ML16330A243: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:APPENDIX B QUESTIONS AND RESPONSES RELATED   
{{#Wiki_filter:APPENDIX B
 
QUESTIONS AND RESPONSES RELATED   


TO   
TO   
Line 33: Line 35:
HAVE BEEN INTENTIONALLY DELETED.   
HAVE BEEN INTENTIONALLY DELETED.   


B-2 Rev 5 7/87 12.0  Conduct of Operations REQUEST:
B-2 Rev 5 7/87 12.0  Conduct of Operations
12.1 Provide an organization chart of corporate management showing the scope and relationship of the corporate structure to the onsite operating organization. The organization for corporate, consultant, vendor, and other technical support should be delineated in more detail with regard to the technical expertise available to specifically support the nuclear plant.
 
REQUEST:  
 
12.1 Provide an organization chart of corporate management showing the scope and relationship of the corporate structure to the onsite operating  
 
organization. The organization for corporate, consultant, vendor, and other technical support should be delineated in more detail with regard to the technical expertise available to specifically support the  
 
nuclear plant.  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR Figures 12.1-2 and 15.6.1, and pages 12.1.1-1 and 12.1.1-2, and Figure 6.1 of the Technical Specifications.    
Refer to FSAR Figures 12.1-2 and 15.6.1, and pages 12.1.1-1 and 12.1.1-2, and Figure 6.1 of the Technical Specifications.  


REQUEST:   
REQUEST:   


12.2 The Facility Organization Chart (Figure 12.1-1) does not clearly or adequately depict the nuclear plant operating organization described in Section 12.1.1, especially with respect to single vs. dual unit operation. Please provide the following additional information:    
12.2 The Facility Organization Chart (Figure 12.1-1) does not clearly or adequately depict the nuclear plant operating organization described in Section 12.1.1, especially with respect to single vs. dual unit  
: a. Justification for the adequacy of the proposed six man dual unit staffing in order to determine whether or not the proposed crew size is sufficient to adequately cope with plant operating requirements during routine, abnormal, and emergency situations affecting both nuclear units.    
 
: b. The facility organization chart should be modified to show the complete shift crew operating organization for single and dual unit operation. The generic term "plant operators", used on the existing organization chart, coupled with the absence of the crew disposition for single and dual unit operation, does not adequately delineate the shift crew organization and their attendant responsibilities.    
operation. Please provide the following additional information:  
: a. Justification for the adequacy of the proposed six man dual unit staffing in order to determine whether or not the proposed crew size is sufficient to adequately cope with plant operating requirements during routine, abnormal, and emergency situations  
 
affecting both nuclear units.  
: b. The facility organization chart should be modified to show the complete shift crew operating organization for single and dual unit operation. The generic term "plant operators", used on the existing organization chart, coupled with the absence of the crew  
 
disposition for single and dual unit operation, does not adequately delineate the shift crew organization and their  
 
attendant responsibilities.  
: c. In addition to personnel position requirements and qualifications, a brief description of the duties, responsibilities, and authorities of individual plant positions should be indicated.
: c. In addition to personnel position requirements and qualifications, a brief description of the duties, responsibilities, and authorities of individual plant positions should be indicated.
What is the function of the "Plant Engineer - Results"?
What is the function of the "Plant Engineer - Results"?
Specifically, what kind of personnel are assigned under his supervision and what are their functions?  Is the "Nuclear Operator" referred to in Section 12.1.1 (but not shown in Figure 12.1-1) a licensed reactor operator or is he equivalent to an "Auxiliary Operator"?    
Specifically, what kind of personnel are assigned under his supervision and what are their functions?  Is the "Nuclear Operator" referred to in Section 12.1.1 (but not shown in Figure 12.1-1) a licensed reactor operator or is he equivalent to an  
: d. Indicate the experience level of maintenance repairmen who will perform maintenance and repair of-the-nuclear plant and its components and auxiliaries.     
 
"Auxiliary Operator"?  
: d. Indicate the experience level of maintenance repairmen who will perform maintenance and repair of-the-nuclear plant and its  


B-40 RESPONSE:    
components and auxiliaries. 
 
