ML20054G478
| ML20054G478 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/14/1982 |
| From: | Morisi A BOSTON EDISON CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM 82-170, NUDOCS 8206210593 | |
| Download: ML20054G478 (45) | |
Text
.
BOWTON EDISDN COMPANY osmanAL carecre soo sorteTon sTasse SQ WTON. M AS E ACHUBETTS O2199 A. V. M O RIsl MANAoER NUCLEAR OPERATIONS SUPPORT DEPARTMENT June 14, 1982 BECo. Ltr. #82-170 Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555 License No. DPR-35 Docket No. 50-293
Dear Sir:
We have reviewed your letter of April 27, 1982 regarding upgraded SR0 and R0 Training Programs and Training for Mitigation of Core Damage.
Specifically your letter requested answers to eight questions before you can complete your evaluation of NUREG 0737 Action Items:
I.A.2.1 Immediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualifications 11.6.4 Training for Mitigating Core Damage Our response to each question follows:
1.
The PNPS Training Manual fails to give the details of any training lectures.
However, it did list some " FORMS" under Section 3.1.1.1.
In order for us to complete our evaluation, we need details of all the forms listed under Section 3.1.1.1; please send copies of the forms and explain exactly how they are used.
Response
The following forms are listed in Section 3.1.1.1:
Yh Form 0-1 General Indoctrination Form 0-2 Qualification Requirements for Nuclear Plant Operator Form 0-3A Qualification Requirements for Nuclear Operating Supervisor Fonn 0-3B Qualification Requirements for iluclear Watch Engineer Fonn 0-4 Qualification Requirements for Senior Reactor Operator 8206210593 820614 PDR ADOCK 05000293 P
CO3 TON EDICON COMPANY Mr. Domenic B. Vassallo, Chief June 14, 1982 Page 2 Form 0-5 Qualification Requirements for Nuclear Auxiliary Operator Form 0-6 Qualification Requirements for " Fuel. Handler" (Limited SR0 License)
A copy of each form is enclosed with this letter.
A description of how each form is used follows:
A.
Form 0-1 provides a guideline to new employees in the Operations Group.
The employee reads the listed procedures and reviews them with an Ins tructor.
B.
Form 0-2 is used to document our Hot License Program requirements. The license candidate must complete Form 0-2 in order to sit for the NRC Deactor Operator's Examination.
C.
. corm 0-3A is used to document the qualification requirements for Nuclear Operating Supervisors.
D.
Form 0-3B is used to document the qualification requirements for Nuclear Watch Engineers.
E.
Form 0-4 is used to document our SR0 Hot License Program requirements.
The SRO License candidate must complete Form 0-4 in order to sit for the NRC Senior Reactor Operator's License.
F.
Form 0-5 is used to document initial training for the Nuclear Auxiliary Operators (now Licensed Radwaste Operators).
G.
Form 0-6 is used to document initial training to qualify a person to sit for the NRC Senior Reactor Operator's License Limited to Fuel Handling.
2.
De Forms 0-2 and 0-4 provide for lectures which cover the subjects of heat transfer, fluid flow and thermodynamics as called out in Enclosure 1 of Denton's March 28, 1980 letter? If they do, do these lectures in fact cover this material to the level of detail spelled out in Enclosure 2 of the Denton letter? Please send course outlines if available.
Response
Form 0-2 and 0-4 do provide for lectures which cover the subjects of heat transfer, fluid flow,and thermodynamics as called out in Enclosure 1 of Denton's letter of March 28, 1980.
We believe these lectures meet the detail spelled out in Enclosure 2 of the Denton letter. A copy of the course outline in attached.
CO2 TON EDCON COMPANY Mr. Domenic B. Vassallo, Chief June 14,1982 Page 3 3.
Does' Operations Group Training (Section 3.1) have lectures which address the subject of using installed plant systems to control or mitigate an accident in which the core is severely damaged? This requirement is called out in of Denton's letter.
Do these lectures address the topic to the level spelled out in Enclosure 3 of Denton's letter? Please send a course outline if available.
Response
We are at present using a book " Recognizing and Mitigating the Consequences of Severe Reactor Core Damage" by General Pnysics Corporation. We refer you to the Introduction of that book, Page 1-1, for information on course content and how it was developed. A copy of the introduction and course outline is enclosed for your review.
The above 2, Honed book is a Generic BWR Course prepared by General Physics.
At present General 'hysics is under contract with 'us to prepare a site specific book. We will use that book for both Initial and Requalification Training on Mitigation of Core Damage.
4.
Are the lectures and quizzes on the subject of accident mitigation given to Shift Technical Advisors and Operating personnel from the Plant Manager through the operations chain to the licensed Operators? If they are, would you please provide the titles of the people who are trained and an organization chart which illustrates their position in the operations chain?
Response
All qualified Shift Technical Advisors, Nuclear Plant Operators, Nuclear Operations Supervisors and Nuclear Watch Engineers have received Mitigation of Core Damage Training.
In addition the Nuclear Operations Manager and the two (2) Deputy Nuclear Operations Managers have received Mitigation of Core Damage Training.
An organization chart for the Pilgrim Nuclear Power Station is enclosed. The chart illustrates those people referenced above.
5.
Do the training and requalification program elements which involve heat transfer, fluid flow, thermodynamics and accident mitigation involve 80 contact hours in l
each program? (A contact hour of instruction is a one-hour period in which the course instructor is present or available for instructing or assisting students; lectures, seminars, discussions, problem-solving sessions, and examinations are considered contact periods under this definition.)
Response
We request you review the attachments referenced in our responses to Items #2 and #3.
Our heat transfer, thermodynamics and fluid flow course is 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
CO] TON EoCON COMPANY Mr. Domenic B. Vassallo, Chief June 14,1982 Page 4 The General Physics Mitigation of Core Damage course is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
6.
