION, RESIDENT INSPECTION TRAINING REQUIREMENTS FOR REACTOR CONSTRUCTION INSPECTORS A.
APPLICABILITY The training described below is required for all resident jnspectors assigned to perform construction inspection, activities at BWR and PWR facilities.
B.
. TRAINING 1.
Required Regional Training.
This training is to be conducted at the site or in the region using the Regional Training and Qualification Journal.
Regional and/or Site Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Onsite Training Construction Inspection Accompaniments
'2.
Required Training Courses.
This training is coordinated through and g.
conducted by the Technical Training Center or its contractors.
(-
s (1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R (3) Concrete Technology and Codes Course (C-302)
(4) Welding Technology and Codes Course (C-303)
(5) Electrical Technology and Codes Course (C-304)
(6) Instrumentation Technology and Codes Course (C-305)
(7) NDE Technology and Codes Course (C-306)
(8) Fundamentals of Inspection Course (G-101) 3.
Supplemental Training Courses.
Depending on the inspector's pre-vious work experience and planned inspection activities, these op-tional courses are required for performing inspections in specific areas.
(1) Inservice Inspection Course (C-308)
(2) Radiation / Contamination Protection Course (G-102) or equivalent plant training R
(3) Quality Assurance Inspection Course (G-303) 4.
Refresher Training.
Appropriate refresher training for each inspec-R tor will be determined by regional management and will be documented R R
through the Individual Development Plan (IOP).
J Issue Date: gg 011986 3 1o 1245 i
. ~.
C.
EXCEPTIONS ALLOWED e,
1.
Personnel assigned as resident inspectors after January 1,1984, 1
must complete the training / qualification requirements for sel f-study, on-the-job training, and required training identified in the Regional Training and Qualification Journal.
2.
Inspectors -who have been trained / qualified under existing regional inspection journals do not have to requalify under the Regional
. Training and Qualification Journal.
3.
At the discretion of regional management, inspectors currently work-ing to complete their training / qualification under existing regional inspector journals may transfer appropriate self-study, on-the-job training, and required training courses to the Regional Training and Qualification Journal.
D.
TIME LIMITATIONS FOR COMPLETING TRAINING 1.
Required Regional Training and Training Courses.
All newly hired personnel and new assignees are required to complete the required training activities or take and pass' equivalency examination (s) within the first 24 months after being assigned.
2.
Refresher Training.
Inspectors are required to complete refresher R training courses within 4 to 5 years after completion of required R training courses and every 4 to 5 years thereafter.
R 4
I i
/
1245 A-11 Issue Date:. AUG 01 386 I
SECTION IV REACTOR ENGINEERING SUPPORT INSPECTION TRAINING REQUIREMENTS FOR REACTOR ENGINEERING SUPPORT INSPECTORS A.
APPLICABILITY
'The training described below is required for all regional-ly based reactor engineering support inspectors assigned to perform construction,'preopera-tional testing, startup testing and/or operational inspections at BWR and PWR facilities.
B.
TRAINING 1.
Required Regional Training.
This training is to be conducted in the regions using the Regional Training and Qualification Journal.
Regional Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Inspection Accompaniments 2.
Required Training Courses.
This training is coordinated through and conducted by the Technical Training Center or its contractors.
p (1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R (3) Fundamentals of Inspection Course (G-101) 3.
Supplemental Training Courses.
Depending on the inspector's pre-vious work experience and planned inspection activities, these op-tional courses are required for performing inspections in specific areas.
For those inspectors whose specific duties involve inspec-tions at operating reactors, either a BWR or a PWR course series is strongly recommended.
(1) BWR Technology Course (R-200 level, R-300 level, or R-400 level) R (2) BWR Advanced Technology Course (R-500 level)
R (3) BWR Simulator Course (R-600 level)
R (4) GE Nuclear Engineering Course (R-801B)
(5) GE Maintenance Overview Course (R-8028)
R (6) PWR Technology Course (R-200 level, R-300 level, or R-400 level) R (7) PWR Advanced Technology Course (R-500 level)
R (8) PWR Simulator Course (R-600 level)
R (9) Reactor Health Physics Technology Course (H-200) or equivalent plant training (10) Concrete Technology and Codes Course (C-302)
(11) Welding Technology and Codes Course (C-303)
(12) Electrical Technology and Codes Course (C-304)
(13) Instrumentatien Technology and Codes Course (C-305)
V g 01 W A-12 1245 Issue Date:
-(14) NDE Tcchnolcgy and Ccdes Course (C-306)
(15) Inservice Inspection Course (C-308)
(16) Radiation / Contamination Protection Course
. -.]
(17) Power Plant Engineering Course (G-110)
R
~
(18) Quality Assurance Inspection Course (G-303)
R (19) PRA Basics for Inspection Applications Course (G-500)
R 4.
Refresher Training.
Appropriate refresher training for each inspec-R tor will be determined by regional management and will be documented R through the Individual Development Plan (IDP) grocess.
Examples R are:
R (1) BWR Simulator Refresher Course (R-700 level)
R (2) GE Nuclear Engineering Course (R-801B)
R (3) PWR Simulator Refresher Course (R-700 level)
R (4) GE Maintenance Overview Course (R-8028)
R C.
EXCEPTIONS ALLOWED 1.
Personnel assigned as regionally based reactor engineering support inspectors after January 1,1984, must complete the training /quali-fication requirements for self-study, on-the-job training, and re-quired training identified in the Regional Training and Qualifica-tion Journal.
l 2.
Inspectors who have been trained / qualified under existing regional inspector journals-do not have to requalify under the Regional Training and Qualification Journal.
3.
At the discretion of regional management, inspectors currently work-ing to complete their training / qualification under existing regional inspector journals may transfer appropriate self-study, on-the-job training, and required training courses to the Regional Training and 2
Qualification Journal.
D.
TIME LIMITATIONS FOR COMPLETING TRAINING 1.
Required Regional Training and Training Courses.
All newly hired personnel and new assignees are required to complete the required training activities or take and pass equivalency examination (s) within the first 24 months after being assigned.
2.
Refresher Training.
Inspectors are required to attend refresher training 48 months after completing the required training and every 48 months thereafter.
This requirement must be met as long as the inspection activities identified in Section IV. A (this appendix) are assigned.
i i
1245 A-13 Issue Date: AUG 01.986 4
I
. ~.
SECTION V SAFEGUARDS INSPECTION TRAINING REQUIREMENTS FOR SAFEGUARDS INSPECTORS A.
APPLICABILITY The-training described below is required of all safeguards ipspectors assigned to - perform physical security and mat,erial control and account-ability inspection activities.
B.
TRAINING 1.
Required Regional Training.
This training is conducted in the region using the Regional Training and Qualification Journal.
Regional Orientation Code of Federal Regulations Safeguards Inspection Procedures Regulatory Guides NRC/IE Manual Industry Codes and Standards Safeguard Inspection Accompaniments 2.
Required Training Courses.
This training is coordinated through and concuc ed by the Tecnnical Training Center or its contractors.
Physical Security Inspectors (1) Reactor Safety Systems and Vital Equipment for Safeguards R Personnel Course (S-401)
R (2) Fundamentals of Inspection Course (G-101)
(3) Radiation / Contamination Protection Course (G-102) or equivalent plant training (4) Industrial Facilities Protection Course (S-2105)
Fuel Facility Material Control and Accountability Inspectors (1) Fundamentals of Inspection Course (G-101)
(2) Radiation / Contamination Protection Course (G-102) or equivalent plant training (3) Basic Statistics Course (S-101A) or equivalent (4) Safeguards Chemical Analysis Course (S-401A) or equivalent R
(5) Fundamentals of Nondestructive Assay of Nuclear Materials Course R (S-602A)
R a
1245 Issue Date:
A-14
3.
Supplemental Trainino Cours1.
Dep;nding en th') insp;ctor's previcus
-work experience and planned inspection activities, these optional courses are-required for performing inspections in specific areas.
' Physical Security Inspectors (1) Reactor Concepts Course (G-100)
(2) Computer Security Course (5-2115) 4 (3) Intrusion Detection Systems - Operation and Maintenance Course (S-3205)
(4) Electronics for Electricians Course (S-3305)
Fuel Facility Material Control and Accountability Inspectors (1) Advanced Statistics Course (5-301A)
(2) Neutron Assay of Nuclear Material Course (S-603A)
(3) Gamma-Ray Assay of Nuclear Material-Course (5-604A) 4.
Refresher Training.
Appropriate refresher training for each inspec R
tor will be determined by regional management and will be documented R through the Individual Development Plan (IDP) process.
Inspectors R are encouraged to attend appropriate workshops and seminars, such R as, the Physical Security Workshop (American Society for Industrial R
Security) and the Protective Security Workshop (International Assoc-R
]
iation of Chiefs of Police).
R C.
EXCEPTIONS ALLOWED 1.
Personnel - assigned as safeguards inspectors after January 1,1984, must complete the training / qualification requirements for self-study, on-the-job training, and required training identified in the Regional Training and Qualification Journal.
2.
Inspectors who have been trained / qualified under existing regional inspector journals do not have to requalify under the Regional Training and Qualification Journal.
3.
At the discretion of regional management, inspectors currently work-ing to complete their training / qualification under existing regional inspector journals, may transfer appropriate self-study, on-the-job training, and required training courses to the Regional Training and l
[
Qualification Journal.
D.
TIME LIMITATIONS FOR C0MPLETING TRAINING 1.
Required Regional Training and Training Courses.
All newly hired personnel and assignees are required to complete the required train-ing activities or take and pass equivalency examination (s) within the first 24 months after being assigned.
2.
Refresher Training.
Inspectors are required to complete refresher R training courses within 4 to 5 years after ccmpletion of required R training courses and every 4 to 5 years thereafter.
R 4
i 1245 A-15 Issue Date:
AUG 011986 i
SECTION VI VENDOR INSPECTION TRAINING REQUIREMENTS FOR VENDOR INSPECTORS A.
APPLICABILITY The training described below is required for all vendor in'spectors". assigned to perform architect and engineer (A&E), nuclear steam system supplier R (NSSS), equipment qualification (EQ), or component inspection activities.
R B.
TRAINING 1.
Required Training.
This training is to be conducted at IE (Head-R quarters) using the IE Training and Qualification Journal.
R Administrative Orientation R
Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Vendor Inspection and Accompaniments Document Control System (DCS) - User Training Course R
2.
Required Training Courses (Special Project Section Inspectors).
R This training is coordinated through and conducted by the Technical R
Training Center or its contractors.
R (1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R (3) Fundamentals of Inspection Course (G-101)
(4) Technology Courses (e.g. welding, NOE, instrument technology) as R determined by VPB management depending on area of assignment, R
previous training,,and experience.
R 3.
Required Training Courses (Reactive Section Inspectors and Program R Coordination Section Inspectors).
This training is coordinated R through and conducted by the Technical Training Center or its con-R tractors.
(1) BWR Technology Course (R-100 level) or PWR Technology Course R (R-100 level)
R (2) Fundamentals of Inspection Course (G-101)
R (3) Technology courses (e.g. welding technology, electrical techno-R
~
logy) as determined by VPB management depending on area of R assignment and previous training and experience.
R 4.
Required Training Courses (Equipment Qualification Section Inspec-R tors).
This training is coordinated through and conducted by the R Technical Training Center or its contractors.
R (1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R
~~<
i lUdI5f A-16 1245 Issue Date:
- ~.
