ML20101E507

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Forwards Shift Experience Program for Review & Concurrence Per SER (NUREG-0876).All Personnel Will Be Trained by Last Quarter 1985.Response to 840928 Request for Exemption from Observation Training Requested
ML20101E507
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 12/18/1984
From: Danni Smith
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0876, RTR-NUREG-876 9528N, NUDOCS 8412260279
Download: ML20101E507 (75)


Text

M/ s

, ^'N; . Commonwealth Edison

./ ) one First National Plaz9, Chicago. Ilknois .

$ T ' Address Reply to: Post Offica Box 767 -

( ,/ Chicago, Illinois 60690 L

December 18, 1984 Mr.. Harold R. Denton,-Director Office of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission-Washington,- DC 20555 l

Subject:

Braidwood Station Units 1 and 2 On-Shift Operating Experience NRC-Docket Nos.150-456/457 References.(a): Byron Station Units 1 and 2, Safety Evaluation Report, NUREG-0876 Section 13.1.2.1

-(b): Administration of Operating Tests Prior to Initial Criticality (Generic Letter No.

84-10)

(c): Adequacy of On-Shift Operating Experience For Near Term Operating License Applicants (Generic. Letter No. 84-16)

(d): J. G. Marshall letter to H. R. Denton dated September 28, 1984

Dear Mr. Denton:

References (a), (b) and (c) present requirements for ensuring that shift operators have sufficient operating experience prior to initial criticality. The enclosure is Braidwood Station's Shift Experience Program. We request that you review the program and indicate to us your concurrence that it fulfills those requirements.

The Six Month Program was begun in April, 1984 when two people.were sent to Zion Station. Two more began in October 1984.

These will be followed at regular intervals until all required SRO's have completed the program.

The eight week program began October 22, 1984 with eight people at Zion. The next class of eight will convene in January,

.1985. This will be followed at approximately eight week intervals until all candidates have completed this program. This schedule permits all personnel to be trained by the last Quarter of 1985.

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. In Reference (d), we requested an exemption from Observation Training for :a number of operators. We asked a reply by December 1,.1984-to permit scheduling of the January 1985 session.

The lack or delaylof these exemptions will cause significant unnecessary expense and. inconvenience. Therefore, your prompt reply on1this matter is requested.

Please direct any questions you may have concerning these matters to this. office.

One _(1) signed original and fif teen (15) copies of this letter are provided for your use. Because of its volume, three

. copies of.the enclosure are included.

Verftrulyyjurs,

/

c' O. H. Smi h Nuclear Licensing Administrator Enclosure

^

cc:L Joseph I. McMillen - RIII Don H. Beckham - NRR, Operator

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Licensing Branch i

9528N,

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m y '- s p .i f s B' r a i d w o o d' Station's Shift" Experience Procram

-In order:to accommodate several requirements with regard.to shift < experience-levels and observation. training at an operating-

reactor,LBraidwood Station has designed'a-program that will~ satisfy teach. requirement.

. ?Specifically,'the Byron Station Safety. Evaluation. Report (13.1.2.1),xGeneric Letter.No. 84-10 and Generic Letter No. 84-16

(with enclosure) detail specific experience and/or training

~

requirements for shift personnel and license ~ candidates. Coupling

'the. requirements contained in these documents with ANS 3.1, 1981, the programs to accomplish the needed training consist of the

.following:

I. 'Six months of experience for one Senior Reactor

' Operator (SRO) per shift at an operating Westinghouse plant (six weeks of which shall be 20% power);

II. Six-weeks of' experience for another SRO per shift at an operating Westinghouse plant.( 20% power);

III. Eight weeks of observation training for~all license candidates that don't have extensive actual operating

+ experience at,a comparable facility or are not specifically' exempted by the NRC. (Currently we have an eight week simulator training phase and to achieve e

four months of combined simulator and observation

. training, an eight week length-for the observation training program is necessitated.)