Is there an increased emphasis on reactor and plant transients in the reactor operator and senior reactor operator training program as required by Item
' A.2.C(3) of Enclosure 1 of Denton's March 28, 1980, letter? If there is, does this training deal with both normal transients and abnormal (accident) transients?
Response
Our Reactor Operator and Senior Reactor Operator training on transient analysis has received increased emphasis with both normal and abnormal transients.
General Electric, under contract to us, has rewritten their abnormal event analysis book to be site specific to Pilgrim Nuclear Power Station. This course is 40 contact hours. A course outline is enclosed.
7.
The PNPS NRC Licensed Operator Requalification Program, Rev. 5, has lectures which have the potential for covering the subjects of heat transfer, fluid flow and thermodynamics as called out in Enclosure 1 of Denton's March 28, 1980 letter.
Do these lectures in fact cover this material and is the coverage to the level of detail spelled out in Enclosure 2 of the Denton letter? Please send a course outline if it differs from that used in the training program.
Response
We plan to use the same material developed for the initial License Program in the Licensed Operator Requalification program.
Information regarding that material was detailed in our response to Item #2. Portions of this material will be reviewed on a periodic basis.
8.
Does PNPS NRC Licensed Operator Requalification Program, Rev. 5, have lectures which address the subject of using installed plant systems to control or miti-gate an accident in which the core is severely damaged? This requirement is called out in Enclosure 1 of Denton's letter.
Do these lectures address the topic to the level spelled out in Enclosure 3 of Denton's letter? Please send a course outline i# it differs from that used in the training program.
Response
We plan to use the same material developed for the initial License Program in the Licensed Operator Requalification program.
Information regarding that material was detailed in our response to Item #3.
Portions of this material will be reviewed on a periodic basis.
COOTON EDicDN COMPANY Mr. Domenic B. Vassallo, Chief-June 14, 1982 Page 5 t!e trust these responses are adequate to complete your review process.
If you require additional information on these matters please feel free to contact Mr. William F. Olsen, Operation Training Supervisor at Pilgrim Station at (617)-
424-3817.
Very truly yours, f
i' Enclosure-cc w/
Enclosure:
Dr. R. T. Liner Scierce Applications, Inc.
1710 Goodridge Drive McLean, Virginia 22102
Form 0-1 Paga 1 of 1 PNPS OPERATIONS GROUP TRAINING GENERAL INDOCTRINATION Name Social Security #
Complete an indoctrination on the procedures and instructions which are applicable to the Operations Group that implement the Quality Assurance Program.
This indoctrination will include the following:
1.
1.1.1 Station Organization and Responsibility 2.
1.2.1 Operations Review Committee 3.
1.3.2 Special Orders 4.
1.3.4 Procedures 5.
1.3.6 Adherence to Technical Specifications 6.
1.3.7 Records 7.
1.3.8 Document Control 8.
1.3.9*
Reports 9.
1.3.13 Plant Design Changes 10.
1.3.14 Indoctrination and Training 11.
1.3.16 Conduct of Personnel in Control Room 12.
1.3.23*
Preparation of Safety Evaluations 13.
1.3.24 Failure and Malfunction Reports 14.
1.3.26*
Response to Deficiency Reports 15.
1.4.5 PNPS Tagging Procedure 16.
1.4.6 Housekeeping 17.
1.5.3 Maintenance Request 18.
1.5.7 Unplanned Maintenance 19.
3.M.1-l*
Preventative Maintenance 20.
1.5.9 Temporary Modifications 21.
3.M.1-5 Procurement of Items and Services 22.
3.M.1-8*
Disposition of Non-Conforming Material 23.
8.1 Periodic Surveillance Test Requirements Satisfied:
a) 10CFR50, Appendix B b)
ANSI N18.7 c)
BEQAM, Volume II Date Completed Signature, Day Watch Engineer Date Signature, Nuclear Training Specialist
- Management Only Date Senior Nuclear Training Specialist Return completed form to the Training Dept.
)
e Rev 4
Form-0-2 Pcg2 1 of 8 PNPS Qualification R0guiremente for Nuclear Plant Operator Name A.
Prior to NRC Licensed Operator Training 1.
Meet all " qualifications" specified in the Nuclear Plant Operator " job qualification," Regulatory Guide 1.8 and PNPS Procedure #1.3.14.
Date Certified Signature, Day Watch Engineer Requirements Satisfied:
a)
Regulatory _ Guide 1.8 (ANSI N18.1, Section 4.5.1) b)
" Nuclear Plant Operator" Job Specification 2.
Complete Form 0-1 Operations Group Training General Indoctrination Date Signature,I4uclear Training Specialist or Day Watch Engineer 3.
Demonstrate the ability to safely and correctly tag equipment out, as per procedure #1.4.5.
Date Signature, Nuclear Training Specialist or Day Watch Engineer 4.
Demonstrate the ability to read and record supplementary operating log data, Date Signature, Nuclear Watch Engineer, Day Watch Engineer or Nuclear Training Specialist 5.
Demonstrate the ability ta operate, read (and record) radiation detection instruments including:
a.
PIC-6A Date Initials, Instructor b.
PRM-4A Date Initials, Instructor
)
Form 0-2 Pcgn 2 of 8 c.
Telectector Date Initials, Instructor d.
RO-2A Date Initials, Instructor Date Signature, Nuclear Watch Engineer or Nuclear Training Specialist 6.
Demonstrate the ability to perform necessary decontamination activities as required.
Date Signature, Nuclear Watch Engineer or Nuclear Training Specialist 7.
Demonstrate the ability to perform routine operating maintenance on equipment and instruments.