B-40 RESPONSE:  
: a. Refer to FSAR page 12.1.1-2.   
: a. Refer to FSAR page 12.1.1-2.   
: b. Refer to FSAR Figure 12.1-1 and page 12.1.3-23.   
: b. Refer to FSAR Figure 12.1-1 and page 12.1.3-23.   
Line 57: Line 79:
REQUEST:   
REQUEST:   


12.3 The actual qualifications of some key plant personnel appear to be substantially less than the minimum qualification, requirements (nuclear) stated for those key positions in the FSAR. This observation is based upon apparent deficiencies in the critical areas of nuclear power plant operating experience coupled with deficiencies in associated  reactor technical areas such as reactor core physics, nuclear plant maintenance, chemistry, and radio-chemistry. Provide justification for the adequacy of technical expertise in the above areas.
12.3 The actual qualifications of some key plant personnel appear to be substantially less than the minimum qualification, requirements (nuclear) stated for those key positions in the FSAR. This observation is based upon apparent deficiencies in the critical areas of nuclear power plant operating experience coupled with deficiencies in associated  reactor technical areas such as reactor core physics, nuclear plant maintenance, chemistry, and radio-chemistry. Provide justification for the adequacy of technical expertise in the above  
 
areas.  
 
RESPONSE:   
RESPONSE:   


Line 64: Line 89:
REQUEST:   
REQUEST:   


Indicate the position title of the individual who is responsible for the conduct and administration of the nuclear power training program.
Indicate the position title of the individual who is responsible for the conduct and administration of the nuclear power training program.  
 
RESPONSE:   
RESPONSE:   


Line 71: Line 97:
REQUEST:   
REQUEST:   


12.5  Indicate the scope and content of training programs that have been provided for reactor plant technicians, auxiliary operators, or their equivalents, turbine operators, and repairmen.
12.5  Indicate the scope and content of training programs that have been provided for reactor plant technicians, auxiliary operators, or their  
 
equivalents, turbine operators, and repairmen.  
 
RESPONSE:   
RESPONSE:   


Refer to FSAP page 12.2.3-1.   
Refer to FSAP page 12.2.3-1.   


B-41 REQUEST:
B-41 REQUEST:  
12.6 Provide information concerning the course entitled "Operation Aspects of Radiation Surveillance - 1969" with regard to length and content of course and where conducted (This course is listed under education and training for "Plant Engineer - Chemistry and Health Physics")  
 
12.6 Provide information concerning the course entitled "Operation Aspects of Radiation Surveillance - 1969" with regard to length and content of course and where conducted (This course is listed under education and  
 
training for "Plant Engineer - Chemistry and Health Physics")  


RESPONSE:  
RESPONSE:  
Line 85: Line 117:
REQUEST:   
REQUEST:   


12.7 Indicate the scope and content of the retraining (refresher) program, and state which positions will receive formal retraining. The maximum retraining program cycle should be indicated.
12.7 Indicate the scope and content of the retraining (refresher) program, and state which positions will receive formal retraining. The maximum  
 
retraining program cycle should be indicated.  
 
RESPONSE:   
RESPONSE:   


Line 92: Line 127:
REQUEST:   
REQUEST:   


12.8 Indicate the scope and content of the replacement training program unless it is your intention to utilize the "Westinghouse Reactor Operator Training Program" for subsequent replacement personnel, in which case a statement to that effect should be included in the FSAR.
12.8 Indicate the scope and content of the replacement training program unless it is your intention to utilize the "Westinghouse Reactor Operator Training Program" for subsequent replacement personnel, in  
 
which case a statement to that effect should be included in the FSAR.  
 
RESPONSE:   
RESPONSE:   


Line 99: Line 137:
REQUEST:   
REQUEST:   


12.9 What means will be provided to evaluate the effectiveness of the training, retraining, and replacement training programs?
12.9 What means will be provided to evaluate the effectiveness of the training, retraining, and replacement training programs?  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR page 12.2.1-5.   
Refer to FSAR page 12.2.1-5.   


B-42 REQUEST:
B-42 REQUEST:  
 
12.10 Has a general employee training program been incorporated in the training program to ensure that all plant personnel are trained in (1)
12.10 Has a general employee training program been incorporated in the training program to ensure that all plant personnel are trained in (1)
Industrial Safety, (2) First Aid, (3) Radiological Health and Safety, (4) Industrial Security, (5) Use of Protective Clothing and Equipment, and (6) Appropriate Plans and Procedures?
Industrial Safety, (2) First Aid, (3) Radiological Health and Safety, (4) Industrial Security, (5) Use of Protective Clothing and Equipment,  
 
and (6) Appropriate Plans and Procedures?  
 
RESPONSE:   
RESPONSE:   


Line 113: Line 156:
REQUEST:   
REQUEST:   


12.11 Provide a listing (by titles) of written procedures specified for station operation.
12.11 Provide a listing (by titles) of written procedures specified for station operation.  
 