Qualification procedures.which have been developed to address the above programs are enclosed as attachments 1 and 2 and are titled:

, 1. ;Braidwood Nuclear Station. Senior Reactor Operator-Six Month Hot Participation Procedure

- 2. .Braidwood Nuclear Station Senior Reactor Operator Eight

' Week Hot Participation Procedure

.The Braidwood Nuclear Station Senior Reactor Operator Six.

Month Hot Participation Program will be completed by those SR0s who

-will'ba required to fulfill the six month on-shift experience requirements.

.The Braidwood Nuclear Station Senior Reactor Operator Eight Week-Hot Participation Program will be completed by the remainder of the Braidwood Senior Reactor Operator candidates and Reactor Operator' candidates who are required to do so. By doing so, the six week on-shift experience requirement will be met as well as the requirement for on-shift observation training for cold license candidates.

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i t-The qualification procedures were compiled on the. basis of INPO Guidelines83-022,-Zion Station's 3 month 6JT program, the.

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Commonwealth Edison -Shif t Control Room Engineer (SCRE) task analysis:  !

and informal, review of Zion Station's administrative procedures ~to determine shift supervisor required actions.

?SubsequentLto the development of att'achments 1 and 2, it was determined that an observation training program must be conducted for all appropriate personnel. .To that end, a vendor will

~

'be'contractedLto provide on-shift training at Zion Station for 8-weeks.- Classes will consist of 3 or 4 students.per instructor and will spend at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per-day in the control room, covering all' shifts on a rotating basis. Attachment 3 is an outline of that

-eight week schedule. Attachment 2 served as.the basis for the development of attachment 3.

Observation training will thus serve to satisfy,the requirement of six weeks hot experience for an SRO on shift. Those SR0s who are required to spend six months at an operating plant will attend observation training and then spend an additional four months at the operating plant, completing items in attachment 1 that were not covered during observation training.

The Braidwood. Station'NRC Senior Resident Inspector has been appraised of our intention in these matters and his concurrence in our actions has been sought and obtained. It is requested that approval of our methods of satisfying the requirements discussed above be granted by your organization.

9528N J

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ATTACHMENT.-l J ' +- 'BRAIDWOOD NUCLEAR STATION

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~ DL ' SENIOR REACTOR' OPERATOR

-SIX MONTH.

- ~ HOT-PARTICIPATION' PROCEDURE

, ~ .

i "A. STATEMENT-0F APPLICABILITY '

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- .The' purpose of-this procedure is:to describe the steps'necessary e~ ,

~

. for the successful completion.of the Braidwood Nuclear Station -

Senior Repctor' Operator Six Month' Hot Participation Program.

M:n "

When"this program has been completed, the participant will-have t?-  : gained 6 months.of Hot Participation. Experience at a plant a ji  :-similar to Braidwood. 'During this period,-the SRO trainee will CMi be involved in the review and discussion: leading to decisions 2: - relative'to operating a nuclear power plant.

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m 'This ' program includes the following requirements:- ,

L 1. 16 months Hot Participation at Zion Station.

2. 6 weeks operation above 20% rower.

3.. -

Startup from subcritical'to 20% power.

. 4. 'Chutdown-from 20% power to, cold shutdown.

B.-' REFERENCES
1. J. H. Miller'.s presentation to the NRC Commissioners,

" Industry Evaluation of Operating Shift Experience Requirements,'.' February 24,'1984.

2. INPO Guideline 83-022, June 1983, PWR' Control Room Operator,

' Senior Control Roos Operator, and Shif t Supervisor Qualification.

3. ' NucleariStation Directive, A09, Conduct of Operations.

4.' Zion Administrative Procedure 2-52-1, Station Training

.p Administrative Program.

C. lPREREQULSITES f4- Individuals shall successfully complete an SRO Certification Program on a similar-plant before beginning the Hot

' Participation Program.

D. , MAIN BODY- '

M ;- > ;

1. Complete the SRO Hot Participation Training Resume c (Attachment'A) as follows:

. a. The trainee, or.a member of the Braidwood Station Training Department shall complete Section A (General Information) as follows:

1) Name: Fill in name of trainee.