Date Signature, Nuclear Watch Engineer or Nuclear Training Specialist 8.
Demonstrate the ability to satisfactorily perform a Nuclear Plant operation tour as outlined in PNPS General Plant Operating Procedure #2.1.16 (Oper #8).
Date Signature, Nuclear Watch Engineer or Nuclear Training Specialist B.
NRC Licensed Operator Training 1.
Successfully complete the NRC licensing preparatory course within first enrollment.
Course Average Hours Date Signature, Nuclear Training Specialist 2.
Candidate must be knowledgeable of the systems safety function, design basis, major components, surveillance requirements, significant instrumen-tation setpoints, interlocks and modes of operation.
Candidate must also be knowledgeable of normal operating procedures, safety-related procedures and the Technical Specificaticns governing the system.
, Rev 4
Form 0-2 Prga 3 of 8 SIGNATURE, NUCLEAR WATCH ENGINEER SYSTEM DATE OR NUCLEAR TRAINING SPECIALIST a.
Reactor Vessel & Internals b.
Fuel c.
Reactor Vessel Instrumenta-tion d.
C.R.D.
including C.R.D.
hydraulics RPIS & Reactor Manual Control System e.
Recirculation & Flow Control f.
Nuclear Instrumentation --
Including SRM, LRM, LPRM, APRM, RBM & TIP System h.
Main Steam j.
Turbine L.O.
System k.
Generator & Auxiliaries 1.
Turbine Control System m.
Feed & Condensate System n.
Reactor Vessel Water Level Control
SIGNATURE, NUCLEAR WATCH ENGINEB SYSTEM DATE OR NUCLEAR TRAINING SPECIALIST o.
AC Distribution p.
Diesel Gen. & Emerg. Power Distribution q.
D.C.
Distribution r.
Pri. & Secondary Containment t.
RHR System v.
Core Spray w.
HPCI x.
Reactor Core Isolation Cooling y.
A.D.S.
2.
Salt Water Sys.
aa.
Salt service Water bb.
TBCCW cc.
RBCCW dd.
Fire Protection System ei ee.
Compress Air System Rev 3
4 SIGNATURE, NUCLEAR WATCH ENGINEEC SYSTEM DATE OR NUCLEAR TRAINING SPECIALIST ff.
Standby Gas Treatment Sys.
gg.
Augmented Off Gas System hh.
Process Radiation Monitoring ii.
Area Radiation Monitoring jj.
Refueling Equipment 3.
Participate in the manipulation of reactor plant controls during day-to-day operation at least six (6) months.
Applicant has three (3) months training on shift as an extra person in the control room.
Date Signature, Day Watch Engineer Requirements Satisfied:
(a) 10CFR55.10a (6)
(b)
Regulatory Guide 1.8 (ANSI N18.1, Section 5.2.2)
(c)
OLB Guide #3 (d)
NRC letter from H.
Denton of March 28, 1980 4.
Complete one of the following:
A.
Manipulate the controls of the reactor during two training startups Date Signature, Nuclear Watch Engineer Date Signature, Nuclear Watch Engineer B.
Satisfactorily complete an NRC approved training program of at least one week duration at a nuclear power plant simulator (attach certification).
Simulator Used Dates at Simulator Date Signature, Nuclear Training Specialist Rev 3
Form 0-2 Paga.. of 8'
]
Requirements Satisfied:
.(a) 10CFR55.10a (6)
(b)
Regulatory Guide 1.8 (ANSI N18.1, Section 5.2.2)
(c)
OLB Guide #3 5.
Participate in at least five significant reactivity l
changes.
(Refer to Section 3.1.2A.1.3 for approved reactivity manipulations)
Reactivity Date
-Signature, Nuclear Watch Engineer Manipulation #
Reactivity Date Signature, Nuclear Watch Engineer Manipulation #
Reactivity Date Signature, Nuclear Watch Engineer Manipulation #
I Reactivity Date Signature, Nuclear Watch Engineer j
Manipulation
- i j
Reactivity Date Signature, Nuclear Watch Engineer Manipulation #
-t I
Requirements Satisfied:
(a) 10CFR55.10a (6)
(b)
(ANSI N18.1, Section 5.2.2) 4, (c)
OLB Guide #3 4
C.
After completing assigned training, demonstrate satisfactory knowledge in the following areas:
l.
Principles of Nuclear Power Plant Operation j
Quiz Grade 2.
Fundamentals of Thermodynamics, Heat Transfer and fluid flow Quiz Grade 3.
Plant systems design, including safety and emergency systems-Quiz Grade j
i 4
I Rev. 4
,1---
_.,+.---.r.-,,,
., - - -. -. -. -. - -. - - - -. + -
~-,e-m-y..
+
,m,
Form 0-2 rage i or u a
4.
Instrumentation and controls Quiz Grade 5.
Procedures - Normal, abnormal, emergency.and radiological control Quiz Grade Overall Average NOTE:
The applicants must obtain an overall average of 80% and 70% per section.
Requirements Satisfied:
(a)
Regulatory Guide 1.8 (ANSI N1.8.1, Section 5.2.1)
(b) 10CFR55.21 (c)
OLB Guide #1, Section.E (d)
NRC letter from H.
Denton of March 28, 1980 D.
Evaluation 1.
Successfully complete an NRC Simulated Oral Examination administered by the Nuclear Training Specialist (attach Form 0-7)
Note:
This evaluation may be conducted by an independent consultant.
In this case their evaluation form may replace Form 0-7.
Point Average from Form 0-7 (if used)
Date passed Signature, Nuclear Training Specialist 2.
Successfully complete a NRC Simulated written examination Note:
This examination may be administered by an independ-ent consultant.
l i Rev. 4
Category Grade 1.