(3) Fundamentals of Insp;ction Course (G-101)
R (4) Electrical Technology and Codes Course (C-304)
R (5) Instrumentation Technology and Codes Course'(C-305)
R 5.
Supplemental' Training Courses (All Sections).
Depending on the in-R spector's previous work experience and -planned inspection activi-ties, these optional courses are required for performing inspections in specific areas.
(1) Radiation Contamination Protection Course (G-102) or equivalent
~
I plant training l.
(2) Power Plant Engineering Course (G-110)
R (3) Quality Assurance Inspection Course (G-303)
R (4) PRA Basics for Inspection Applications (G-500)
R (5) BWR or PWR Technology Course (R-200 level,-R-300 level, or R-400 R level)
R (6) BWR or PWR Advanced Technology Course (R-500 level)
R (7) BWR or PWR Simulator Course (R-600 level)
R 6.
Refresher Training.
Appropriate refresher training for each inspec-R i
tor will be determined by VPB managn.ent and will be documented R through the Individual Development Plan (IDP) process.
R C.
EXCEPTIONS ALLOWED 1.
Personnel assigned as vendor inspectors after January 1,1984, must l
complete the training / qualification requirements for self-study, on-R
}
the-job training, and required training courses identified in the R Vendor Inspectors Training and Qualification Journal.
R 2.
Inspectors who have been trained / qualified under existing regional R
~
l[
inspector journals may transfer applicable sections of their exist-R ing qualification to the Vendor Inspectors Training and Qualifica-R tion Journal.
R i
j.
3.
At the discretion of VPB management, inspectors who are currently R working to' complete or.have completed their training / qualification R under existing regional inspector journals may transfer appropriate self-study,on-the-job training, and required training courses to R j
the Vendor Inspector Training and Qualification Journal.
R D.
TIME LIMITATIONS FOR COMPLETING TRAINING
.'j i
1.
Required General Training and Technical Training Courses.
All newly R hired oersonnel and new assignees are required to complete the re-quired training activities or pass equivalency examination (s) within the first 24 months of assignment.
l 2.
Refresher Training.
Inspectors are required to complete refresher R training courses within 4 to 5 years after completion of required R j'
training courses and every 4 to 5 years thereafter.
R i
l j.
AL)G 011986 1245 A-17 Issue Date:
_ _ _... _ _ _ _ _., _ _ _ _ _ _.. _ _ _. _.. ~ _ - - _.,. _ _. - - - _ -
SECTION VII EMERGENCY PREPAREDNESS INSPECTION TRAINING REQUIREMENTS FOR EMERGENCY PREPARE 0 NESS INSPECTORS A.
APPLICABILITY The training identified below is required for all emergency preparedness analysts / radiation specialist inspectors assigned to perform emergency preparedness inspection activities.
B.
TRAINING 1.
Required Regional Training.
This training is to be conducted in the region using the Regional Training and Qualification Journal.
Regional Orientation Code of Federal Regulations Final Safety Analysis Report Regulatory Guides NRC/IE Manual Industry Codes and Standards Emergency Preparedness Inspection Accompaniments 2.
Required Training Courses.
This training is coordinated through and conducted by the Technical Training Center or its contractors.
(1) BWR Technology Course (R-100 level)
R (2) PWR Technology Course (R-100 level)
R (3) Fundamentals of Inspection Course (G-101)
(4) Radiation / Contamination Protection Course (G-102)
R 3.
Supplemental Training Courses.
Depending on the inspector's pre-vious work experience and planned inspection activities, these op-tional courses are required for performing inspections in specific areas.
(1) Reactor Health Physics Technology (H-200)
(2) Radiological Emergency Response Course (H-303)
(3) Radiological Emergency Planning Course (H-306)
(4) Radiological Accident Assessment Course (H-307)
(5) Health Physics in Radiation Accidents (REAC/TS) (H-309)
(6) Management Oversight and Risk Tree (MORT) Analysis Seminar (G-201) 4.
Refresher Training.
Appropriate refresher training for each inspec-R tor will be determined by EPB management and will be documented R through the Individual Development Plan (IDP) process.
R C.
EXCEPTIONS ALLOWED 1.
Personnel assigned as emergency preparedness analysts / radiation specialist inspectors after January 1,
1984, must complete the s
i k
A-18 1245 Issue Date:
training /qualificaticn r quirements for s21f-study, cn-the-j b training, and required training courses identified in the Regional q.
Training and Qualification Journal.
t 2.
Inspectors who have been trained / qualified under existing regional inspector journals do not have to requalify under the Regional-Training and Qualification Journal.
3.
At the discretion of regional management, inspectors. currently work-ing to complete their training / qualification under ekisting regional inspector journals, may transfer appropriate self-study, on-the-job training, and required training courses to the Regional Training and Qualification Journal.
' O.
TIME LIMITATIONS FOR COMPLETING TRAINING 1.
Required Regional Training and Trainino Courses.
All newly hired personnel and assignees are required to complete the required train-ing activities or take and pass equivalency examination (s) within the first 24 months after being assigned.,
2.
Refresher Training.
Inspectors are required to complete refresher R training courses within 4 to 5 years after completion of required R training courses and every 4 to 5 years thereafter.
R
- t O
4 t
i L
9 4
1245 A-19 Issue Date:
AUG 01 1986
SECTION VIII R
REACTOR DESIGN INSPECTION i
TRAINING REQUIREMENTS FOR REACTOR DESIGN INSPECTORS A.
APPLICABILITY The training described below is required for all reactor design. inspectors assigned to perform Integrated Design Inspections (IDIs), Readiness Review Program design reviews, Independent Design Verification Program inspec-tions, Engineering Assurance Program inspections, and the design aspects of modifications made during an outage, and Safety System Functional inspections.
B.
TRAINING 1.
Required Training.
This training is to be conducted at IE (Head-quarters) using the Reactor Design Inspectors Training and Qualifi-cation Journal.
(1) General Orientation (2) Code of Federal Regulations (3) Final Safety Analysis Report (4) Regulatory Guides (5) NRC/IE Manual (6) Industry Codes and Standards (7) Design Inspection Orientation (8) Document Control System (OCS) - User Training Course Q,
2.
Supplemental Training.
A prerequisite for assignments as a design inspector is extensive design experience with nuclear architect engineering firms, nuclear steam supply system companies, or other areas of the nuclear industry performing original design work.
The following technical training courses are recommended as supple-mental courses and should be incorporated in the individual devel-ment plans, as appropriate.
This training is coordinated through and conducted by the Technical Training Center or its contractors.
These courses also may be specified by QAB management as required refresher courses for individual inspectors.
(1) BWR Technology Course Series (R-200, 300, or 400 level; R-500 level; and R-600 level)
(2) PWR Technology Course Series (R-200, 400 level, R-500 level, and R-600 level)
(3) Fundamentals of Inspection Course (G-101)
(4) Quality Assurance Inspection Course (G-303)
(5) PRA Basis for Inspection Applications (G-500)
(6) Electrical Technology and Codes Course (C-304)
(7) Instrumentation Technology and Codes Course (C-305)
C.
EXCEPTIONS ALLOWED 1.
Personnel assigned as design inspectors must complete the training /
s qualification requirements for self-study, on-the-job training, and K01 W A-20 1245 Issue Date:
~
required training courses identificd in the Reactor D2 sign Insp;c-tors Training and Qualification Journal.
l 2.
Inspectors who have been trained / qualified under existing regional 7 inspector journals may transfer applicable sections of their exist-ing qualification to the Reactor Design Inspectors Training and Qualification Journal.
3.
At the discretion of QAB management, inspectors who are currently working to complete or have completed their. training / qualification under existing regional inspector journals may transfer appropriate self-study, on-the-job training, and required training courses to the Reactor Design Inspector Training and Qualification Journal.
D.
TIME LIMITATIONS FOR COMPLETING TRAINING Required General Training and Technical Training Courses.
All newly hired personnel and new assignees are required to complete the required training activities or pass equivalency examination (s) within the first 24 months of assignment.
The corresponding time limit for current inspectors is January 1988.
1 1245 A-21 Issuebate: AUG 011986
-O
.p.
m
.)
APPENDIX B IE TRAINING AND QUALIFICATION JOURNAL A.
PURPOSE To establish a method of conducting and documenting successful completion of the training requirements set forth in this manual chapter.
B.
BACKGROUND The IE Training and Qualification Journal (IE Journal) is designed to ensure that a uniform method of conducting and documenting training is being fol-lowed for all inspectors.
The IE Journal establishes the minimum training requirements that must be met for all required general and formal training courses listed in R Appendix A and serves as a guide for development of other training and R qualification journals (i.e., regional and vendor journals).
R C.
BASIC REQUIREMENTS The IE Journal must be used to conduct and document training activities for R all inspectors.
The Technical Training Center (TTC) is responsible for developing and main-taining the IE Journal.
Each regional office is responsible for developing and maintaining its Regional Training and Qualification Journal and noting completion of the regional journal in each inspector's personnel record.
The TTC, Vendor Program Branch, and regions will develop and make available R applicable journals according to the following schedule:
Regional / Design /
Title IE Journal Vendor Journal R
Radiological Safety Inspectors 07/01/83 01/01/84 Reactor Operations, Resident and 04/01/83 10/01/83 Region-Based Project Inspectors Reactor Construction, Resident 07/01/83 01/01/84 Inspectors Reactor Engineering Support 09/01/83 01/01/84 Inspectors Safeguards Inspectors 09/01/83 01/01/84 Vendor Inspectors 09/01/83 07/01/85 R
Emergency Preparedness Inspectors 09/01/83 01/01/84 Reactor Design Inspectors 09/01/83 01/15/86 R
i c
Issue Date:
AUG 011986 B-1 1245 I
M% k
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UNITED STATES e
(
2 NUCLEAR REGULATORY COMMISSION
^.
1 3
OFFICE OF INSPECTION AND ENFORCEMENT
\\,, v,/
Washington, D.C. 20555 INSPECTION AND ENFORCEMENT MANUAL DQAVT CHAPTER 1249 TECHNICAL TRAINING CENTER POLICY 1249-01 PURPOSE To publish the policy of the Technical Training Center (TTC) in implemen-ting the requirements of IE Manual Chapter 1245.
1249-02 OBJECTIVES To ensure that NRC employees understand: (1) the organization and function of the TTC, (2) the mechanics of scheduling TTC training courses, (3) the general TTC policies on the conduct of TTC training courses, (4) the re-quirements for continuation through a reactor technology course series, (5) the TTC policy for giving equivalency examinations and reexaminations, (6) the program for observation training at the TVA sites.
~
1249-03 RESPONSIBILITIES AND AUTHORITIES The TTC organization includes a Director, an administrative staff, a Boil-ing Water Reactor (BWR) Technology Branch, a Pressurized Water Reactor (PWR)
Technology Branch, and a technical support group as shown in the attached organization chart.
03.01 Director, TTC a.
Develops and implements the policies and programs for training NRC inspectors and provides technical training for NRC personnel and foreign nationals as requested.
b.
Provides training to initially teach and continually maintain IE inspector and other NRC staff personnel with the level of knowledge of BWR/PWR technology needed to perform their assigned job func-tions.
c.
Provides expert technical assistance to IE and cther NRC personnel in the area of BWR/PWR operation, system design, instrumentation and control.
d.
Periodically assesses the regional implementation of the training required by MC 1245.
M Issue Date:
03.02 Chief. 8WR Technology Branch a.
Directs the work within the BWR Technology Branch.
b.