RESPONSE:   
RESPONSE:   


Line 120: Line 164:
REQUEST:   
REQUEST:   


12.12 Indicate the normal locations and accessibility of various written procedures and plans specified for station operation.
12.12 Indicate the normal locations and accessibility of various written procedures and plans specified for station operation.  
 
RESPONSE:  
RESPONSE:  


Line 127: Line 172:
REQUEST:   
REQUEST:   


12.13 Describe the method you will use for assuring that procedures have been distributed, read and understood, and are complied with by station personnel.
12.13 Describe the method you will use for assuring that procedures have been distributed, read and understood, and are complied with by station  
 
personnel.  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR Section 12.3.   
Refer to FSAR Section 12.3.   


B-43 REQUEST:
B-43 REQUEST:  
12.14 List those procedures for which check-off lists are specified. How are check-off lists completed and approved?
 
12.14 List those procedures for which check-off lists are specified. How are check-off lists completed and approved?  
 
RESPONSE:   
RESPONSE:   


Line 140: Line 190:
REQUEST:   
REQUEST:   


12.15 Provide a complete listing (by titles) of the specific types of records to be kept. Are training records and personnel experience/qualification records kept?  Are Quality Assurance Control records kept? What are the titles of the general types of operating records kept?
12.15 Provide a complete listing (by titles) of the specific types of records to be kept. Are training records and personnel experience/qualification records kept?  Are Quality Assurance Control records kept? What are the  
 
titles of the general types of operating records kept?  
 
RESPONSE:   
RESPONSE:   


Line 147: Line 200:
REQUEST:   
REQUEST:   


12.16 What recording methods (recorder, computer, manual) are employed for the various types of records?
12.16 What recording methods (recorder, computer, manual) are employed for the various types of records?  
 
RESPONSE:   
RESPONSE:   


Line 154: Line 208:
REQUEST:   
REQUEST:   


12.17 Indicate the position title of the individual who has direct responsibility for records management.
12.17 Indicate the position title of the individual who has direct responsibility for records management.  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR page 12.4.1-1.   
Refer to FSAR page 12.4.1-1.   


B-44 REQUEST:
B-44 REQUEST:  
12.18 The brief description of industrial security appearing in Section 12.5 (administrative control) should be expanded to include the specific types of security measures to be employed to guard against and detect unauthorized access to the reactor site, reactor control areas, and principal buildings or other critical areas of the facility (e.g. are personnel identification badges, perimeter lighting, alarms, television etc. employed?).
 
12.18 The brief description of industrial security appearing in Section 12.5 (administrative control) should be expanded to include the specific types of security measures to be employed to guard against and detect unauthorized access to the reactor site, reactor control areas, and principal buildings or other critical areas of the facility (e.g. are personnel identification badges, perimeter lighting, alarms, television  
 
etc. employed?).  
 
RESPONSE:   
RESPONSE:   


Line 167: Line 226:
REQUEST:   
REQUEST:   


12.19 Indicate the methods of controlling the various types of expected visitors.
12.19 Indicate the methods of controlling the various types of expected visitors.  
 
RESPONSE:   
RESPONSE:   


Line 174: Line 234:
REQUEST:   
REQUEST:   


12.20 The controls or methods specified for guarding critical plant features against acts of sabotage should be indicated.
12.20 The controls or methods specified for guarding critical plant features against acts of sabotage should be indicated.  
 
RESPONSE:   
RESPONSE:   


Confidential policy matters will be the subject of a separate proprietary document.
Confidential policy matters will be the subject of a separate proprietary document.  
 
REQUEST:   
REQUEST:   


12.21 The spectrum of emergencies classified and defined in Section 12.3.2 (Emergency Procedures) are properly a part of the Section 12.3.3 (Emergency Control Plan). However, in addition to classification and definition of emergencies, the consequences of the various types of accidents or emergencies should be considered in the Emergency Plan.
12.21 The spectrum of emergencies classified and defined in Section 12.3.2 (Emergency Procedures) are properly a part of the Section 12.3.3 (Emergency Control Plan). However, in addition to classification and definition of emergencies, the consequences of the various types of accidents or emergencies should be considered in the Emergency Plan.
The consequences of radiological accidents ranging from accidents affecting only local operating personnel to the design basis accident which could affect site and neighboring environment, should be considered in greater depth than currently appears in Section 12.3.2.
The consequences of radiological accidents ranging from accidents affecting only local operating personnel to the design basis accident  
 
which could affect site and neighboring environment, should be  
 
considered in greater depth than currently appears in Section 12.3.2.  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR page 12.3.3-1, Table 12.3.3-1, and the Emergency Control Plan.       
Refer to FSAR page 12.3.3-1, Table 12.3.3-1, and the Emergency Control Plan.       