Principles of Nuclear Power Plant Operation 2.
Fundamentals of Thermodynamics, heat transfer and fluid flow 3.
Plant systems design, including safety and emergency systems
~4.
Instrumentation and controls 5.
Procedures-Normal, abnormal and radiological control (Note:
Passing Grade is 80% overall and 70%/section)
Overall Grade Date Passed Signature, Nuclear Training Specialist 3.
Recommended for NRC Examination Date Signature, Nuclear Training Specialist Date Signature, Senior Nuclear Training Specialist Date Signature, Nuclear Operations Manager Requirements Satisfied:
(a)
(ANSI N18.1, Section 5.5)
(c)
NRC letter from H.
Denton of March 28, 1980 E.
License Issued i
j License Number Date Issued i
i
( Rev. 4 I
Form 0-3A Pcg3 1 cf 1 PNPS Qualification Requirements for Nuclear Operating Supervisor Name 1.
Meet all qualifications specified in job specification.
Date Certified Signature, Day Watch Engineer 2.
Demonstrate the ability to perform job-related surveillance tests and inspections.
Date Signature, Day Watch Engineer 3.
Form 0-4 completed Date Signature, Nuclear Training Specialist 4.
Qualification as Nuclear Operating Supervisor certified complete.
Date Signature, Day Watch Engineer Date Signature, Nuclear Training Specialist Date Signature, Sr. Nuclear Training Specialist m
O w
,-n.-
g
-w--
Form 0-3B Prgs 1 of 1 PNPS Qualification Requirements for Nuclear Watch Engineer Name i
1.
Meet all qualifications specified in job specification.
Date Certified Signature, Day Watch Engineer j
2.
Form 0-4 completed Date Signature, Nuclear Training Specialist
)
3.
Demonstrate the ability to perform job-related surveillance tests and inspections.
Date Signature, Nuclear Training Specialist
]
4 4.
Qualification as Nuclear Watch Engineer certified complete.
Date Signature, Day Watch Engineer Date Signature, Nuclear Training Specialist 1
r Date Signature, Sr. Nuclear Training Specialist i
i Y
.l 4
l
Form 0-4 Pcga 1 of 3 Qualification Requirements for-Senior Reactor Operator Name NRC Operators License Number Date Issued (Note:
The SRO applicant shall have held an NRC Operators License for one year)
NRC Licensed Senior Operator Training 1.
Successfully complete all NRC Licensed Operator-licensing requirements specified in the " Qualification Requirements for Nuclear Plant Operator," (Form 0-2).
Date Certified Signature, Nuclear Training Specialist 2.
After completing assigned training, demonstrate satisfactory knowledge in the following areas:
1.
Theory of Nuclear power plant operation Quiz Grade 2.
Theory of fluids and thermodynamics Quiz Grade 3.
Plant systems design, control and instru-Tentation Quiz Grade 4.
Procedures-normal, abnormal, emergency and radiological control Quiz Grade-i 5.
Administrative Procedures, Conditions and Limitations Quiz Grade n
i r
l Rev. 4 i
l.
Form 0-4 pegg-2 of-3 g.
Overall Average Note:
Passing score is 80% overall and 70%-
per section.
Requirements Satisfied:
(a)
Regulatory Guide-l.8 (ANSI N18.1, Section 5.2.1).
(b) 10CFR55.22 (c)
OLB Guide 41, Section E (d)
NRC letter from H.
Denton of March 28, 1980 Date Signature, Nuclear Training Specialist 3.
Evaluation a.
Successfully complete an NRC Simulated Oral Examination (attach Form 0-7)
Note:
This examination may be administered by an independent consultant.
Their form maybe used in place of Form 0-7.
Point Average Grade from Form 0-7 Date Signature, Nuclear Training Specialist (Note:
Passing grade is a point average grade of 3.0) b.
Successfully complete the senior portion of an NRC simulated written examination.
Category Grade 1.
Theory of Nuclear Power plant operation.
2.
Theory of fluids and thermodynamics 3.
Plant systems design, control and instrumen-tation.
}
4.
Procedures - normal, abnormal, emergency and radiological control Rev. 4
L 5.
Administrative Procedures, Conditions and Limitations (Note:
Passing grade, 80% overall, 70%/section)
Overall Average Note:
This examination may be administered by an independent consultant.
Date Passed Signature,-Nuclear Training Specialist-Requirements Satisfiad:
(a)
Regulatory Guide 1.8 (ANSI N18.1, Section 5.5)
(b)
NRC letter from H.
Denton of March 28, 1980 c.
Recommended for NRC SRO Examination Date Signature, Nuclear Training Specialist Date Signature, Sr. Nuclear Training Specialist Date Signature, Nuclear Operations Manager 4.
Successfully complete the NRC Senior Reactor Operator Examination.
License Number Issued Date 1 Rev 4
Form 0-5 Pcga 1 of 3 k,? '.
t Qualification Requirements for Nuclear Auxiliary Operator Name SSN i
1.
Complete Form 0-1, Operations Group Training General Indoctrination.
4 i
Date Signature, Nuclear ~ Training Specialist or Day Watch Engineer 4
2.
Meet all Qualifications specified in the Nuclear Auxiliary l
Operato'r job specification.
i Y
u j
Date Signature, Radwaste Supervisor i
i 3.
Demonstrate the ability to properly and safely-I operate the radwaste system, process demineralizers, liquid filters and associated chemical control equipment.
1 Date Signature, Radwaste Supervisor i
4.
Demonstrate the ability to monitor the operational performance of the above equipment and identify, report and followup on items requiring maintenance.
1 Date Signature, Radwaste Supervisor 5.
Demonstrate the ability to perform lubrication checks of equipment within the scope of the Radwaste Group.
l Date Signature, Radwaste Supervisor 1
I l
i 1
1 j
am n-..