Develops and implements programs to initially teach and continually maintain NRC inspectors and other NRC technical staff with the level of knowledge of. BWR technology needed to perform their assigned
-functions.
Provides expert technical assistance to the NRC technicil staff in c.
the area of BWR operation, system design, and control.
03.02 Chief, PWR Technology Branch a.
Directs the work within the PWR Technology Branch.
b.
Develops and implements programs to initially teach and continually maintain NRC inspectors and other NRC technical staff with the level of knowledge of PWR technology needed to perform their assigned functions.
c.
Provides expert technical assistance to the NRC technical staff in the area of PWR operation, system design and control.
03.04 Senior Program Manager a.
Manages, develops, implements, and reviews specialized technical training programs for professional employees.
b.
Acts as project officer for contracted specialized technical train-(~)
ing courses covering a broad range of engineering disciplines.
1249-04 POLICY 04.01 The standard course hours for all classroom courses are 7:30 AM to 4:15 PM.
Hours for other types of courses such as 600/700 level simulator courses depend on the availability of simulator time.
The actual course hours for all courses will be promulgated in the standard course letter to course participants.
04.02 All students should be removed from compressed work schedules for the pay period (s) during which the student will attend TTC courses.
In the unlikely event that TTC courses must be scheduled over a holiday, students would be required to attend on the holiday.
04.03 Students attending TTC courses are generally unavailable to their office during classroom hours.
Students will not be called out of the class for telephone messages unless the message is dealing with a personal ur family emergency.
A message will be taken for all other incoming calls.
Such messages are posted on a bulletin board; students may return calls during breaks between classroom presentation and after class has ended for the day.
Calls which are to be returned during break periods should be sufficiently short to allow the student to return to the classroom before s
AUG 0119W
. Issue Date:
2-m9
1 7
class resumes.
This is necessary to ensure that the student receives the
- maximum benefit from the training and other students are not distracted by 8
late arrivals.
l
_ 04.04 Examinations are given at the end of most of the TTC courses.
. Students required by MC 1245 (or other formal requirement) to complete a course as part of their qualification must pass the examination.
The pass-ing grade for all-TTC courses is 70%.
For those courses in which an exam-ination is given, all students must take the examina. tion.
After the course examinations have been graded course reporting letters with actual course grades will be sent to the appropriate region or program office and to the student.
The examination results will indicate only the knowledge level of a student at the conclusion of the course and the numer-ical grade should not be used as a performance indicator.
04.05 Examination results are normally considered final.
If a question concerning the grading of an examination arises, the examination will be regraded provided:
a.
The examination has been discussed with the student's management.
b.
The student's management requests the regrading of the examination in writing, to the appropriate TTC Branch Chief.
c.
The original examination is returned to the TTC.
(Under no circum-stances will a copy of the examination be regraded.)
7 The complete examination will be regraded by an instructor who was not
/
associated with the original examination.
The regraded examination will be considered as the final grade for the examination and will be returned to the student's management.
04.06 For all students who satisfactorily complete the course (or course series), the course reporting letter will reflect that the minimum course (or course series) requirements were met.
For students with a course or course series grade less than 70%, the course reporting letter also will identify to the immediate supervisor those areas in which the student needs additional attention so that the appropriate upgrading program can be plan-ned and implemented.
1249-05 SCHEDULING OF TTC COURSES 05.01 The TTC course schedule is published semiannually as a memorandum ~
from the Director, TTC to all NRC employees.
This memorandum gives a chronological and topical listing of the courses offered by or through the TTC.
05.02 Each of the courses mentioned in this memorandum is described in the Guide to Training Opportunities (Addendum).
This syllabus presents stand-ardized information for each course, including prerequisites for attend-ance.
Students who do not meet these prerequisites should not be scheduled into these courses.
1249 Issue Date:
05.03 Changes to the TTC course schedule will be made as needed to reflect course data changes, course additions, or course cancellations.
Such noti-fication will be made in memorandum form and will be promulgated to train-ing coordinators.
05.04 All scheduling of students into TTC courses will be done by the training coordinator of the region or NRC office concerned.
Individual supervisors who want their personnel assigned to a given course must do so through their appropriate training coordinator.
05.05 The maximum and minimum class sizes for the various reactor tech-nology courses offered by the TTC are listed below.
The normal TTC policy will be to cancel such courses if the projected attendance is below the minimum one week before the course starting date.
Course Maximum Size Minimum Size 100 Level 24 16 200 Level 18 12 300 Level 18 12 500 Level 18 N/A 600 Level 6
4 700 level 6
4 900 level 8
6 BWR/PWR Radwaste 24 12 05.06 Given that maximum class sizes have been established, that the various regions have extensive training needs, and that IE headquarters
~
and other program offices have training needs, it has been necessary to allocate a fixed number of slots to the regions for certain of these courses.
Allocation of slots which will generally apply for these courses is as follows:
Course I
II III IV/V* IE AE00 NRR Remaining 100 Level 4
4 4
4 2
1 1
4 200 Level 3
3 3
3 2**
1 1
2 300 Level 3
3 3
3 2**
1 1
2 500 Level 3
3 3
3 2**
1 1
2 6
BWR/PWR Radwaste 4
4 4
4 The remaining slots identified above can be used by the program offices (with general priority to IE and NRR for 100 level courses and with about equal priority for course series slots).
Those slots not used by the pro-gram offices will be offered to the regions.
The TTC has established this policy of allocating slots to enable the regions and program offices to better plan the schedules of their employees.
Only in the most unusual of circumstances will a region not be given all the slots normally allocated for a given course.
e
- Regions IV and V will be offered the total number of slots indicated.
- IE will receive an additional slot for a HQ Operations Officer in every t
other series.
Issue Date: AUG 01 1986 '
1249
05'.07 The procedura us;d to sch:dule studints into available slots will be as follows.
Approximately 6 weeks before a given course begins, a TTC J
Course Registration Form (attached) indicating the distribution of slots
^
i
)
for each region / office will be transmitted to the training coordinators.
When the region or program office receives notification of the number of slots it has been allocated for a given course, efforts should be initiated to (1) select the students to fill the slots, (2) have the students initi-ate their travel requests, and (3) notify the TTC of the names of the students attending the course.
Approximately 4 weeks before a course begins, the names of the course students should have beert received by the TTC and the standard course letter will be mailed out.
Any slots for which names have not been assigned will be considered open and will be made available to the other regions or program offices.
Once a slot for a given course has been lost by failure to give the TTC the name of the student (4 weeks prior to the course), it cannot be reclaimed if it has been filled by another region or office.
I Personnel filling these slots will be in a student status at the TTC courses and will be expected to fully participate in all assigned activi-ties and to take any required examinations.
There will be no observers at the TTC courses with the exception of certain' personnel sent through the Office of International Programs.
1249-06 REACTOR TECHNOLOGY COURSE SERIES 06.01 The Reactor Technology Course Series consists of a 200 or 300 level
]
Technology Course followed by a 500 level Advanced Technology Course fol-
/
lowed by 600 level Simulator Course.
The slot allocations for these courses are made for the entire series.
i Supervisors should realize that if an employee is scheduled into a series, a commitment has been made for that person to be a student in the Technol-ogy Course (2 weeks or 3 weeks), the Advanced Technology Course (2 weeks),
and the Simulator Course (1 week).
06.02 Once scheduled, students should not be withdrawn from a course series except for personal emergencies.
In the event that a student has to be withdrawn from a series, the region or program office will retain the slot, which can be filled by any of its qualified personnel.
Students joining a series must meet the specific course prerequisites of the sylla-bus.
Supervisors should recognize that once someone is pulled from a course series, it will be difficult to get that student into another series.
06.03 The above policy on continuation through a course series applies only to those cases where the student's course grades are high enough to warrant continuation.
There will be situations, however, when a student's course examination grades are inadequate to justify continuation through the series, j
The specific requirements on examination grades for continuation through a course series are as follows:
A M 01 g 1249 Issue Date:
[
~
a.
For'a student who has attended the 200/300 level Technology Course-to proceed to the 500 level Advanced Technology Course, the course
. grade for the 200/300- level Technology Course must be at least 65%.
Experience has -shown that students making less than 65% in the systems course rarely. bring their grade 'up and pass the series.
b.
For a student who~has attended the 200/300 level Technology Course and the 500 level. Advanced. Technology Course to proceed to the 600 level Simulator. Course, the course grades for the. first t.wo courses must be at least 65% and the average of the first two courses must be at least 70%.
c.
If. these requirements are not met, the student will not proceed to the next course of the series.
Students who - are dropped from a course series after the first course, because of the grade criteria specified above, may be scheduled into a later course series starting with the first course of the ocw series.
i They also may be reinserted into a later course series beginning with the second course of the series if they are certified for the first course in the interim.
Such students can become certified by successfully completing a reexamination of the first course, if they meet the eligibility require-ments specified in Section'08 below.
Students who do not meet the requirement for. proceeding beyond the second course of the series will be dropped from the current series.
They may be scheduled into a later course series.
If they had successfully passed-the first course, they may start with the second course of the new series (if there is a slot open).
These students also may be reinserted into a later r*
course series beginning with the third course of the series if they are
(')
certified for the second course of the series by successfully completing a reexamination of the second course and providing they meet the eligibility requirements specified in Section 08 below.
1249-07 EQUIVALENCY EXAMINATIONS 07.01 Equivalency examinations may be given to certain personnel who meet the requirements of IE ' Manual Chapter 1245 for the purpose of validating certain stand-alone courses or courses of the Reactor Technology Course Series.
Such equivalency examinations must be requested in writing by the student's immediate supervisor in a memorandum to the Director, TTC.
These requests must include detailed remarks on the individual's prior experience and/or education to allow the Director, TTC to make a decision regarding an equivalency exam.
Experience has shown that an individual should not validate both the 200/
300 level Technology Course and the 500 level Advanced Technology Course.
Even experience as a senior reactor operator on an operating plant has not guaranteed a background suitable for validating both of these courses.
The TTC recommends that even individuals with excellent backgrounds validate
.only the first course of a series.
07.02 Equivalency examinations, if approved by the Director, TTC, will be given under the following conditions:
J Issue Date: 1249 y
~.
a.
-Students validating 'a 200/300 level Technology Course may take the equivalency examination at the TTC.
The TTC will consider requests
]1 -
for the equivalency examination to be given in the regional office or program office on the regular examination day for the course that is being validated.
b.
Students ' authorized to validate both the 200/300 level Technology Course and the 500 level Advanced Technology Course may do so indi-
.vidually or simultaneously. If the validation is to.be done individ-ually, the equivalency examination for each of the course', will be taken at the TTC (or at the employee's office if approved) on the regular examination day for each course that is being validated.
If i
simultaneous validation is to be attempted, then a comprehensive equivalency examination will be taken at the TTC on the regular examination day for the 500 level Advanced Technology Course which is being validated.
c.
Students validating a 100 level Technology Course (or any other non-series course) may take an equivalency examination either at the TTC or in the employee's office at a time agreed upon by the student's immediate supervisor and the TTC.
d.
Students validating required contractor courses may take an equival-ency examination either at the TTC or in the employee's office at a time agreed upon by the student's immediate supervisor and the TTC.
07.03 The requirements of the section on continuation through a Reactor 4
Technology Course Series also apply to students who attempt to validate 3l the first or the second course of the series.
)
i 1249-08 REEXAMINATIONS 2
08.01 Written reexaminations may be given to students who receive failing grades on a non-series course or a given course of a Reactor Technology
]
Course Series, subject to the following limitations:
a.