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-2) Ceco Service Date: ~ Fill in trainee's Company

, Service Date,

b. The trainee, or a member of tae Braidwood Station .

Training. Department shall complete Section B (Education) as.follows:

' 1) List the formal training completed by the trainee at' accredited colleges and/or universities.

Indicate Major / Minor, date of graduation, and the

-school which issued the diploma.

c. -A member of.the Braidwood Station Training Department a shall complete Section C (Commonwealth Edison Training Courses) as follows:
1) Senior Reactor Operator' Training Program:

a) Indicate location and date of certification.

- b)' If licensed, indicate Unit on which licensed and date of license.

2) Other Technical Courses:

P. a) Indicate course name, location and date of completion.

3); Ceco Management Courses:

a). Indicate course name, and date of completion.

2. The trainee shouhd read all required reading items listed on '

the'SRO Hot Participation Required Reading Form (Attachment B) before going on' shift at Zion.

-3. After completion of each. required reading item, the trainee shall document that the required reading is complete by signing his/her name in the space provided on Attachment B.

4. The Job Qualification Checklists (Attachments C, D, and E) contain.those taska which shall be completed by the trainee while on shift at Zion Station.

a.. General Instruction;

., Each; task description is followed by a (P) or an (F).

Those tasks descriptions followed by a (P) must be actually performed or observed by the trainee while on shift. The trainee is further required to demonstrate n ,,

adequate knowledge relative to the performance of the  ;

J evolution. The task descriptions followed by an (F),

may be' fulfilled by demonstrating adequate familiarity

through simulation or discussion with designated on shift personnel. The preferred method of fulfilling a 2

1825P 0288A-

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, .e task is'by performance (P). The option of demonstrating familiarity (F) should be used only when a perform (P) is not possible or practical. -

.The Job Qualification Checklist Addendum Log will'be

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^- completed by the trainee listing those activities which are not specifically listed on the Job qualification t checklist.

'b. Checklist Instructions >

'There are 3 SRO Hot Participation Job Qualification Checklists:

t

1) In plant SRO Hot Participation Job Oualificall2R Checklist (Attachment C).

HQII The in-plant SRO Hot Participation portion may require up to one month'of full-time effort.

This portion of the training program is designed to

, acquaint the trainee with the tasks of non-licensed operators (E0/EA's) outside the control room.

During this period the trainee should work closely

. with-the Shift Engineer / Shift Foreman and, under  ;

his cognizance, should. accompany non-licensed '

operators in their daily routines to become i f amiliar with- the various aspects of their job functions. .The trainee should document hic participation in as many of the following

. evolutions as possible:

. local control and operation of equipment

. surveillance testing of equipment

. . system valve and breaker lineups

. shutdown /startup/ shifting of pumps,' filters, heat exchangers, ion exchangers and other .

components and systems.

p.

. monitoring of' system parameters and equipment conditions during operations.

. -procedures and practicer used for removing equipment from service for maintenance and, returning equipment to service.

? ', .

!,  :. procedures and practices used to minimize

"/' radiation exposure and control contamination.

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._ .. . ._ _ . _ . . , _ . _ _ _ _ _ . . . _ _ . . _ . . ~ . _ . _ _ . , _ . _ . , . . . _ . . _ . . . _ - _ _ . _ _ _ . _ . . . _ . . _ . _ _ _ . _ _ _

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e The trainee should discuss those evolutions observed with the Shift Engineer / Shift Foreman who will " sign-off" each item. The trainee should be able to fulfill the following objectives for any evolution observed:

. How the evolution affects unit availability.

. Personnel safety precautions which should be observed while performing the evolution.

. How the evolution impacts upon Reactor Safety.

The trainee is to complete all items on the Job Qualification checklist'(Attachment C) and, to document all additional items on the Job Qualification Checklist Addendum Log.

2) Reactor Operator Hot Participation Job Qualification Checklist:

EQT.E The Reactor Operator Hot Participation portion requires approximately two months of full-time effort.