4 4
Form 0-5 Pega 2'of 3
/
6.
Demonstrate the ability'to'take samples of water or chemicals.
Date Signature, Radwaste Supervisor 7.
Demonstrate the ability to perform routine operating maintenance on chemical and radiochemical control sub-systems, including demineralizers, filters and pumps.
Date Signature, Radwaste Supervisor 8.
Demonstrate the ability to make radiation and contamin-ation surveys using portable and stationary radiation monitoring devices and to calibrate and perform operating maintenance on these devices.
Date Signature, Radwaste Supervisor 9.
Demonstrate the ability to perform decontamination work.
Date Signature, Raduaste Supervisor 10.
Demonstrate the ability to apply those principles learned in the General Employee " Radiological Health and Safety Indoctrination" on-the-job.
Specifically, demonstrate the ability to:
(a)
Control the spread of contamination (b)
Minimize one's own radiation exposure (c)
Properly use personnel monitoring equipment (d)
Decontaminate both personnel and equipment Date Signature, Raduaste Supervisor s Rev 3
Form 0-5 pig 3 3 Cf 3 0
4 11.
Qualification as Nuclear Auxiliary Operator certified complete.
Date Signature, Radwaste Supervisor Date Signature, Day Watch Engineer Date Signature, Senior Nuclear Training Specialist Requirements Satisfied:
Regulatory Guide 1.8 (ANSI N18.1, Section 5.3.4) 1 I
i l'
l
, Rev 4
y a.
Form 0-6 Pago 1 of 3-i-
PNPS Qualification Requirements for Fuel Handlers, Limited SRO License Holders Name 1.
Complete Form 0-1, the Operations Group Training Checklist.
Date Signature, Nuclear Training Specialist' or Day Watch Engineer 2.
Successfully complete a fuel handler training program emphasizing the theoretical and practical aspects of fuel handling (attach program outline).
Course Grade Hours Date Signature, Nuclear Training Specialist 3.
Participate in the following on-the-job training:
a.
Perform three dummy fuel assembly manipulations Date Signature, Nuclear Training Specialist or Nuclear Watch Engineer Date Signature, Nuclear Training Specialist or Nuclear Watch Engineer Date Signature, Nuclear Training Specialist or Nuclear Watch Engineer b.
Demonstrate the ability to perform job related surveillance tests and inspections.
Date Signature, Nuclear Training Specialist or Nuclear Watch Engineer Rev 3
' Form 0-6 Paga 2 of 3 0'
4.
After completing assigned trafning, demonstrate satisfactory knowledge in-the following areas:
a.
Reactor and Fuel Characteristics b.
Equipment and Instrumentation Description and Design c.
Procedures and Limitations d.
Emergency Systems and Safety Devices e.
Health Physics and Radiation Protection Date Signature, Nuclear Training Specialist 5.
Evaluation a.
Successfully complete an NRC Simulated SRO, Limited to Fuel Handling, oral examination (attach Form 0-8).
Grade (Average Point Value from Form 0-8)
Date Signature, Nuclear Training Specialist (Note:
Passing Grade - Average Point Value of 3.0)
Note:
An independent consultant may be used for this evaluation.
Their form may replace Form 0-8.
- Rev 3
Form 0-6 Paga 3 of 3.
b.
Successfully complete an NRC Simulated SRO, Li'mited to Fuel Handling, written examination.
Category Grade Reactor and Fuel Characteristics-Equipment and Instrumentation Descriptions and Designs Procedures and Limitations-Emergency Systems and Safety Devices Health Physics and Radiation Protection Thermodynamics Overall (Note: - Passing Grade 80% overall, 70%/Section)
An independent consultant may administer this examination.
4 Date Signature, Nuclear Training Specialist c.
Recommended for NRC Examination i
Date Signature, Nuclear Training Specialist 1
Date Signature, Senior Nuclear Training Specialist Date Signature, Nuclear Operations Manager 4
6.
Successfully complete the NRC Senior Reactor Operator, Limited to Fuel Handling, examination.
License Number Issued Date i
i J
w -,
I,.
..=
L..
,~
y '
HEAT TRANSFER, THERMODYNAM'ICS AND FLUID FLOW COURSE TABLE OF dONTENTS SECTION 1.
Introduction 2.
Goals 3.
Instructions 4.
Heat Transfer, Thermodynamics and Fluid Flow Course Outline (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) 4.1; Module 1, Basic Concepts of Heat Transfer and Thermodynamics - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.1.1; Submodule 1.1, Thermodynamic Properties:
Measurement and Conversion: ($ hours) 4.1/1; Submodule 1.1.,
Thermodynamics (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 4.1 5; Submodule 1.S, Heat Transfer Methods (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.1.g; Submodule 1.$, Problem Solving (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.1.jf; Module Review Quiz 4.2; Module 2, Heat Transfer Applications - 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 4.2.1; Submodule 2.1, Heat Cycles (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.2.2; Submodule 2.2, Heat Exchangers (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.2.3; Submodule 2.3, Reactor Heat Generation (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.2.4; Submodule 2.4, Reactor Fuel Heat Transfer (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 4.2.5; Module Review Quiz 4.3; Module 3, Reactor Thermal Limits - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4.3.1; Module Review Quiz
~
4.4; Module 4, Basic Concepts of Flnid Behavior - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.4.1; Submodule 4.1, Properties of Fluids (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.4.2; Submodule 4.2, Principles of Fluid Flow (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 4.4.3; Module Review Quiz
h,.,,., _,,. ;,
~
- - 4,"
..u..
i...
r
.._i ',
-i-
^
t s
s.
s-4.5; Module'5, Fluid Flow Applications - 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> y,
t.