No reexamination will be given to a student who receives a course grade of less than 50%.
In this situation, the only way to get the student certified for that particular course is to have the individ-ual repeat the entire course.
b.
No reexamination will be given, regardless of the grade, if the course which has been failed is not required training for the indi-vidual as specified in the manual chapter applicable to that indi-vidual, unless a request is received from the student's management.
c.
No reexamination will be given to a student who scores less than 70% on one course of a course series but otherwise has a passing average (70%) for the series.
l d.
Only one reexamination will be given to a student for any given course.
A student who fails a reexamination must repeat the course to satisfy the training requirement.
i, l
M l
1249 Issuo Date:
- ~ - - - -. -
u t t. -
f
.I b
08.02 Reexamination for students who meet the above' eligibility require' ments must be requested in writing by the student,b. management in a memo-randum or letter to the Cirector, TTC.
Such regbests imust be received'by the TTC within 30 working days from the date the.exanination letter identi-fying the failure was mailed to the student and /mmediate supervisor.
A prepared reexamination will then be mailed with' a cover letter. signed"by the Director, TTC, to the student's immediate supervisor.
This letter will $
indicate 'how the. reexamination should be administered.
The completid re6 examination should be returned to the Director, TTC, withfin.3 weeks of the
date of receipt.
c 08.'03 The student will be certified as having completed;the course if the reexamination raw grade is greater than or equal to 70%.
The maximum. grade recorded for any reexamination.is 70% no matter how high the raw nrade' might be.
A 70% grade will be' entered into the student's record (ahif for purposes of course series grade computation) for all reexaminations of this type which have been passed.
/
^
1249-09 OBSERVATION TRAINING 09.01 Observation training is available on a limited basis at certain nuclear power plants.
The NRC presently has an agreement with TVA so that up to two NRC people at a time can be assigned this observation training at' three different TVA sites.
The length of time for this' observation train-ing is 6 months.
The TVA sites for which this is possible are'Soquoyah (Westinghouse PWR), W.ntts Bar (Westinghouse PWR), and Browns Ferry (GE BWR).. During this observation trainingi thr, NRC employees rotate among the different TVA organizations on site and work with the TVA staff.
Such i
i observation training allows the NRC Amploye6s a rare opportunity to learn
\\,, )
the different aspects of a nuclear puer plant organizatinn.
09.02 Observation training will generally be given only to NRC personnel who have completed at least a 100 'levelgeactor Technology Course appli-cable to the plant where theys will be. stationed.
Observation training should be requested by manageraent in' a letter or memorandum to the Director, TTC.
Scheduling of this observation training and notification of appropriate TVA officials will be handled by the TTC on a first-come-first-served basis until the demand for these slots exceeds the slot availability.
Each region will be allotted only two observation slots unless the other regions do not fill the slots.
The starting dates for the observation training at a site may be staggered at the discretion of 'the:TVA site management or TTC management.
i I
1249-10 SPECIAL PROJECTS COURSES i
10.01 Course hours for courses presented at the TTC will follow the gen-eral TTC policy.
Hours' for courses presented at a contractor's facility or course sponsored by another agency will b'e set by the contractor or sponsoring agency.
The passing gra.de for all TTC contracted courses is 70%.
Course results will be reported in accordance with the general TTC policy.
10.02 The TTC Management Assistant will coordinate attendance for all such courses controlled by the TTC.
Sloi.s will be allocated in a manner similar V
i gyG 01 W
' 1249 Issue Date:
to that used for the reactor technology courses.
Training Coordinators should provide the TTC Management Assistant with the names of the course N. -
attendees.
Maximum class sizes are generally set by the contractor or by
./
the sponsoring agency.
Decisions to cancel a scheduled course will be made on case-by-case basis, considering factors such as the number of attendees, course cost, etc.
10.03 Reexaminations and equivalency examinations will be handled in accordance with the general TTC policy.
END Attachments l
1249 Issue Date: AUG 01 1986
1
?
TECHNICAL TRAINING CENTER Director
---~
Senior Program Manager Management Assistant Training Specialist Secretary / Receptionist *
~
4 BWR TECHNOLOGY BRANCH PWR TECHNOLOGY BRANCH Chief Chief Lead Instructors Lead Instructors Instructors Instructors Secretary Secretary
- Fulltime temporary s
1249 A-1 Issue Date:
AUG 01 1986
d.
TTC COURSE REGISTRATION FORM ALLOCATION OF COURSE SLOTS Cturse No.
Course
Title:
Cturse Dates:
Course Location:
~.
Office /
Office /
Slot No.
Region Name Slot No.
Region Name 1
13 2
14 3
15 4
16
-5 17 6
18 7
19 8
20
/-
k 9
21 10 22 11 23 12 24 The individuals designated for our assigned slots are indicated above.
Il cdditional slots are unfilled, we would be willing to send those individuals licted below. Those individuals assigned to a course which is part of a series cro cosanitted to attend the full series.
l Training Coordinator ALTERNATES:
I
- 2..
J.
3.
g 0 1 1986 Issue Dats:
1249 A-2
p___ y
~
d REACTOR OPERATIONS, RESIDENT AND REGION-BASED PROJECT INSPECTORS IE TRAINING AND QUALIFICATION JOURNAL Acolicability This IE Training and Qualification Journal (IE Journal) es based project inspectors assigned to perform preoperational testing, startup testing, and/or operational inspection activities.
The IE Journal serves as a guideline for development of a Regional Training and Qualification Journal (Regional Journal), used to implement the minimum The Regional Journal must provide traceable documentation to show that the minimum requirements are met for each inspector (quizzes, b requirements.
/
records of seminars and/or discussions).
The IE Journal consists of a series of Qualification Guides and Signature Cards. The Qualification Guides list the minimum knowledge levels o of study that must be completed.to document completion as indicated i
- i.,d Signature Cards and associated Qualification Guides must be completed a b
outlined below:
Required Sionature Cards Insoector 1
All (except 9.B.2)
New Resident 1B&C, 2, 3, 4, 5, 6, 8, i
New Project 9A&B.1, 9C
.t 3, 7 i
}
Resident Being Reassigned to Same Type of Plant i
3, 7, 9B.2 and 9C 1
Resident Being Reassigned to
{
Different Type of Plant i
I i
D II-1
4 Signature Card 1 Recional and/or Site Orientation Initials Date
^.
Site Orientation 1.
New employee processing package (Employee)~
completed 2.
Initial site activities completed (SRI) 3.
Resident orientation completed (SRI) 4.
Briefings on re'sident administration
. duties completed (SRI or Section Chief)
B.
Regional / Site Orientation 1.
Self-Study list completed (Employee)
C.
Regional Orientation I
1.
Staff introduction and tour completed (Section Chief)
?
i I
2*
Briefings on administrative items (Section Cnief) 3 completed i
}
3.
NRC organization and mission orientation completed (Section Cnief)
- i
~
i II-2 1
o Signature Card 2 Code of Federal Regulations Initials Date A.
Familiarization with selected 10CFR parts completed.
(Section.Cnief)
B.
Seminars / Discussions c.ompleted on 10CFR parts related to the (Section Chi'ef) inspection program.
e i
4 a
e h
II-3
o Signature Card' 3 Final Safety Analysis Report Initials Date A.
Self-study on facility FSAR completed" (Employee)
~
1 B.
Current Technical Specifications for facility
- 1.
Self-study completed (Employee) 2.
Discussion items completed (SRI or Section Chief) f "For Project Inspectors, this need only be completed for one of the facilities in the section to which he is assigned.
II-4
- Signature Card 4
~
t' ^
Regulatorv Guides Initials Date A.
Self-study of Regulatory Guides completed (Employee)
B.
Regulatory Guide seminars / discussions
~
completed (SRI or Section Chief) 0 9
e e
i e
l l
l II-5 O
Signature Card 5
~~,
NRC/IE' Manual Initials Date A.
Review of NRC Manual Chapters completed (Employee)
B.
Review of IE Manual Chapters completed (non-inspection program)
(Employee)
- C.
Review of IE Manual Chapters concerning inspection program (Employee) completed D.
Discussion of inspection program and inspection philosophy completed (Section or Branch Chief) e 0
s 4
II-6
Signature Card 6
~
( "' s Industry Codes and Standards A.
Review of:
Initials Date 1.
Selected portions of the ASME Codes completed (Employee)
~
2.
Selected ANSI /ANS Standards completed (Employee) 3.
Selected IEEE Standards completed (Employee) 4.
Selected National Fire Protection Agency standards completed (Employee)
B.
Seminar / discussion of an application of Codes and Standards in the inspection
. (SRI or Section Chief) process completed I
4 l
l II-7
Signature Card 7 Onsite Training Initials Date A.
Onsite training completed (SRI or Section Chief)
~
[
l II-8
Signature Card 8
(.
Power Plant Inspection Accompaniments Initials Date A.
Inspections completed 1.
(Facility)
(Dates)
(Inspector in Charge) 2.
(Facility)
(Dates)
(Inspector in Charge) 3.
(Facility)
(Dates)
(Inspector in Charge) 4.
(Facility)
(Dates)
(Inspector in Charge)
S 4
4 I
l i
II-9
Signature Card 9 Technology Training Program Initials Date A.
Regional Training and Qualification Journal reviewed and completed (Section Chief) 1 B.
Training program completed per IE MC 1231 1.
For newly hired inspectors, the follow-ing training courses completed for the type of facility assigned:
a.
BWR(PWR) Technology Course (R-404B(P))
(Training Coordinator) b.
, Course (R-505B(P))
,(Training Coordinator) c.
BWR(PWR) Simulator Course (R-604B(P))
(Training Coordinator) d.
Fundamentals of Inspection Course (G-101)
(Training Coordinator) e.
Radiation / Contamination Protection Course (G-102)
(Training Coordinator) or equivalent plant training.
2.
For resident reassigned to a different type facility (i.e. BWR reassigned to PWR):
a.
BWR(PWR) Technology Course (R-204B(P))
(Training Coordinator) b.
BWR(PWR) Advanced Technology Course (R-504B(P))
(Training Coordinator) c.
BWR(PWR) Simulator Course (R-604B(P))
(Training Coordinator) 3.
Other training courses required for inspectors performing in-spections in specific areas.
Area of Inspection Course a.
(Training Coorcinator)
II-10 t
,m_
b.
(Training Coordinator) c.
(Trair.ing Coordinator) d.
(Train.ing Goordinator)
C.
Branch Chief _ review completed (Branch Chief) 4 8
O
\\
II-11
~
Qualification Guide 1
)
Recional and/or Site Orientation
^
The following list of activities is provided as a guide for completing inspec-tor orientation conducted at the regional office or resident site.
A.
Site Orientation These activities are to be completed by resident inspectors "at their assigned facility.
1.
Upon reporting to the site, a package of administrative forms and activities will be provided by the regional office.
Guidance for completing these activities can be obtained from the Regional Aaministrative Office and inspectors on site.
2.
Initial activities on site should include the following:
a.
Introduction to the licensee by the, senior resident or resident inspector b.
Completing licensee's health physics and security training c.
Entering into. licensee's badge system
=
[
[d.
~ Completing a site tour conducted by the resident and/or
~
~T senior resident inspector.
_.g
- w---...
. e.
Accompanying the resident inspector on daily activities B.'
Regicnal/ Site Orientation These activities are to be completed by resident inspectors at their assigned facility, and by project inspectors at the regional office.