During this portion of the program, the t'eainee will complete the Reactor Hot Participation Operator Qualification Checklist. Items in which the trainee participates that are not listed on the Qualification Checklist should.be. documented on the Job Qualification Checklist Addendum Log.

3) Shift Supervisor Hot Participation Job Oualification Checklist: The objective of this checklist is to directly' involve the trainee in the review and discussion leading to decisions relative to. operating a nuclear power plant. The trainee is to complete all items on the Shift Supervisor Hot Participation Job Qualification Checklist and to document all additional items on the Job Qualification Checklist Addendum Log.
5. The Braidwood Station Training Supervisor and the Ass't Superintendent of Operations shall sign the Braidwood Nuclear Station Hot Participation Experience Record (Attachment F) after verifying the trainee has successfully completed the Hot Participation Program requirements.

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-ce Attachment A

.SRO Hot Participation Training Resume A. General Information

1. Name:'

'2. Ceco Service Date:

-B. Education Maior/ Minor Fields gnig School

1. B.S.
2. M.S. __
3. PhD.
4. Other-

- C. Comunonwealth Edison Training Programs

-1. Senior Reactor

' Operator Training Program Location /Date Unit on Which of Certification Licensed /Date of License r 2. 'Other Technical Courses Title of Promram Location Date of Conoletion

+

amuses

  • 1 .

1 1

1825P 0288A

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I Attachment A (Con't) 3.. Ceco Management Courses A. Cosununication and Motivation (SAI)

Date d

B. ' Rational Situation Management (KT)

Date C. Others.

Date i Date Date 9

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Attachment B

- SRO' Hot Participation Required Reading

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1 Thelt rainee shall read'the following documents:

Trainee Signature /Date A. ZION ADMINISTRA*IVE PROCEDURES

1. ZAP 0' Conduct of Operation
2. . ZAP 01 Admitting and Control of LWestinghouse Trainees
3. -ZAP 02- Station Fire Fighting Forces
4. ZAP 02A Fire Protection Surveillance 4

Procedure-5.. ZAP'02B Control of Flammable and Combustible Liquids

6. ZAP 0-3 Press Releases
7. ZAP 1-51-1 Station Organization
8. ZAP 2-52-1~ Station Training Program 9 .- ZAP 2-52-3 Operating Experience Feedback

-s- 10. ZAP 2-54-1 On-Site' Station' Review

'11. ZAP 2-54-2 ~ Plant Nuclear Safety Review Committee

12. ZAP 2-54-3 Emergency Operating Procedure Review Committee
13. ZAP 3-51-1 Origination and Routing of Work Requests
14. ZAP 3-51-18 Plant Modification Program
15. ZAP 2-51-2 Non-Production Plant Work Orders
16. ZAP 3-51-4 Procedure Governing the Use of Temporary Jusper Cables, the Lifting of~ Terminated Wires, The Bypassing of Alarms, or The Installation _Of Mechanical Blocks or Bypasses 1

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Attachment B (Con't)

Trainee Sinnature/Date s

17. ZAP 3-51-4B Procedure for Non-Routine Valve Line-Ups

'18. ZAP 3-51-5 Field Change Requests

19. ZAP 3-51-6 Evaluation of Component Parts J20. ZAP 3-51-7 Annunciator Alarm Review
21. ZAP 3-52-1 Change of Instrument Setpoint/ Scaling
22. ZAP.3-52-2 OAD Periodic Relay. Testing and Instrument Calibration Procedure Reportability to Zion Station
23. ZAP 3-52-3 Zion Scaling Procedure
24. ZAP 3-52-4 Change of Protective Relay Setpoint
25. ZAP 4-51-1 Establishing Quality Requirements for Requests.for Purchase and Requisition Cards
26. ZAP 5-51-2 Guidelines for an ALARA Review
27. ZAP 5-51 Procedure Periodic; Review
28. ZAP:5-51-4 Procedure Control and Approval 29.-- ZAP 5-51-5 Procedure Content and Format