B-45 REQUEST:
B-45 REQUEST:  
12.22 The various locations of Emergency Procedures, drawings and diagrams of the plant, required in the event of implementation of the Emergency Control Plan; should be specified.
 
12.22 The various locations of Emergency Procedures, drawings and diagrams of the plant, required in the event of implementation of the Emergency
 
Control Plan; should be specified.  
 
RESPONSE:   
RESPONSE:   


Line 195: Line 266:


12.23 Protective measures and corresponding protective action levels should be specified for each emergency or accident in the spectrum of emergencies or accidents considered in the "Emergency Control Plan."
12.23 Protective measures and corresponding protective action levels should be specified for each emergency or accident in the spectrum of emergencies or accidents considered in the "Emergency Control Plan."
The technical basis for each of the Protective Measures should be supported in the plan along with a description of the available plant instrumentation and other instrumentation (including portable monitoring  equipment) which is used as a basis for the development of the various Protective Action Levels.
The technical basis for each of the Protective Measures should be supported in the plan along with a description of the available plant instrumentation and other instrumentation (including portable  
 
monitoring  equipment) which is used as a basis for the development of  
 
the various Protective Action Levels.  
 
RESPONSE:   
RESPONSE:   


Line 202: Line 278:
REQUEST:   
REQUEST:   


12.24 Are individual facility (unit) Emergency Control Plans to be developed? Is a compatible site Emergency Plan to be developed?  Consideration should be given to accident consequences and emergency procedures for one-unit (fossil or nuclear) affecting another unit.
12.24 Are individual facility (unit) Emergency Control Plans to be developed? Is a compatible site Emergency Plan to be developed?  Consideration should be given to accident consequences and emergency procedures for  
 
one-unit (fossil or nuclear) affecting another unit.  
 
RESPONSE:   
RESPONSE:   


Line 209: Line 288:
REQUEST:   
REQUEST:   


12.25 The role of the offsite support groups, their authorities, and their responsibilities with regard to a plant emergency, should be described in the Emergency Control Plan. Are agreements with offsite support groups being confirmed in writing?  Local law enforcement agencies and civil defense agencies are not mentioned as offsite support groups.
12.25 The role of the offsite support groups, their authorities, and their responsibilities with regard to a plant emergency, should be described in the Emergency Control Plan. Are agreements with offsite support  
What are their roles?
 
groups being confirmed in writing?  Local law enforcement agencies and civil defense agencies are not mentioned as offsite support groups.
 
What are their roles?  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR page 12.3.3-1 and the Emergency Control Plan.   
Refer to FSAR page 12.3.3-1 and the Emergency Control Plan.   


B-46 REQUEST:
B-46 REQUEST:  
 
12.26 The significant features of the medical plan (referred to in Section 12.3.2 as "being developed with the medical school and hospital")
12.26 The significant features of the medical plan (referred to in Section 12.3.2 as "being developed with the medical school and hospital")
should be reflected in the Emergency Control Plan. The scope of available local medical support, experienced and trained in treating victims of radiological accidents, should be indicated.
should be reflected in the Emergency Control Plan. The scope of available local medical support, experienced and trained in treating  
 
victims of radiological accidents, should be indicated.  
 
RESPONSE:   
RESPONSE:   


Line 224: Line 311:
REQUEST:   
REQUEST:   


12.27 The scope of Emergency Control Plan training and drills should be addressed. Will training and drills involve all support groups?  How often will drills be held?
12.27 The scope of Emergency Control Plan training and drills should be addressed. Will training and drills involve all support groups?  How  
 
often will drills be held?  
 
RESPONSE:   
RESPONSE:   


Line 231: Line 321:
REQUEST:   
REQUEST:   


12.28  It is implied in Section 12.3.3 that the plant security guards are furnished by a contract guard service company. The guard on duty at the facility is identified as a member of the Emergency Monitoring Team with training in the use of radiation survey instruments. What is the scope of this training and who is responsible for conducting it?  Are there enough replacement guards trained in the use of the equipment what assurance exists that only these specially trained personnel will be used to guard the nuclear power plant?
12.28  It is implied in Section 12.3.3 that the plant security guards are furnished by a contract guard service company. The guard on duty at the facility is identified as a member of the Emergency Monitoring Team  
 
with training in the use of radiation survey instruments. What is the scope of this training and who is responsible for conducting it?  Are there enough replacement guards trained in the use of the equipment what assurance exists that only these specially trained personnel will  
 
be used to guard the nuclear power plant?  
 