2~
1.'-' Inspector crientation shall acquaint the inspector with various
~ ' publications, their location, and general contents, to include the following: -
a.
Facility Final Safety Analysis Report
' b.
Facility Technical Specifications c.
NRC Manual s
d.
IE Manual e.
Licensee administrative and emergency procedures f.
Plant operating procedures II-12
4 g.
Code of Federal Regulations
('--
h.
Regulatory Guides
.i..
Standards available (ASME, ANSI, IEEE, ANS, etc.)
I i
- 2.
The inspector should become familiar with the general content of the following self-study list. in preparation.for briefings and l
discussions to be held at the regional orientatiorg
' ADMINISTRATIVE ITEMS WITH IMMEDIATE PERSONAL IMPACT a.
Hours of Work / Time Cards / Weekly Manpower-(MPS) 1.
NRCH 4136 (Hours of Work and Premium Pay, Overtime /
Compensating Time) t 2.
NRCM 4137 (Time and Attendance Reporting) 3.
IE Manual Chapter 0530 (Weekly Manpower Reporting) b.
Personal Conduct -
1.
10'CFR Part 0 (Conduct of Employees) 2.
IE Manual Chapter 0235 (Conduct of Employees) 3.
IE Manual Chapter 0236 (Requests for Approval of Outside Employment) 4.
IE Manual Chapter 0237 (Supplemental Statement on Conduct of Employees for Resident Inspectors) c.
Office Security / Security of Classified Material Regional Procedure (Physical Security Plan) d.
Privacy and Freedom of Information Acts i
1.
NRCM 0204 (Privacy Act) 2.
NRCH 0211 (Freedom of Information Act) i 3.
10 CFR 9 (Public Records) e.
Use of Telechones Regional Procedure (Telephone Procedure) f.
Probationary Period / Performance Acoraisals 1.
NRCM 4109 (Probationary Period)
II-13
2.
NRCM 4151 (Personnel Performance Appraisal System)
~'
3.
Regional Procedure (Appraisal of Inspection Program
~ Performance) g.
NRC Resident Training Program and-Inspector Qualifications IE Manual Chapter 1231 (Inspector Qualification)
~
h.
-Safety Progran-1.
NRCM 0507 (NRC Safety Program Under OSHA) 2.
NRCM 0553 (Motor Vehicle Operator Standards) 3.
Regional Procedure (Office Safety Procedures) 4.
Regional Procedure (Respiratory Protection Program for Inspectors) u.
NRC and Reofonal Organi:ation & Function 1.
10 CFR 1 (Organization) 2.
NRCM 0127 (Organization and Functions, Office of Inspection and Enforcement) 3.
NRCM 0128 (Organization and Functions, Regional Offices) 4.
Regional Organization Chart.
5.
NUREG-0325, USNRC Functional Organization Chart j.
Legal Basis of NRC 1.
Atomic Energy Act of 1954, as amended.
2.
Energy Reorganization Act of 1974, as amended.
k.
IE Manual Chapter 0710 (0400 Revised) (Enforcement Actions)
C.
Regional Orientation These activities are to be completed by resident and project inspectors at the regional office.
e II-14
~
1..
The inspector should be given a tour of the regional office'and.
should be introducted to the Regional Administrator, Deputy Regional l
Administrator,. Division Directors, and staff members of the various functional divisions with whom contact may be frequent.
2.
Briefings should be given on the following administrative itemt by
)
staff. members acquainted with the subject.
These briefings should reinforce self-study completed _in Item B.2.above,.and provide the inspector an opportunity to have questions answered.
These briefings may be held on a one-to-one basis, but would be better if integrated with initial training sessions including other newly hired personnel.
Hours of Work Personal Conduct Office Security / Security of Classified Privacy and Freedom of Information Acts Salary, Checks, Leave Manpower Reporting (MPS)
Use of Telephones Probationary Period and Performance Appraisals Travel Public Relations Library Services Mail Policy Union Membership Word Processing Services Regional Safety Program 3.
The inspector should be briefed on NRC and regional organization and on NRC mission by a Section Chief or by personnel at a level atiove Section Chief.
This should reinforce the self-study completed in Item B.2.j above and provide an opportunity to have specific questions answered.
4.
A one-week session should be scheduled so that several newly hired inspectors could be in the regional office at the same time.
This will facilitate formal training sessions, group discussions, and l
exchange of information as well as economize on the use of super-visory time.
This aspect of regional introductory training should be completed by the end of the third month of employment.
Formal Trainino Sessions Enforcement 766 System Inspection Report Writing and Processing Bulletin, Circular, and Information Notice System i
Entrance and Exit Interviews l~
Allegations and Investigations l
Outstanding Items File System AITS Daily Reports and Preliminary Notifications j
II-15
Emergency Preparedness / Incident Response
'.' ' '~
Licensee Events (LERs)
Licensee Enforcement History Systematic Assessment of Licensee Performance (SALP).
Independent Measurements Program Other formal training sessions, as appropriate.
6 4
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Qualification Guide 2
~
, 1[O Code of Federal Regulations The following list of areas is provided as a guide for reviewing the Code of Federal Regulations.
A.
Listed below are 10CFR parts not covered in other portions of this-Journal which the new inspector should become generally ~ familiar.
This may be accomplished by self-study, study quizzes, briefings, or discussions.
Completion of reviews of each part must'be documented by listing the area (s) and date of completion.
1.
10CFR2 Rules of practice for domestic licensing proceedings 2.
10CFR19 Notices, instructions and reports to 4
workers; inspections 3.
10CFR30 Rules of general applicability to domestic licensing of byproduct material 4.
10CFR31 General domestic licenses for byproduct material 5.
10CFR32 Specific domestic licenses to manufacture or transfer certain items containing by-product material 6.
10CFR33 Specific domestic licenses of broad scope for byproduct material 7.
10CFR34 Licenses for radiography and radiation safety requirements for radiographic operations 8.
10CFR35 Human uses of byproduct material 9.
10CFR100 Reactor site criteria 4
B.
Listed below are 10CFR parts with application in the inspection program.
Application of the specific 10CFP, parts to the inspection program listed should be covered by a regional seminar.
These seminars should be con-ducted by senior inspectors to illustrate recent application of various sections of the CFR parts to the inspection programs.
It is suggested that inclusion of experienced as well as new inspectors in these seminars would enhance exchange of inspection experience.
Alternatively, discus-sions of a similar nature can be held with the Senior Resident Inspector or Section Chief.
At least four such seminar / discussions should be con-ducted during the new inspector's first 24 months of employment.
l II-17
, -~,
Completion of each seminar / discussion must be documented by listing the areas covered, date, and initials of the seminar / discussion leader.
1.
10CFR20 Standards for protection against radiation 2.
10CFR21 Reportingofdefectsandnoncodpliance 3.
10CFR50 Domestic licensing of production and utilization facilities 4.
10CFR55 Operator's licenses
({l 10CFR70 Domestic licensing of special nuclear material (h
10CFR71 Packaging of radioactive material for transport and transportation of radioactive material under certain conditions 7.
10CFR73 Physical protection of plants and materials II-18
~
. Qualification Guide 3 b
Final Safety Analysis Report A.
The inspector should become thoroughly familiar with the Final Safety Analysis Report (FSAR) for the facilities assigned.
The following self-study areas provide a guide to reviewing the FSAR and relating it to the licensing process via the Standard Review Plan (SRP).
Completion of self-study in.each area must be documented by listing the area (s) and date of completion.
~
1.
10 CFR 50.34 and 10 CFR 50.34a (Contents of applications; technical information).
2.
Regulatory Guide 1.70 (Standard Format for Safety Analysis Reports).
Compare by scanning, an FSAR and the SRP to determine their organization, general content, and relationship.
Scan a Preliminary Safety Analysis Report (PSAR) and compare it to an FSAR to determine differences in content.
3.
FSAR Section,2 (Site Characteristics).
4.
FSAR Section 3 (Design of Shutdown Systems and Components).
5.
FSAR Section 4 (Reactor).
6.
FSAR Section 5 (Reactor Coolant System and Connected Systems).
7.
FSAR Section 6 (Engineered Safety Features).
8.
FSAR Section 7 (Instrumentation and Control Systems).
9.
FSAR Section 8 (Electric Power Systems).
10.
FSAR Section 9 (Auxiliary Systems).
11.
FSAR Section 10 (Steam and Power Conversion Systems).
l 12.
FSAR Section 11 (Radioactive Waste Management).
I 13.
FSAR Section 12 (Radiation Protection).
14.
FSAR Section 13 (Conduct of Operations).
15.
FSAR Section 15 (Accident Analysis).
16.
FSAR Section 17 (Quality Assurance).
l B.
Each section of the facility's Technical Specifications should be studied and discussed with the Senior Resident Inspector or Section Chief, emphasizing application of Technical Specifications in the inspection program.
II-19
Qualification Guide 4 Regulatory Guides m
The following list of areas is provided as a guide for reviewing the Regula-tory Guides.
A.
Listed below are Regulatory Guides for self-study.
The inspector should become familiar with the general content and scope of each of the Regula-tory Guides in preparation for the seminars and discusstans in Part B of this Qualification Guide.
Note that many Regulatory Guides reference or endorse industry codes and standards listed in Qualification Guide 6.
Study of corresponding codes and standards is recommended.
Regulatory Guide Subject 1.8 Personnel Selection and Trai.ning 1.16 Reporting of Operating Information 1.26 Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste-Containing Components of Nuclear Power Plants 1.27 Ultimate Heat Sink 1.32 Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants 1.33 Quality Assurance Program Requirements (Operation) 1.39 Housekeeping Requirements for Water-Cooled Nuclear Power Plants 1.45 Reactor Coolant Pressure Boundary Leakage Detection Systems 1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems 1.62 Manual Initiation of Protective Actions 1.68 Initial Test Programs for Water Cooled Reactor Power Plants l
1.74 Quality Assurance Terms and Definitions l
1.75 Physical Independence of Electric Systems l
l II-20
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1.81 Shared Emergency and Shutdown Electric
-=
Systems for Multi-Unit Nuclear Power Plants
- .q 1.88 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records 1.89 Qualification of Class IE Equipment for Nuclear Power Plants I
-1.93 Availability of Electric Power Sources 1.97 Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Condi-tions During and Following an Accident 1.101 Emergency Planning for Nuclear Power Plants 1.105 Instrument Setpoints 1.108 Periodic Testing of. Diesel Generator Units Used As Onsite Electric Power Systems at Nuclear Power Plants 1.114 Guidance on Being an Operator at the Controls of a Nuclear Power Plant 1.118 Periodic Testing of Electric Power and Protection Systems 1.120 Fire Protection Guidelines for Nuclear Power Plants 1.139
~
Guidance for Residual Heat Removal 5.7 Exit / Entry Control to Protected Areas, Vital Areas, and Material Access Areas 5.43 Plant Security Force Duties 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Reasonably Achievable 8.15 Acceptable Program for Respiratory Protection 8.27 Radiation Protection Training for LWR Nuclear Power Plant Personnel h
II-21
B.
Application of the Regulatory Guides to the inspection programs should be covered by regional seminars.
These seminars should be conducted by senior inspectors and illustrate current use of Regulatory Guides in the inspec-tion programs.
It is suggested that. inclusion of experienced as'well as new inspectors would enhance exchange of inspection experience.
Alterna-tively, discussions of a similar nature can be held with the Senior Re-sident Inspector or Section Chief. At least four such seminar / discussions should be conducted during the first 24 months of employment.