4.5.1; Submodule 5.1, Pumps'(4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 4.5.2; Submodule 5.2, Systems and Components (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)
- 4.5.3; Submodule 5'.3, Core Heat Removal Considerations (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 4.5.4; Module Review Quiz.
4 4
e 4
.f b
T
!I.
l i
l i
l 9
5 k
.._,.L._..._
_._....--.m._,_,__,-__,,,,4,,,,,,r_..,._,-._,,,,
V N
.ma p
e 9
e g
6 m e e.ammmimme en.
i l
e---
e e.
p=m mmmm.
RECOGNIZING AND
- w-.-
MITIGATING -
_. -TH E CONSEQUENCES OF SEVERE REACTOR CORE DAMAGE i
I i
t h
E a.
TABLE OF CONTENTS I
o Chapter Page i
1 Introdus eion...
1-1 2
Three Mile Island Unit 2 Incident 2-1 A.
Introduction.
2-2 B.
Three Mile Island Unit 2 Transient.
2-2 Three Mile Island Graphs.
2-23 Three Mile Is' land Figures 2-31 3
Core Cooling Mechanics.
3-1 A.
Introduction.
3-1 4
B.
Heat Transfer Mechanisms.
3-2 C.
Heat Transfer in Reactor Elements 3-10 D.
Fundamentals, of Fluid Flow.
3-13 t
E.
Boiling Water Reactor Heat Transfer 3-18 F.
BWR Thermal-Hydraulics..............
3-26 G.
Critical Power.
3-33 H.
Linear He'at Generation Rate 3-41 I.
Average Planar Linear Heat Generation Rate (APLHGR).
3-45 J.
3-49 K.
Effectiver.2ss of Core Standby Cooling Systems 3-62 L.
Natural Circulation in a BWR.
3-77 M.
BWR Depressurization Transients and Fuel Clad Quenching Effects 3-81 N.
Corrosion Effects in the Primary Containment Following a LOCA.
3-90 O.
Core Heat Removal 3-92 P.
Steam Binding and Reactor Recirculation Pumps 3-94 Q.
LOCA Recovery Procedures to Mitigate Core Damage.
3-98 i
r TABLE CF CONTENTS (Continued)
Chapter Pace 4
Potentially Damaging Operating Conditions.
4-1 A.
Introduction...
4-1 B.
Plant Response to Loss of Feedwater Events.
4-5 C.
Small Break LOCA.
4-14 5
Recognizing Core Damage / Critical Plant Parameters 5-1 A.
Fission Product Release 5-1 B.
Isotopic Analy7es.
5-7 C.
Hydrogen Production and ZrO -UO Eutectic Formation.
5-14 2
y D.
Reporting Requirements for Plant Transients and Accidents..
5-18 E.
Vital Instrumentation Review.
5-23 F.
Post Accident Instrument Use.
5-31 6
Hydrogen Hazards During Severe Accidents.
6-1 A.
Introduction...
6-1 B.
Sources of Hydrogen in Light Water Reactors 6-5 C.
Hydrogen Combustion 6-10 D.
Hydrogen Phenomena at TMI-2 6-13 E.
TMI-2 Hydrogen Generation Calculation Example:
6-19 F.
Summary of Material Balances at TMI 6-24 G.
Summary of Gas Generation at TMI-2.
6-27 H.
Control of Hydrogen in ths Reactor Coolant System and the Containment 6-27 I.
TMI Lessons Learned That Can Be Applied to a Boiling Water Reactor 6-31 ii
b TABLE OF CONTENTS (Continued) e 1
f Chapter Page
.i 7
Neutron Monitoring / Core Recriticality..
7-1 A.
Introduction...
7-1 I
t B.
Incore Nuclear Instrumentation Lessons Learned at TMI 7-3 C.
Excore Nuclear Instrumentation Lessons Learned at TMI 7-19 i
i D.
Neutron Monitoring System for a BWR 7-27 E.
Neutron Monitoring System Lessons Learned at TMI Which Can Be Applied to a BWR 7-33 F.
Reactor Core Recriticality Considerations 7-52 Appendix 7A - Standby Liquid Control System 7A-1
?
8 Radiation Hazards / Radiation Monitoring.
8-1 A.
Introduction.
8-1 B.
Radiological Emergency Planning.
8-2 C.
Plant High Radiation Areas.
8-16 D.
Plant Radiation Monitoring System.
8-18 i
E.
Behavior of G - M Detectors in High Radiation Fields 8-23 F.
Behavior of Scintillation Detectors in High Radiation Fields.
8-27 G.
Expected Accuracy of Monitors at Different Locations 8-28 H.
Radiation Monitor Failure Modes...
8-29 I.
Anticipated Radiation Hazards.
8-29 J.
Radiation Hazards to Operating Personnel.
8-32 K.
Recommended Changes in Radiation Monitoring.
8-37 Appendix 8A - Radiation Monitoring Systems for the James A. FitzPatrick Nuclear Power Plant 8A-1 1
iii
l t
TABLE OF CONTENTS (Continued)
Chapter Page t
9 BWR Lessons Learned,,,,,,,,,,,,,,,,, _
9, 10 Federal Register Excerpt, October 2, 1980, Pages 65466 through 65477 b
f l
t 4
?
I l
iv
e5 00 4
i 4
4 i
CHAPTER 1 Introduction 4
I Y
e I
i l
4 i
I I
i
t.
f l
LESSON NOTES Prgo 1-1 l
LESSON OUTLINE REMARXS I
This program is intended to train operating personnel in l.tha use of installed plant systems to control or mitigate an Ijrecident in which the core is severely damaged. This training l criterion was suggested by Dr. Harold R. Denton, Director, l office of Nuclear Reactor Regulation of the U.S. Nuclear s
i 1R gulatory Commission (U.S.N.R.C.) in his letter of March 28, 1980 (Enclosure 3) for all Power Reactor Applicants and fLicznsees. It has been revised to include the suggested guide-f linss for recognizing and mitigating the consequences of severe
', ratetor core damage as suggested by the Institute of Nuclear Power Operations (INPO) on June 30, 1980.