RESPONSE:   
RESPONSE:   


Line 238: Line 333:
REQUEST:   
REQUEST:   


12.29 What are the "established criteria" and "prescribed limits" (referred to in Section 12.3.2) for putting the offsite vs onsite portions of the Emergency Plan into effect?  What are the provisions for emergency dosimetry and tracking of offsite releases?
12.29 What are the "established criteria" and "prescribed limits" (referred to in Section 12.3.2) for putting the offsite vs onsite portions of the Emergency Plan into effect?  What are the provisions for emergency  
 
dosimetry and tracking of offsite releases?  
 
RESPONSE:   
RESPONSE:   


Refer to the Emergency Control Plan.   
Refer to the Emergency Control Plan.   


B-47 REQUEST:
B-47 REQUEST:  
12.30 Have alternate personnel been designated to man hey positions within the Emergency Control Plan Organization? (e.g., the Conservation Supervisor on Emergency Monitoring Team)
 
12.30 Have alternate personnel been designated to man hey positions within the Emergency Control Plan Organization? (e.g., the Conservation  
 
Supervisor on Emergency Monitoring Team)  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR Section 12.3.2 Conservation Supervisor duties have been changed.    
Refer to FSAR Section 12.3.2 Conservation Supervisor duties have been changed.  


REQUEST:   
REQUEST:   


12.31 Describe distinguishing feature of various alarms associated with the Emergency Control Plan. Has a test been conducted to ascertain auditibility in all required areas, particularly in areas of high noise level or acoustically insulated areas?
12.31 Describe distinguishing feature of various alarms associated with the Emergency Control Plan. Has a test been conducted to ascertain auditibility in all required areas, particularly in areas of high noise  
 
level or acoustically insulated areas?  
 
RESPONSE:   
RESPONSE:   


Line 258: Line 363:
REQUEST:   
REQUEST:   


12.32 Has a plan been developed which makes adequate provision for coordination and dissemination of public information released following an accident?
12.32 Has a plan been developed which makes adequate provision for coordination and dissemination of public information released following  
 
an accident?  
 
RESPONSE:   
RESPONSE:   


Refer to FSAR page 12.3.2-2 and 12.3.2-3.   
Refer to FSAR page 12.3.2-2 and 12.3.2-3.   


B-48 13.0  Initial Tests and Operations REQUEST:   
B-48 13.0  Initial Tests and Operations
 
REQUEST:  
 
13.1 Provide details of the organizational structure for pre-operational testing, fuel loading, startup, and initial testing of the operating reactor. Position titles, station-groups (operations, technical,
 
maintenance) to which assigned, functional roles, responsibilities, and qualifications of any augmenting personnel should be indicated during
 
the above phases of operations. Planned augmentation of regular shift crew personnel should be indicated along with a summary of functional
 
roles, responsibilities and qualifications.    


13.1 Provide details of the organizational structure for pre-operational testing, fuel loading, startup, and initial testing of the operating reactor. Position titles, station-groups (operations, technical, maintenance) to which assigned, functional roles, responsibilities, and qualifications of any augmenting personnel should be indicated during the above phases of operations. Planned augmentation of regular shift crew personnel should be indicated along with a summary of functional roles, responsibilities and qualifications.
RESPONSE:   
RESPONSE:   


Line 272: Line 389:
REQUEST:   
REQUEST:   


13.2 The summary of the initial testing of the operating reactor (tables 13.3-1A through 13.1-1D) omits a "Plant Trip Test."  In the case of two other current Westinghouse PWR plants, such a test has been listed "to verify reactor control performance" under conditions of "full load rejection from 30% and 100%."  Section 14.1.10 of the FSAR indicates that "the unit is designed to accept a 50 percent step loss of load without actuating a reactor trip.  "Was this test inadvertently omitted or will it not be performed?  If it will not be performed state your reasons.
13.2 The summary of the initial testing of the operating reactor (tables 13.3-1A through 13.1-1D) omits a "Plant Trip Test."  In the case of two other current Westinghouse PWR plants, such a test has been listed "to verify reactor control performance" under conditions of "full load rejection from 30% and 100%."  Section 14.1.10 of the FSAR indicates that "the unit is designed to accept a 50 percent step loss of load without actuating a reactor trip.  "Was this test inadvertently omitted or will it not be performed?  If it will not be performed state your  
 
reasons.  
 