Note that other Qualification Guide seminar topics can be. integrated into a single
. set, such as those on the Code of Federal Regulations and Codes and Standards.
Completion of each seminar / discussion must be documented by listing the areas covered, date, and initials of the seminar / discussion leader.
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-Qualification Guide 5 G
NRC/IE Manual The following list of areas is provided as a guide for review of the NRC Manual and IE Manual.
This review may be accomplished by self-study, study quizzies, briefings, or discussions.
Completion of review in each area must be documented by listing the area (s) reviewed and date of completion. This list includes only manual chapters not covered elsewhere in this Journal.
A.
NRC Manual Chapters
~'
,1.
0516 - Systematic Assessment of Licensee Performance (SALP)
<2.
1501 - Travel v3.
4125 - Differing Professional Opinions B.
IE Manual Chapters (non-inspection program)
/J..
0030 IE Manual System 2.
0720 Bulletins, Circulars, Information Notices
- 3.
1310 Regional Office Incident Response Actions C.
IE Manual Chapters (inspection program) 1.
0310 Independent Inspection Effort 2.
0610' Inspection Reports: Format and Content 3.
08$$InspectorFeedback 4.
2594 Reactor Inspection Program for Sites Having a Resident Inspector - Startup Testing P,hase D.
Upon completion of the above self-study items, the inspector should dis-cuss specifics of inspections and inspection philosophy with the appro-priate Section or Branch Chief.
I1-23
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Qualification Guide 6
'"i Industry Codes and Standards A.
The following list of areas is provided as a guide for review of indus-try codes and standards.
These reviews may be completed by self-study, study quizzes, briefings, or discussions.
Completion of review must be documented by listing codes and standards reviewed.and date of completion.
Note-that many codes and standards are referenced or endorsed in the Re-gulatory Guides, studying them together is recommended.
1.
Selected portions of the ASME Code 2.
Selected ANSI /ANS Standar'ds 3.
Selected IEEE Standards 4.
Selected National Fire Protection Agency Standards B.
Application of the Codes and Standards to the inspection program should be covered by regional seminars.
These seminars should be conducted by senior inspectors and illustrate current use of Codes and Standards in the inspection programs.
It is suggested that inclusion of experienced as well as new inspectors would enhance exchange of inspection experience.
Alternatively, discussions of a similar nature with the Senior Resident Inspector or Section Chief can be held.
At least four such seminar /
discussions should be conducted during the first 24 months or employment.
Note that other Qualification Guide seminar topics can be integrated into a single set, such as those on industry codes and standards and Regula-tory Guides.
Completion of each seminar / discussion must be documented by listing the areas covered, date, and initials of the seminar / discussion leader.
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o Qualification Guide 7 7
/,
Onrit.eTraini$a The resident inspector should become thoroughly familiar with the operations management organization, and systems of the assigned site.
The following pro-vides a guide for those items to be covered in this familiarization.
A.
Observation of Facility Operation 1.
Complete at least one observation shift at each of the major opera-tor stations for your facility.
Examples of major operator stations are: Shift Supervisor (Engineer), Shift Technical Advisor, Control Room Operator,. Shift Foreman.
These and any additional observation shifts at other operator stations"and centers of site activity must be documented by listing the station and dates of observation.
2.
Under the guidance of the SRI:
- 1) complete all the inspections required in IE 71707 (Operational Safety Verification) at least twice; 2) Complete the inspections required in IE 71710 (Engineered Safety Systems Walkdown) for at least three systems.
Completion of each inspection must be documented by listing the procedure, date of completion, and SRI initials.
B.
Site Management.
The following list of organization components or activities should be reviewed for functions and responsibilities.
Comp'letion of each item i.
must be documented by listing dates of discussions or briefings, or by retention of notes or sketches.
1.
Site Organization Chart 2.
Onsite and offsite safety review committees.
3.
Site QA program.
C.
Site Systems The following list is a guide for review of systems and components.
This review may be accomplished by some or all of the following methods:
Self-study using licens'ee procedures and operator training materials, Walk-throughs c,onducted by experienced inspectors, Tracing (walkdown) of systems using licensee procedures and/or piping and instrumentat, ion drawings, Making simple sketches of system flowpaths (includirg major and safety related components) or structures, Discussion with the SRI, or Oral boards held by' experienced inspectors i
II-25 1
t...
. ~. _ _.,,
Completion of each area to be reviewed must be documented by listing the 1
area completed, date of completion and: 1) retention of study notes, sketchs, completed procedures, or 2) initials of person conducting walk-throughs, discussions, or oral boards.
1.
a.
Reactor vessel' b.
Fuel c.
Reactor coolant system and components 2.
Secondary systems:
a.
Main steam b.
Condensate and feedwater c.
Turbine / generator and auxiliaries e.
Circulating water and service water 3.
Engineered Safety Features (ESF) s a.
Systems and components listed as ESF in the FSAR.,
b.
Operation, interlocks, and control features of the ESF.
4.
Electrical power system a.
Offsite power (AC) b.
Normal auxiliary power (AC) c.
Emergency power (AC and DC) 5.
Instrumentation and control systems a.
Safety related systems as listed in the FSAR.
b.
Turbine EH control c.
Feedwater control or steam generator level control system d.
Recirculation flow control system e.
Steam dump system f.
Instrument room layout g.
Cable spreading room II-26 s.
i 3
h.
Remote shutdown equipment and instrumentation i.
Integrated control system 6.
Radwaste Systems a.
Gaseous
.b.
Liquid c.
Solid 7.
Safety-related seismic structures & instrumentation 8.
Security, alarm and access system.
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Qualification Guide 8
'r5-Power Plant Inspection Accompaniments Each inspector should accompany region-based inspectors or residents on at least four inspections.
For resident inspectors, at least two of these in-spections should be performed at a facility other than that assigned.
-The following provides a guide for material that should be studied and dis-cussed with the inspector in charge during these inspections.
It is not in-tended that each inspection activity encompass all of these items; however, all may be encountered within the scope of the inspections.
The inspector in charge should ensure, through ooservation of work or discussion during inspec-tions, that the material in each area is thoroughly understood.
INSPECTIONS 1.
The Inspection Program IE Manual Chapter 2500 (Reactor Inspection Program) a.
b.
IE Manual Chapter 2510 (Light Water Reactor (LWR) Inspection Program) c.
IE Manual Chapter 2513 (LWR - Preoperational) d.
IE Manual Chapter 2514 (LWR - Startup Testing) 4 e.
IE Manual Chapter 2515 (LWR - Operations) f.
IE Manual Chapter 2600, 2700, 2800 (Scan) g.
IE Manual Chapter 0106 (Inspection of SNUPPS) h.
Regional Instruction:
(Inspection Program Control and Transfer of Lead Responsibility) 2.
Schedulino and Preoaration for Insoections a.
How to prepare for an inspection b.
IE Manual Chapter 0300 (Unannounced Inspections) c.
Regional Instruction (Inspection Access at Power Reactors)
II-28
e d.
Regional Instruction:
(Inspection Program Assignments and Scheduling) e.
Regional Instruction:
(Inspection Plans) 3.
Scope of Inspections a.
Regional Instruction:
(Emphasis on Safety Inspections)
I 4.
Entrance / Exit Interviews a.
Conducting entrance and exit interviews with licensee management b.
IE Manual Chapter 30703 (Management Meetings - Entrance and Exit Interviews)
Regional, Instruction:
(Exit Interviews) c.
5.
Conduct of Inspection, Accumulation of Data a.
How to perform an inspection involving' documentation review and observation of work activities b.
How to deal sith apparent fraud or prevarication c.
Effective communication during the conduct of inspections d.
Investigation and followup of allegations 6.
Post-inspection Activities of Inspectors a.
Debrief with regional management b.
Inspection Report Processing (1)
IE Manual-Chapter 1005 (Inspection Reports)
(2)
IE Manual Chapter 1006 (Safeguards Inspection Reports)
(3) Regional Instruction:
(Preparation of Inspection Report Packages)
(4)
Regional Instruction:
(Handling and Documenting Deviations) s i
II-29 I
c..
Outstanding Items List I
(1) Regional Instruction:
(Regional Office Work Forms) d.
Statistical Data Reporting (766 System)
(1) IE Manual Chapter 0535 (Statistical Data Reporting) e.
Enforcement (1)
IE Manual Chapter 0710 (0400 Revised) (Enforcement Actions)
(2) Identifying appropriate legal commitments and requirements for enforcement action (3)
IE Manual Chapter 30702B (Management Meetings - As Needed) f.
Contacts With Licensee (1)
IE Manual Chapter 1100 (Notification of Significant Meetings)
NON-ROUTINE INSPECTOR ACTIVITIES 1.
Morning Reports IE Manual Chapter 0230 (Morning Report) 2.
Non-routine Licensee Events a.
IE Manual Chapter 1105 (Reports of Non-routine Events) b.
IE. Manual Chapter 1110 (Potential Abnormal Occurrence) c.
Regional Instruction:
(Handling of Non-routine Event Reports)'
d.
IE Manual Chapter 92700 (Licensee Fuent Followup) e.
IE Manual Chapter 90711B (Non routine Event Review) f.
IE Manual Chapter 90712B (In-office Review of Event Reports) g.
NUREG-0161 (Instructions for Preparation of Entry Sheets for LER File) h.
Reg. Guide 1.16 (Repbrting of Operating Information) i.
NUREG-0660 (NRC Action Plan Developed As a Result of the TMI-2 Accident) j.
NUREG-0694 (TMI-related Requirements for New Licensees) k.
NUREG-0737 (Clarification of TMI Action Plan Requirements)
II-30
.a.
p,.
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3.
Preliminary Notifications
^
a.
IE Manual Chapter 1120 (Telephone and Written Preliminary Notifications)-
b.
Regional Instruction:
(Issuance of PN) 4.
Circulars / Bulletins /Information Notices a.
IE Manual Chapter 1125 (NRC Office of Inspection and Enforcement Bulletins & Circulars) b.
IE Manual Chapter 92703B (IE-Bulletin / Circular /Immediate Action Letter Followup c.
Regional Instruction:
(Authority for Processing IE Bulletins and Circulars) 5.
- Hearinos, a.
Participation in public hearings b.
10 CFR 2 and, Study Guide c.
IE ' Manual Chapter 94010B (IE Testimony for ASLB or ASLAB Hearings) 6.
Evaluation of Licensee Management Effectiveness a.
Evaluation of licensee management effectiveness
~-
b.
Regional Instruction:
(Periodic Audit of Licensee En-forcement History) 7.
Safety-related Matters Not Covered by Raiouirements or Commitments a.
The Atomic Energy Act of 1954, Section 161 b.
The Energy Reorganization Act of 1974, Section 206 c.
10 CFR, Paragraphs 50.70, 30.63, 40.81, 50.110, 70.71, 71.64, 73.80, Part 50, Appendix B d.
IE Manual Chapter 0525 (Action Item Tracking System) 8.
Incident Response a.
NUREG-0845 (Agency Procedures for the NRC Incident Response Plan) b.
Incident Response Program / Headquarters Organization b
II-31
O 3
(1) IE Manual Chapter 1320 (Headquarters Incident Response
.. e.,
Actions)
(2)
IE Manual 1310/1 (MUF Action Guidelines) c.