The original program proposed by General P'hysics was de-fvelopedinresponsetoDr.HaroldR.Denton'sletterofMarch
- 28, 1980.
It was at this time that General Physics contacted j the U.S.N.R.C. requesting more information regarding Dr.
,l Denton's letter.
1 I
l After a discussion with the U.S.N.R.C. it was learned, among the lessons learned at the Three Mile Island (TMI) Nuclear Incident, that a need exists for training in var ous areas i
directly related to mitigating (or minimizing) the effects of an accident in which the reactor core has become degraded.
The intent of this program is to acquaint operations personnel in avoiding those conditions which threaten adequate core cooling.
General Physics has spent the.many months following the in-cident at TMI assisting in a variety of training programs for the operations and maintenance personnel and as a result has had a first-hand experience in learning about the various areas outlined in Dr. Denton's " Training Criteria for Mitigating Core Damage."
General Physics is also indebted to Mr. Nelson Brown and Mr. John Brummer of the Metropolitan Edison Company for their assistance in preparing these notes. Further, General Physics has also used the "Three Mile Island--A Report To The Commissioners And The Public" by Mitchell Rogovin and George T.
1 LESSON NOTES Pcq3 1-2 LESSON OUTLINE REMARKS Frampton, Jr. along with Nuclear Safety Analysis Center Report NSAC-80-1 entitled " Analysis of Three Mile Island--Unit 2 Accident," in preparing these notes.
This original program has been further revised to include the suggested guidelines as outlined by INPO on June 30, 1980 and Revision 1, January 15, 1981.
The course outline showing approximate time to be spent in each topical area is as follows:
Chapter 1 - Introduction (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
A program designed ;.o ensure that all operating personnel are trained in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
This program has been divided into 10 chapters.
The overall program will be previewed during the introduction.
t Chapter 2 - Three Mile Island Incident (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Objective:
The trainee will be intreduced to the accident at TMI-2 in order to have a better understanding of the lessons learned from the transient.
Subject Areas Presented The first 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of the TMI-2 accident.
e Basic system drawings and event graphs to help o
understand this incident.
Review of actual accident data to better understand e
its general applicability to other light water reactors.
Chapter 3 - Core Cooling Mechanics (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)
Objective:
The trainee will be able to:
Understand BWR Core Thermal Hydraulics relevant to e
ensuring adequate reactor core cooling.
l:-
LESSON NOTES pega 1-3 LESSON OUTLINE REMARKS Understands the operational effectiveness of the o
I Core Standby cooling Systems l
e Understand Natural Circulation in a BWR.
e Understand the criteria for operation and cocling j
mode selection to recover from an inadequate core i
cooling condition to mitigate reactor core damage.
Subject Areas Presentedt BWR Core Thennal-Hydraulics e
e Critical Power-and Linear Heat Generation Rate Considerations Operation of Core Standby Cooling Systems e
Effectiveness of Core Standby Cooling Systems e
e Natural Circulation in a BWR Criteria for operation and cooling mode selection e
Chapter 4 - Potential]v Damagina Ooerating Conditions (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Objective: The trainee will be able to recognize plant operating conditions in which the plant is most vulnerable to multiple failures.
Subject Areas Presented o Plant Response to Loss of Feedwater Events Plant Response to Small Break IDCA e
Chapter 5 - Recoonizing Core Damage / Critical Plant Parameters (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Objective: The trainee will be able to relate certain avail-able parameters in the plant to suspected core damage and utilize available vital instrumenta-tion to confirm pocsible damage.
I
._m.__.
y
I V
LESSON NOTES Prga 1-4 i
LESSON OUTLINE I
REMARKS Subject Areas Presented:
Fission Product Release Scenario e
Isotopic Analyses of Radionuclides e
Hydrogen Production and Zr0 eUO Eutectic Formation, e
2 2
Reporting Requirements for Plant Transients and o
Accidents Vital Parameter Instrumentation e
Monitoring of Critical Parmeters During Accident e
Conditions Chapter 6 - Hydrogen Hazards During Severe Accidents (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)
Objective: The trainee will be able to:
List the sources of hydrogen within the containment a.
b.
State the hazardous concentration ranges of ex-plosive and flammable mixtures of hydrogen and oxygen Describe the means of concentration measurement c.
and control for hydrogen and oxygen
- Sub, Areas Presented Sources of hydrogen in Containment o
Hazardous concentrations and characteristics e
of hydrogen explosives Hydrogen Phenomena at 'IMI-2 e
Hydrogen Pressure effects on BWR Containment types o
Sample BWR Hydrogen Generation Calculation e
Chapter 7 - Neutron Monitoring System / Core Recritically (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) objective:
The trainee will be able to quickly ascertain whether or not reactor core damage has occurred through the use of nuclear instrumentation.
F
i
.l.
t l
LESSON NOTES ~
Page 1-5 f
LESSON OUTLINE REMARKS l
Subject Areas Presented:
Incore Nuclear Instrumentation Systems lessons i
e I
p learned at TMI l
Excore Nuclear Instrumentation Systems lessons e
learned at TMI Neutron Monitoring System for a BWR e
Neutron Monitoring System Lessons Learned from TMI e
Standby Liquid Control System e
Chapter 8 - Radiation Hazards / Radiation Monitoring (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) gbjective: To enable the trainee tot
~
Discuss the content and implementation of the e
Radiological Emergency Plan Identify plant areas normally used that may e
beccue High Radiaiton Areas.