RESPONSE:   
RESPONSE:   


Line 279: Line 399:
REQUEST:   
REQUEST:   


13.3 Provide a bar-type chart illustrating the sequential and concurrent scheduling of the entire testing program relative to plant temperature, pressure, and power level. Special applicable plant configurations such as "head off" or "head on", should be indicated.
13.3 Provide a bar-type chart illustrating the sequential and concurrent scheduling of the entire testing program relative to plant temperature, pressure, and power level. Special applicable plant configurations  
 
such as "head off" or "head on", should be indicated.  
 
RESPONSE:   
RESPONSE:   


Revision as of 01:33, 30 June 2018

Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Appendix B, Questions and Responses Related to Initial NRC Review of Operating License Application
ML16330A243
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 10/29/2016
From:
Florida Power & Light Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16330A191 List:
References
L-2016-198
Download: ML16330A243 (13)
v • d • e


Text

APPENDIX B

QUESTIONS AND RESPONSES RELATED

TO

INITIAL NRC REVIEW

OF

OPERATING LICENSE APPLICATION

B-1

PAGES B-2 THROUGH B-39

HAVE BEEN INTENTIONALLY DELETED.

B-2 Rev 5 7/87 12.0 Conduct of Operations

REQUEST:

12.1 Provide an organization chart of corporate management showing the scope and relationship of the corporate structure to the onsite operating

organization. The organization for corporate, consultant, vendor, and other technical support should be delineated in more detail with regard to the technical expertise available to specifically support the

nuclear plant.

RESPONSE:

Refer to FSAR Figures 12.1-2 and 15.6.1, and pages 12.1.1-1 and 12.1.1-2, and Figure 6.1 of the Technical Specifications.

REQUEST:

12.2 The Facility Organization Chart (Figure 12.1-1) does not clearly or adequately depict the nuclear plant operating organization described in Section 12.1.1, especially with respect to single vs. dual unit

operation. Please provide the following additional information:

a. Justification for the adequacy of the proposed six man dual unit staffing in order to determine whether or not the proposed crew size is sufficient to adequately cope with plant operating requirements during routine, abnormal, and emergency situations

affecting both nuclear units.

b. The facility organization chart should be modified to show the complete shift crew operating organization for single and dual unit operation. The generic term "plant operators", used on the existing organization chart, coupled with the absence of the crew

disposition for single and dual unit operation, does not adequately delineate the shift crew organization and their

attendant responsibilities.

c. In addition to personnel position requirements and qualifications, a brief description of the duties, responsibilities, and authorities of individual plant positions should be indicated.

What is the function of the "Plant Engineer - Results"?

Specifically, what kind of personnel are assigned under his supervision and what are their functions? Is the "Nuclear Operator" referred to in Section 12.1.1 (but not shown in Figure 12.1-1) a licensed reactor operator or is he equivalent to an

"Auxiliary Operator"?

d. Indicate the experience level of maintenance repairmen who will perform maintenance and repair of-the-nuclear plant and its

components and auxiliaries.

B-40 RESPONSE:

a. Refer to FSAR page 12.1.1-2.
b. Refer to FSAR Figure 12.1-1 and page 12.1.3-23.
c. Refer to FSAR pages 12.1.3-18 and 12.1.3-24.
d. Refer to FSAR page 12.1.3-25.

REQUEST:

12.3 The actual qualifications of some key plant personnel appear to be substantially less than the minimum qualification, requirements (nuclear) stated for those key positions in the FSAR. This observation is based upon apparent deficiencies in the critical areas of nuclear power plant operating experience coupled with deficiencies in associated reactor technical areas such as reactor core physics, nuclear plant maintenance, chemistry, and radio-chemistry. Provide justification for the adequacy of technical expertise in the above

areas.

RESPONSE:

Refer to FSAR Section 12.1.3.

REQUEST:

Indicate the position title of the individual who is responsible for the conduct and administration of the nuclear power training program.

RESPONSE:

Refer to FSAR page 12.2.1-1.

REQUEST:

12.5 Indicate the scope and content of training programs that have been provided for reactor plant technicians, auxiliary operators, or their

equivalents, turbine operators, and repairmen.

RESPONSE:

Refer to FSAP page 12.2.3-1.

B-41 REQUEST:

12.6 Provide information concerning the course entitled "Operation Aspects of Radiation Surveillance - 1969" with regard to length and content of course and where conducted (This course is listed under education and

training for "Plant Engineer - Chemistry and Health Physics")

RESPONSE:

Refer to FSAR page 12.2.1-3.