Regional Incident Response (1) Regional Incident Response Plan (2)
IE Manual Chapter 1310 (Regional Office Incident Response Actions)
(3)
Regional Instruction:
(Responsibilities of Regional Duty Officer)
(4) Regional Instruction:
(Regional Emergencies)
(5) Regional Instruction:
(Response to Notifications of Emergency Tests or Drills)
(6)
IE Manual Chapter 93700B (Inspector Dispatched to Site)
~
(7)
IE Manual Chapter 93701B (Followup of Significant Event)
(8)
IE Manual Chapter 93702 (Plant Trips-Safety System Challenges)
(9) Followup of major incident 9.
Allecations and Investigations Regional Instruction:
(Allegations, Complaints, and Investi-gations) 10.
Indeoendent Measurements Program 11.
Use of Consultants by NRC IE Manual Chapter 0105 (OIE Policy Statement on the Use of Consultants)
II-32
r MW1 C
c BWR/6 ADVANCED TECHNOLOGY COURSE (R-506B)
TYPICAL COURSE OUTLINE DAY 1 Course Introduction Technical Specification'0verview Plant Startup Procedure Classroom Exercises DAY 2 Classroom' Exercise Technical Specification Session 1 Transient Session 1 DAY 3 Classroom Exercise BWR Differences Session 1 BWR Differences Session 2 Transient Session 2 DAY 4 BWR Differences Session 3 Technical Issus Transient Session 3 DAY S Log Sununary Technical Specification Session 2 Transient Session 4 DAY 6 BWR Differences Session 4 ERIS/SPDS (1.0)
Transient Session 5 DAY 7 Log Summary Technical Specific,ation Session 3 BWR Differences Session 5 i
4 l
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lda r
d D.
1-DAY 8' Transient Session 6 PCIOMR BWR Differences Session 6 Log Summaary DAY 9 Anticipated Transient Without Scram Discussion Classroom Exercise DAY 10 Course Examination
)
J.
4 I
4 i
.. ~. _ _ _..,, _ _ _ + - -,,, _. - - - _..... _.,., _... _ _.,,. _.
F' l'
.c R-506B i.
DAILY ASSIGNMENTS DAY 1:
EHC Problem DAY 2:
Core Heat Balance DAY 3:
Stuck Control Rod DAY 4:
Dresden Fire / Brown's Ferry Fire Log Summary DAY 5:
Vermont Yankee Log Summary DAY 7:
Oyster Creek Log Summary DAY 8:
Dresden RPS Log Summary O
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[
BWR DIFFERENCES OBJECTIVES 2
~.
BE ABLE T0 IDENTIFY AND EXPLAIN THE MAJOR DIFFERENCES BETWEEN BWR PRODUCT LINES IN THE FOLLOWING CATEGORIES:
a.
METHOD OF FOR'CED CIRCULATION b.
METHOD OF FLOW CONTROL c.
METHOD OF REACTOR ISOLATION PRESSURE AND INVENTORY CONTROL d.
METHODS OF RESIDUAL HEAT REMOVAL e.
METHODS OF EMERGENCY CORE COOLING f.
DESIGN OF CONTAINMENT PACKAGES
/~'
g.
METHODS OF ROD CONTROL h.
DESIGN OF PROTECTIVE CIRCUITS
~
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BWR DIFFERENCES y
SESSION 2
. RECIRCULATION FLOW CONTROL LESSON OBJECTIVES
~
1.
Explain valve vs. pump flow control.
2.
Explain starting sequences.
3.
Explain the thermal shock limitations.
4.
Explain Power / Flow maps.
9 L.~.~.
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- _ _ __ _ -.. _ - -. - -. _ _. -.. - _ - -.. _.. -. - =., -
m._,-._.
~
s BWR DIFFERENCES SESSION 3 I
LESSON OBJECTIVES:
1.
BE ABLE TO DESCRIBE THE. OPERATION OF AN ISOLATION CONDENSER.
2.
BE ABLE TO DESCRIBE HOW THE DIFFERENT BWR PRODUCTION LINES (BWR/2 THRU BWR/6) DISIPATE DECAY HEAT.
1
r f
OBJECTIVES OF BWR DINERENCES SESSION 4 1.
List the High and Low Pressure Emergency Core Cooling Systems for the various product lines.
2.
List the advantagas the BWR/5 and 6 ECCSs have over the BWR/3s and most BWR/4s.
3.
Explain how the various types ECCSs provide core cooling and the purpose of each.
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OBJECTIVES OF BWR DIFFERENCES SESSION 6
~~
(~
4 1.
EXPLAIN HOW CONTROL ROD MOTION IS ACHIEVED WITH THE REACTOR MANUAL CONTROL SYSTEM (RMCS).
2.
STATE THE MAJOR ADVANTAGE THE RC&IS HAS OVER THE RMCS.
3.
LIST THE TYPES OF ROD BLOCKS AND WHEN THEY ARE IN EFFECT FOR THE RWM, RSCS, AND THE ROD BLOCK MONITORING SYSTEM.
4.
EXPLAIN THE SEQUENCE OF EVENTS REQUIRED FOR A ROD DROP ACCIDENT TO OCCUR.
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' APPENDIX D D.0 BWR DIFFERENCES This appendix is provided to give the student some" insight into major differences between the various BWR product lines.
Tables D-1, D-2, D-3, and D-4 have been developed to allow comparisons of various BWR functions for the product lines BWR/2 through BWR/6. The figures in this section (Figures D-1 through D-27) illustrate most of the more important differences indicated in Tables D-1 through D-3.
L D.1 Reactor Vessel and Coolant Circulation 9
All BWR's use forced circulation of coolant, and hence all BWR reactor. vessels and Recirculation Systems support this concept.
f,~
The way that forced circulation is achieved involves differences in the basic design.
The BWR/2 design has no jet pumps inside i
the reactor vessel but has five external recirculation loops to
' provide the required flow.
The BWR/3 through BWR/6 designs do -
have jet pumps internal to the reactor vessel and have only two y
external recirculation loops.
The jet pumps used in the BWR/S and BWR/6 product lines use a five nozzle design which is more efficient than the single nozzle design used in the BWR/3 and BWR/4 product lines.
In the BWR/2, BWR/3, and BWR/4 product lines core flow is controlled by changing the speed of the vari-able speed recirculation pumps in each of the recirculation loops.
In the BWR/S and BWR/6 product lines core flow is controlled by changing the speed of the dual speed recirculation pumps from one
+
i discrete speed to another and by throttling a variable position l.
flow control valve on the discharge side of each recirculation i
pump.
The Recirculation Flow Control System for all product lines allows individual or " ganged" control of each flow control D-1
......... -- ~-.- -.-.... _-- - ----,-- -...-- -. ~ -.
1184
~(
pressure control.
In this mode, reactor steam ' is reduced in pressure and then condensed. in the RHR heat exchangers.
Since the resultant condensate can be directed to the RCIC System pump suction, both systems can be used together to provide an inven-tory-conserving closed loop.
4.
D.3 Residual Heat Removal All BWR facilities have either a large system of several opera-tional modes or else a collection of separate systems to carry out basic heat removal functions.
The earlier product line plants have the individual systems, while the later product line plants use an integrated RHR System.
For example, BWR/2 and some BWR/3 facilities have a separate Shutdown Cooling System and use the Control Rod Drive System for the head ~ spray function while the other product line plants use modes of the RHR System to accomplish the same function.
D.4 Emergency Core Cooling Systems The ECCS package provided for a particular facility is dependent primarily on the vintage of the plant (which takes into account the reactor vessel and Recirculation System design).
In all cases unre are high pressure ECCS and low pressure ECCS.
The Automatic Depressurization System is functionally the same for all facilities.
The BWR/2 product line ECCS high pressure pumping consists of either the normal Codnensate and Feedwater System with vrmal power to.the pumps or else the normal Condensate and Feedwater System with emergency power to the pumps (Feedwater Coolant Injection '(FWCI) System) and delievers the flow to the vessel annulus.
The BWR/2 low pressure ECCS consists of two Core Spray System loops which deliver their flow inside the core shroud.
9 4
D-3
_, _ _,, _ _ _ _, _. _ _ _ ~.
1184 s.
[(
'all BWR/5 product. line plants ' have the ' Mark II Containment. 'All'
~
BWR/6 product line plants have the Mark III Containment.
All three containments have the pressure suppression feature.
The-Mark I Containment _ consists of a drywell (in the shape of an inverted light bulb), a suppression chamber (in.the shape of a torroid), and a-network of vents which extend ra'dially outward and. downward from the drywell to the suppression chamber.
The drywell' and suppression have the same design' pressure.
The Mark II Containment is sometimes referred to as an over-under containment.
It consists of a drywell- (in the shape of a trun-cated cone) a' suppression chamber directly below the drywell (in-the shape of a' right circular cylindar), and a netwcirk of verti-cal vents extending downward from the drywell to the suppression chamber.
The drywell and suppression chamber have the same design pressure.
The Mark III containment employs the construction simplicity of a dry containment while retaining the. advantages of ~ a pressure suppression type containment.
The Mark III Containment consists of a drywell (which is shaped like a right circular cylindar and which is a pressure boundary), a suppression pool (most of which is outside but some of which is inside the drywell), a weir wall (which bounds the suppression pool on the inside of the drywell),.
and the containment vessel which is cylindrical with a domed head, completely surrounds the drywell and suppression pool, and is both a pressure boundary and a fission product boundary.
The design pressure of the drywell is twice that of the containment (which has a much larger volume).
In the Mark I and Mark II containment designs, short term control of post LOCA hydrogen gas concentration is accomplished by iner-ting the primary containment with nitrogen gas for normal plant operation. The nitrogen gas is used to displace the oxygen in the D-5
1184 control rods at a time.
These gangs are predetermined groupings of one, two, three, or four control rods.
The ability to move control rods in gang mode allows BWR/6 startup times to be reduc-ed.
e D.7 Protectiva Circuits and Logic The protective circuits for all BWR/2 through BWR/S and some BWR/6 product -line plants are the same.
These are the circuits for such functions as reactor scrams, containment isolations, and the engineered safety feature actuations.
These circuits use standard relays and contacts and have a one-out-of-two-twice logic associated with them.
Some BWR/6 product line plants (for example, Clinton) use a solid state Nuclear System Protection System (NSPS) which includes the scram function, the isolation function, and the engineered safety features actuation function.
This NSPS uses four separate elec-7 trical divisions and has a two-out-of-four logic for the scram g
and isolation functions and a one-out-of-two-twice logic for the engineered safety feature, actuation function.
4 D-7 I
O I
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) ~.
f i
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FUNCTION I
Bwn/2 BWR/3 BWR/4 BWR/S BWR/6 FORCED CIRCULATION
]'
LOOP 5; NO LOOP 5; 20 LOOP 5; 20 LOOP 5; 20 LOOP 5; 20 5 RECIRC 2 RECIRC 2 REClRC 2 RECIRC 2 RECIRC J
JET PUMP 5 JET PUMP 5 JET PUMP 5 JET PUMP 5 OR 24 JET i
INTE ANAL PUMP DESIGN PUMP 5 NONE SINGLE SINGLE FIVE FIVE NOZ2LE NOZ2LE NOZZLE NOZZLE JET PUMP 5
- JET PUMP 5 JET PUMPS JET PUMP 5
{-
FLOW CONTROL METHOD VARIASLE VARIAsLE VARIASLE DUAL SPEED DUAL SPEED SPEED SPEED SPEED RECIRC RECIRC RECIRC VARIABLE VARIASLE RECIRC PUMP 5; RECIRC PUMP 5; PUMP 5 PUMP 5 POSITOON rCv 5 POSITION FCv 5 FLOW CON TROLLER M ASTE R;
- MASTER; MASTER; MASTER; MASTER;
}.J, ARRANGEMENT INDIVIDUAL INDIVIDUAL INDIVIDUAL F4UW; F LUX; INDIVIDUAL INDIVIDUAL REACTOR ISOLATION ISOLATION ISOLATION SR V'S SAV'S SAV's PRES 5URE CONTROL CONDEN5ER CONDEN5ER 2
SAV's STEAM STE AM STEAM CONDENSING CONDENSING CONDENSING MODE (RHR)
MODE lRHR)
MODE (RHR)
REACTOR 850LATOON ISOLATION ISOLATION RCIC SYS.
j INVENTORY CONTROL CONDEN5E R CONDEN5ER RCic SYS.