Discuss the precautions associated with' sampling e
primary coolant and containment atmosphere.
Describe post accident response frce radiation monitors within containment.
I Discuss radiation monitor failure modes, e
Discuss a method of determining radiation levels e
by direct measurement of detector (Radiation Monitoring System) output signal.
Subject Areas Presented:
Radiological Emergency Planning e
e Plant High Radiaiton Areas Plant Radiation Monitoring System e
Radiation Detector Behavior in High Radiation Fields o
Radiation Monitor Accuracy and Potential Failure e
Modes e Anticipated Radiation Hazards Lessons Learned frce the TMI concerning Radiation e
Hazards
LESSON NOTES Pcga 1-6 8
LESSCN OUTLINE
. REMARKS f
Chapter 9 - BWR Lessons Learned (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) i s
obiective: The trainee will understand the lessons learned q
at the 'ntI-2 Incident as they apply to a BWR.
I I
Subject Areas Covered:
A summary of the lessons learned frcan the Three Mile Island Incident which have general applica-bility to a BWR is listed.
These lessons learned have been presented in the preceeding chapters but are simply summarized here for review.
Chapter 10 - Federal Register on Mitigating Core Damage (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
Objective The trainee will become familiar with the Interim requirements related to hydrogen control and certain degraded core considera-tions.
Subject Areas Covered:
Hydrogen Management e
e High Point vents In-Plant Iodine Instrumentation e
Leakage Integrity outside containment e
Detection of Inadequate core cooling e
Final Examination (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
A Final Examination of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in length is scheduled following this course. The exam will cover each of the chspters presented during this program.
T
Nuclear Operations Manager Deputy Deputy Nuclear Nuclear Operations Operations Manager Manager Station Nuclear Technical Watch Advisors Engineers SRO Nuclear Operating Supervisors SR0 Nuclear Plant Operators R0
Class III February 1982 4
PILGRIM ABNORMAL EVENT ANALYSIS TRAINING MANUAL I
l l
Wayne Marquino l
GENERAL ELECTRIC COMPANY PROPRIETARY INFORMATION Class ill
(
~
NOTICE The information contained in this document was assembled by the GeneralElectric Company solely for educationalpurposes of General Electric Company employees and selected GeneralElectric Company customers. This document contains proprietaryinformation andis not to be reproduced or furnished to third parties, in whole or in part, withoutthe express written permission of the Nuclear Energy Business Group, General Electric Company, San Jose, California.
Neither the General Electric Company nor any of the contributors to this document make any warranty or representation (express or im-plied) with respect to the accuracy, completeness, or usefulness cithe information contained in this document. General Electric Company
(
assumes no responsibility forliability or damage which mayresult from the use of any of'the information containedin this document.
The information in this manual is intended as a guide for instructional purposes only and is not to be used as :.
substitute for the plant's normal, survetlance or emer-gency procedures.
j e
nm
d KEDO-24862D Abnormal Event Analysis Table of Contents Subject Page Number Introduction 1-1 Event Indications 2-1 Control Room Indication 2-1 Reactor Water Level Instrumentation 2-4 Threry 2-4 Effects of Process Variables on Accuracy 2-7
System Description
2-19 Application 2-26 Fu21 Performance 3-1 Haat Transfer 3-2 Machanical Performance 3-4 Pallet Clad Interaction 3-5 Matal Water Reaction 3-9 LHCR 3-11 5
MCPR 3-14 MAPLHCR 3-17 D2termining Thermal Parameters 3-18 Pressure Increase Events 4-1 Genzrator Trip-Load Reject 4-1 Turbine Trip 4-14 Loos of Vacuum 4-25 Prcosure Regulator Failure (Closed) 4-31 MSIV Closure 4-34 Modarator Temperature Decrease Events 5-1 Feedwater Controller Failure Maximum Demand 5-1 Loos of Feedwater Heater
'5-4 Pressure Regulator Failure (open) 5-14
NEDO-24862D Abnormal Event Analysis Table of Contents Subject Page Number P sitive Reactivity Insertion Events 6-1 Continuous Rod Withdrawal at Power 6-1 Continuous Pod Withdrawal in Startup 6-5 Fual Loading Errors 6-7 Control Rod Drop Accident 6-12 Core Flow Decrease Events 7-1 Trip of Two Recirculation Pumps 7-5 Flow Controller Failure (Low Flow) 7-9 Impaller Seizure 7-12 Core Flow Increase Events 8-1 Flow Controller Failure (High Flow) 8-1 Startup of Idle Pump 8-4 Loss of Shutdown Cooling 9-1 Loso of Feedwater 10-1 Introduction 10-2 Short Term Response 10-5 Long Term Response 10-11 Loc 3 of Coolant Accident 11-1 D2 sign Basis Accident 11-2 Large Steam Line Break 11-17 Intsraediate and Small Breaks 11-25 Stuck Relief Valve Short Term Response 11-37
9 O
NEDO-24862D Abnormal Event Analysis Table of Contents Subject Page Number Anticipated Transient Without Scram 12-1 Incomplete Control Rod Insertion
~
12-1 MSIV Closure ATWS 12-9 Turbine Trip ATWS 12-14 J
SORV ATWS 12-16 Loss of Feedwater ATWS 12-19 Containment Response 13-1 l
Mark I Containment Description 13 1 Hydrodynamic Loads 13-3 Sefety/Re'11ef Valve Actuation 13-12 Pressure and Temperature Response 13-18 i
i Erargency Procedure Guidelines 14-1 1
l I
4 d
4
-s s
.-.-.,__-+-.,,--n 7
- - - - - -..