REQUEST:

12.7 Indicate the scope and content of the retraining (refresher) program, and state which positions will receive formal retraining. The maximum

retraining program cycle should be indicated.

RESPONSE:

Refer to FSAR page 12.2.1-4.

REQUEST:

12.8 Indicate the scope and content of the replacement training program unless it is your intention to utilize the "Westinghouse Reactor Operator Training Program" for subsequent replacement personnel, in

which case a statement to that effect should be included in the FSAR.

RESPONSE:

Refer to FSAR page 12.2.2-1.

REQUEST:

12.9 What means will be provided to evaluate the effectiveness of the training, retraining, and replacement training programs?

RESPONSE:

Refer to FSAR page 12.2.1-5.

B-42 REQUEST:

12.10 Has a general employee training program been incorporated in the training program to ensure that all plant personnel are trained in (1)

Industrial Safety, (2) First Aid, (3) Radiological Health and Safety, (4) Industrial Security, (5) Use of Protective Clothing and Equipment,

and (6) Appropriate Plans and Procedures?

RESPONSE:

Refer to FSAR page 12.2.1-5.

REQUEST:

12.11 Provide a listing (by titles) of written procedures specified for station operation.

RESPONSE:

Refer to FSAR Section 12.3.

REQUEST:

12.12 Indicate the normal locations and accessibility of various written procedures and plans specified for station operation.

RESPONSE:

Refer to FSAR Section 12.3.

REQUEST:

12.13 Describe the method you will use for assuring that procedures have been distributed, read and understood, and are complied with by station

personnel.

RESPONSE:

Refer to FSAR Section 12.3.

B-43 REQUEST:

12.14 List those procedures for which check-off lists are specified. How are check-off lists completed and approved?

RESPONSE:

Refer to FSAR Section 12.3.

REQUEST:

12.15 Provide a complete listing (by titles) of the specific types of records to be kept. Are training records and personnel experience/qualification records kept? Are Quality Assurance Control records kept? What are the

titles of the general types of operating records kept?

RESPONSE:

Refer to FSAR page 12.4.1-1.

REQUEST:

12.16 What recording methods (recorder, computer, manual) are employed for the various types of records?

RESPONSE:

Refer to FSAR page 12.4.1-1.

REQUEST:

12.17 Indicate the position title of the individual who has direct responsibility for records management.

RESPONSE:

Refer to FSAR page 12.4.1-1.

B-44 REQUEST:

12.18 The brief description of industrial security appearing in Section 12.5 (administrative control) should be expanded to include the specific types of security measures to be employed to guard against and detect unauthorized access to the reactor site, reactor control areas, and principal buildings or other critical areas of the facility (e.g. are personnel identification badges, perimeter lighting, alarms, television

etc. employed?).

RESPONSE:

Refer to FSAR page 12.5-1.

REQUEST:

12.19 Indicate the methods of controlling the various types of expected visitors.

RESPONSE:

Refer to FSAR Section 12.5.

REQUEST:

12.20 The controls or methods specified for guarding critical plant features against acts of sabotage should be indicated.

RESPONSE:

Confidential policy matters will be the subject of a separate proprietary document.

REQUEST:

12.21 The spectrum of emergencies classified and defined in Section 12.3.2 (Emergency Procedures) are properly a part of the Section 12.3.3 (Emergency Control Plan). However, in addition to classification and definition of emergencies, the consequences of the various types of accidents or emergencies should be considered in the Emergency Plan.

The consequences of radiological accidents ranging from accidents affecting only local operating personnel to the design basis accident

which could affect site and neighboring environment, should be

considered in greater depth than currently appears in Section 12.3.2.

RESPONSE:

Refer to FSAR page 12.3.3-1, Table 12.3.3-1, and the Emergency Control Plan.

B-45 REQUEST:

12.22 The various locations of Emergency Procedures, drawings and diagrams of the plant, required in the event of implementation of the Emergency

Control Plan; should be specified.

RESPONSE:

Refer to FSAR page 12.3.2-1.

REQUEST:

12.23 Protective measures and corresponding protective action levels should be specified for each emergency or accident in the spectrum of emergencies or accidents considered in the "Emergency Control Plan."

The technical basis for each of the Protective Measures should be supported in the plan along with a description of the available plant instrumentation and other instrumentation (including portable

monitoring equipment) which is used as a basis for the development of

the various Protective Action Levels.

RESPONSE:

Refer to FSAR page 12.3.3-1 and Table 12.3.3-1 and Section 11.2.3.