RCIC SYS, E
[
4 1
RCIC SYS.
SHUTDOWN COOLING SHUTDOWN SHUTDOWN SHUTDOWN SHUTDOWN SHUTDOWN COOLING COOLING COOLING COOLING COOLING SYSTEM SYSTEM l
MODE (RHR)
MODE (RHR)
MODE (RHR)
SHUTDOWN COOLING MODE (RHR)
HEAD 5 PRAY CRDH5Y5.
CRDH 5YS.
l SHUTDOWN SHUTDOWN 5HUTDOWN COOLING COOLING
' COOLING CONTAINMENT SPRAY MODE (RHR)
MODE (RHR)
MODE (RHR)
I AND COOLING CON T AINMENT
- LPCISYS, CON TAINMENT CON T AINMEN T CONTAINMENT SPR A Y SYS.
SPRAY AND SPR AY AND i '5 PRAY AND COOLING MODE COOLlNG MDDE COOLING MODE (RHR)
(RHR)
(RHR)
CONTAINMENT SPRAY AND COOLING MODE
~ (RHR)
ECCS HIGH PRES 5URE FEEDWATER FWCl SYS.
HPCISYS.
HPC5 SYS.
HPC5 SYS.
PUMPING SYS.
>=
FWCl SYS.
HPCISYS.
TABLE D-1 BWR DIFFERENCES CHART (PART 1)
m,-
i e
FUNCTION BWR/2 BWR/3 BWR/4 BWR/S BWR/6 i
ECC5 HIGH PRES 5URE VE5SEL VESSEL VESSEL DIRECTLY DIRECTLY PUMPING DELIVERY ANNULUS ANNULUS ANNULUS INSIDE INSIDE POINT VIA VIA VIA CORESHROUD CORESHROUD j
FEEDWATER FEEDWATER FEEDWATER (OMESPRAY (ONE SPRAY
)
LINE LINE LlNE RING)
RING)
ECCS HIGH PRES 5URE NORMAL FW NORMALFW TURSONE MOTOR DRIVEN MOTOR DRIVEN PUMP TYPE (5)
SYS. PUMPS SYS. PUMP 5 DRIVEN HPCI HPCS HPC5 (NORMAL (EMERGENCY (EMERGENCY (EMERGENCY POWER)
POWE R)
POWER)
POWE R)
NORMALFW TURBONE SYS. PUMP 5 DRIVEN HPCI (EMERGENCY POWER)
ECCS HIGH PRESSURE ADS ADS ADS ADS ADS SLOWDOWN
]
j ECCS LOW PRE 550RE TWO CORE TWO CORE TWO CORE ONE LPC5 ONE LPCS SPRAYING SPR AY LOOPS SPR AY LOOPS SPRAY LOOPS LOOP LOOP j
}
ECCS LOW PRESSURE DIRECTLY DIRECTLY DIRECTLY DIRECTLY DIRECTLY 4
SPR AYING DELIVERY INSIDE INSIDE INSIDE INSIDE INSIDE POINT CORESHROUD CORE SHROUD CORESHROUD CORESHROUD CORE SHROUD (TWO 5 PRAY (TWO SPR AY (TWO SPRAY (ONE SPR AY (ONE SPRAY r
RING 5)
RINGS)
RINGS)
RING)
RING) c, ECC5 LOW PRESSURE NOME LPCISYS.
LPCI MODE LPCI MODE LPCI MODE FLOODING TWO LOOPS (RHR)
(RHR)
(RHR)
TWO LOOPS THREE LOOPS THREE LOOPS I
(NO SELECTBON)
LPCI MODE l
(RHR)
TWO LOOPS (LOOP SELECTION)
ECCS LOW PRESSURE NONE VE5SEL VESSEL DIRECTLY DIRECTLY LOWER LOWER INSIDE IN5IDE PLENUM VIA PLENUM VIA CORESHROUD CORESHROUD FLOODING DELIVERY POINT RECORC RECIRC DISCHARGE DISCHARGE i
PIPING PIPING STAND 8Y COOLANT UH5 WATER UH5 WATER UH5 WATER UH5 WATER UH5 WATER TO VE5SEL TO VE5SEL TO VE5SEL TO VE5SEL TO VE5SEL VIA CONDEN5ER OR CONT.
OR CONT.
OR CONT.
OR CONT.
f SUPPLY AND FW SYS VIA FWCl SYS VIA RHR VIA RHR VIA RHR I
l UH5 WATER TO VESSEL
[
OR CONT.
o VIA RHR Za TABLE D-2 BWR DIFFERENCES CHART (PART 2)
l N
i FUNCTION BWR/2 BWR/3 BWR/4 BWR/5 BWR/6 CONTAINMENT PACKAGE MARK 1 MARKI MARKI MARK 11 MARK lil L' ARK 11 LOCA PRES 5URE VIA RADIAL VIA RADIAL SAME A5 VI A VERTICAL VIA HOftIZONTAL SWR /3 VENTS VENTS THROUGH i
SUPPRESSION METHOD VENTS, RING VENTS. RING SWR /2,SULG-(OV E R-DRYWELL WALL (LIGn j
UNOEft) i DOWNCOMER5 DOWNCOME R$
i i
(LIGHTSULS-(LIGHTSULS-SAME AS i
TORUS)
TORUS)
SWAS (OVCR-f uMOE R)
PRIM ARY CONTAINMENT
- DAYWELL, DAYWELL.
DAYWELL.
DRYWELL AND CONTAINMENT F15510N PRODUCT VENTS, AND VENTS, AND VENTS, AND SUPPRESSION SAR RIE R SUPPRESSION SUPPRESSION SUPPRESSION CHAMSEft CHAMSE R CHAMSER CHAMSE ft
}
DRYWELL AND SUPPRESSION CHAMSER POST LOCA SHORT TERM NITROGEN MITROGEN MITROGEN NITROGEN LARGER HYDftOGEN CONTROL INE RTING INE ftTING INE ATING INE RTSMG VOLUMES DURING DURING DURING DUltING M1XING NORMAL NORMAL NORMAL NORMAL COMPRE550ft5 OPE R ATOON OPE R 4 TION OPE A ATSON OPEftATOON POST LOCA LONG TERM NITROGEN MITROGEN NOTROGEN NITROGEN HYDROGEN
?
- NE ATING; INE A TING INE AT BNG; ftECOM81NER5;
{
O VENTING VENTING (CAD SYS);
VENTING HYDROGEN b
VIA SGT5 VIA SGTS VENTING VIA SGT5; IGNITEft5 VIA SGTS HYDftOGEN w
RECOMSINERS ROD CONTROL RMC5 AMC5 AMC5 RMC5 RC & 15 i
(ONE ROD (ONE ROD
{ONE ROO (ONE ROD (UP TO FOUR AT A TIME);
AT A TIME);
AT A TIME);
AT A TIME);
RODS AT A (STANDARD (ST ANDARD (STANDARD (SOLID 5 TATE TIME);
ftELAYS AND RELAYS AND ftELAYS AND TIMER)
(SOLID ST ATE TIMER)
TIME R)
TIMER OR TIMER)
SOLIO ST ATE TIMER)
PROTECTIVE CIRCulT STANDARD STANDARD STANDARD STANDARD STANDARD TY PE (RPS,ISOLATIONS, RELAYSAND RELAYS AND RELAYS AND RELAYS AND RELAYS AND E CC S. ETC.)
CONTACTS CONTACT 5 CONTACT 5 CONTACTS CONTACTS SOLIOSTATE N5P5 TYPICAL PROTECTIVE ONE-OUT-OF-ONE-OUT-OF-ONE-OUT-OF-ONE--OU T-OF-
'ONE-OUT-OF-l I
circuli LOGIC TWO-TWICE TWO-TWICE TWO-TWICE TWO-TWICE TWO-TWICE i
TWO-OUT-OF 4)
FOUR (RPS, N5
~.
ONE-OUT-OF-j l
TWO-TWICE O.
A (ECC5) i I
TABLE D-3 BWR DIFFERENCES CHART (PART 3)
~
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VESSEL HEAD NUT 4
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WATER LEVEL i
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FIGURE D-1 REACTOR VESSEL (BWR/2) v U-13
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COOLING NO MACTOA vtSSEL MaAo VES$th Mi&O Stu0 VESSEL MEAO myt
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SHIELO WALL VESSEL St.PPORT SKIRT
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i FIGURE D-3 REACTOR VESSEL (BWR/5,OR BWR/6) 0-19 l
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FIGURE D-4 RECIRCULATION SYSTEM (BWR/2)
I D-21 i
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---,-_+-_,-m-,
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' (S/O COOUNG SUCTION) 4 3
A blSCHARGE i
MOTOR C1SCHARGE MOTOR ISOLATION ]I ISOLATION j
VALVE VALVE
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VALVE l
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FIGURE D-6 RECIRCULATION SYSTEM (BWR/S OR BWR/6)
1184 ILM Ma~ua' M ASTE R sw A/2 QNLY CONTROLLER r
I I
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FLOW CONTROLLER
- MANUAL (M/A STATION)
L A
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SIMILAR FOR OTHER REClRCULATION LOOP ($)
'f SPEED CONTROLLER II (et ORIVE MOTOR POSITIONEp II FLulO COUPLER
.:p If GENERATOR u
PUM P PUMP MOTOR t.
FIGURE D-7 RFC SYSTEM (BWR/2, BWR/3, OR BWR/4)
D-27 i
IId4 MANUAL EHC LOAD DEMAND SIGNALS r
'J MASTER CONTROLLER NEUTRON FLUX DEMAND I
APRM l
SIGNAL MANUAL r
1r it NEUTRON FLUX CONTROLLER if FLOW DEMAND SIGNAL MANUAL MANUAL
,r p y 1r 1r 1r FLOW FLOW CONTROLLER CONTROLLE R f"* '
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UMf7ER l
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E HYDRAULIC CONTROL SIGNAL 9
VALVE VALVE ACTUATOR ACTUATOR 7
7w a
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RECIRC.
IFTl l
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FIGURE D-8 SIMPLIFIED REC 1RCULATION FLOW CONTROL LOOP 0 !
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k I PUMPS (EMERG AC POWER) l lNINE MILE POINT]
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MAIN CONDENSER HOTWELL
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FIGURE D--14 ECCS COMPOSITE (BWR/2) 0-41
i l
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OnywtLL CTOR MAIN STEAM LINE
= TO TURBINE
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FEEOWATEM LINE j(
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ATE H
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e FIGURE D-15 ECCS COMPOSITE (BWR/3) e D-43
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CONTAINMENT D YWELL MO g
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MO LPCS v,
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+-
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t ORYWELL SHEAR LUG SUPPORT REACTOR PR ESSURE VESSEL l
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