REQUEST:

12.24 Are individual facility (unit) Emergency Control Plans to be developed? Is a compatible site Emergency Plan to be developed? Consideration should be given to accident consequences and emergency procedures for

one-unit (fossil or nuclear) affecting another unit.

RESPONSE:

Refer to FSAR page 12.3.3-1 and the Emergency Control Plan.

REQUEST:

12.25 The role of the offsite support groups, their authorities, and their responsibilities with regard to a plant emergency, should be described in the Emergency Control Plan. Are agreements with offsite support

groups being confirmed in writing? Local law enforcement agencies and civil defense agencies are not mentioned as offsite support groups.

What are their roles?

RESPONSE:

Refer to FSAR page 12.3.3-1 and the Emergency Control Plan.

B-46 REQUEST:

12.26 The significant features of the medical plan (referred to in Section 12.3.2 as "being developed with the medical school and hospital")

should be reflected in the Emergency Control Plan. The scope of available local medical support, experienced and trained in treating

victims of radiological accidents, should be indicated.

RESPONSE:

The medical support is being developed.

REQUEST:

12.27 The scope of Emergency Control Plan training and drills should be addressed. Will training and drills involve all support groups? How

often will drills be held?

RESPONSE:

Refer to FSAR page l2.3.3-6.

REQUEST:

12.28 It is implied in Section 12.3.3 that the plant security guards are furnished by a contract guard service company. The guard on duty at the facility is identified as a member of the Emergency Monitoring Team

with training in the use of radiation survey instruments. What is the scope of this training and who is responsible for conducting it? Are there enough replacement guards trained in the use of the equipment what assurance exists that only these specially trained personnel will

be used to guard the nuclear power plant?

RESPONSE:

Guards will not be used for Emergency Monitoring.

REQUEST:

12.29 What are the "established criteria" and "prescribed limits" (referred to in Section 12.3.2) for putting the offsite vs onsite portions of the Emergency Plan into effect? What are the provisions for emergency

dosimetry and tracking of offsite releases?

RESPONSE:

Refer to the Emergency Control Plan.

B-47 REQUEST:

12.30 Have alternate personnel been designated to man hey positions within the Emergency Control Plan Organization? (e.g., the Conservation

Supervisor on Emergency Monitoring Team)

RESPONSE:

Refer to FSAR Section 12.3.2 Conservation Supervisor duties have been changed.

REQUEST:

12.31 Describe distinguishing feature of various alarms associated with the Emergency Control Plan. Has a test been conducted to ascertain auditibility in all required areas, particularly in areas of high noise

level or acoustically insulated areas?

RESPONSE:

Refer to FSAR page 12.3.3-4.

REQUEST:

12.32 Has a plan been developed which makes adequate provision for coordination and dissemination of public information released following

an accident?

RESPONSE:

Refer to FSAR page 12.3.2-2 and 12.3.2-3.

B-48 13.0 Initial Tests and Operations

REQUEST:

13.1 Provide details of the organizational structure for pre-operational testing, fuel loading, startup, and initial testing of the operating reactor. Position titles, station-groups (operations, technical,

maintenance) to which assigned, functional roles, responsibilities, and qualifications of any augmenting personnel should be indicated during

the above phases of operations. Planned augmentation of regular shift crew personnel should be indicated along with a summary of functional

roles, responsibilities and qualifications.

RESPONSE:

Refer to FSAR Section 13.1.1.

REQUEST:

13.2 The summary of the initial testing of the operating reactor (tables 13.3-1A through 13.1-1D) omits a "Plant Trip Test." In the case of two other current Westinghouse PWR plants, such a test has been listed "to verify reactor control performance" under conditions of "full load rejection from 30% and 100%." Section 14.1.10 of the FSAR indicates that "the unit is designed to accept a 50 percent step loss of load without actuating a reactor trip. "Was this test inadvertently omitted or will it not be performed? If it will not be performed state your

reasons.

RESPONSE:

Refer to FSAR Table 13.3-1c.

REQUEST:

13.3 Provide a bar-type chart illustrating the sequential and concurrent scheduling of the entire testing program relative to plant temperature, pressure, and power level. Special applicable plant configurations

such as "head off" or "head on", should be indicated.

RESPONSE:

Refer to FSAR page 13.1-4.

B-49 PAGES B-50 THROUGH B-51

HAVE BEEN INTENTIONALLY DELETED.

B-50 Rev 5 7/87

Retrieved from "https://kanterella.com/w/index.php?title=ML16330A243&oldid=760234"