-30. ZAP.5-51-6 Confined Space Entry

31. ZAP 5-51-7 Containment Access Control
32. ZAP 5-51-8 Access control to the Control Room
33. ZAP 5-51-9 Liquid Waste Management

'34, 1UU? 5-51-15 High Radiation Area Access Control

35. ZAP 5-51-16. Reactor Cavity (Incore Shaft)

Access Cortrol

36. ZAP 5-51-17 Entry and Exit to Auxiliary Electrical Room 2

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Attachment B (Con't)

-Trainee Sianature/Date

37. ZAP 5-51-18 ~ Personnel Termination Procedure

.38. ZAP 5-51-19 Personnel Qualifications

39. ZAP.6-52 . Zion Station Drawing Change-Request Program -

'40. ZAP 6-52-2 Zion, Station Document Control

41. ZAP 6-52-3 Zion Station Mail Receipt Control

. .42. ZAP 6-52-4 . Zion Station General' Office Master. File Control-

43. ZAP 10-52-1 ' Inspection Plan for Operations
44. ZAP.10-52-2 Operating Log Books
45. ZAP 10-52-3 Shift Manning,' Relief, and Turnover-
46. ZAP-10-52-4 Leak Reduction and Control Program

-47. ZAP 10-52-5 Housekeeping

48. ZAP 10-52-9 Station Lubrication Report
49. ZAP 10-52-10 Vibration Monitoring / Analysis Program
50. ZAP 10-53-1 _ Inspection vlan - Surveillance
51. ZAP 13-51-1 Responsibilities, Movements, and Reporting Related to Safeguarding Nuclear Fuel ,
52. ZAP 13-52-1 Receiving, Handling, Storage, Packaging, and Shipping of Items in
  • the Storeroom z
53. luu? 13-52-2 ~ Preventive Maintenance & Limited

' Shelf Life of Safety-Related and ,

ASME Code Items

54. 2AP 13-52-31 Receiving and Storing Chemicals
55. ZAP 13-52-4 Handling, Storage and Control of Welding Materials 8

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Attachment B (Con't)

Trainee Sinnature'/Date

.56., ZAP 13-52-8 Preparation'and Sh'ipment of Radioactive

. Material

57. ZAP 14-51-2 Inspection. Test and Operating Status Tagging of-Equipment
58. ZAP 16-51-1 Zion Station Action Item Record Program-B. ZION STATION RADIATION PROCEDURES
11. ~RP 1190-1 Zion radiation protection general procedures
2. EW'1210-3 Personnel n.utron monitoring
3. RP 1210-4 Dose calculations, time limits and timekeeping
4. 'RP 1230-1 Lost fila badge. procedure

~ 5. RP 1240 Survey instrument calibration-Series (1-22) and use

6. RP 1280-1 Radiation surveys
7. RP 1280-2 Radiation level arca surveys
8. RP 1310 Use of respiratory. protective Series (1-12) equipment
9. RP 1320-1 Personnel injury in. controlled area
10. RP 1330-1 Working in radioiodine & tritium atmosphere
'11. RP 1340-1 Personnel contamination procedure.

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12. RP-1350-8 Radiation monitor out of service and return to service procedure 1 i

r 13. RP'1350-20-23 Testing of breathing & working

(* environments __

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. Attachment B (Con't) l Trainee Sinnature/Date

14. RP_1350-37 High Radiation Monitor Alarm 1
15. RP 1360-4' Testing of breathing & working environments 16.:RP 1410-1 Protective clothing
17. RP 1410-2 Washing Protective clothing
18. RP 1430-1 Unconditional release of materials 19.-RP 1470 Area and material decon
20. RP 1470-4 Personnel decontamination
21. RP 1480-2 Contamination surveys *
22. RP 1490-1 Contamination control points
23. RP 1520-1&2~ Radioactive waste shipments
24. RP 1610-5 Containment entry procedure 25.'RP 1610-6 Gas leaks in Aux. Building or Containment 1!6. RP 1610-8 Reactor coolant leak detection 27'. RP 1740-1 Monitoring of high activity gas release during an accident
28. RP 1740-2 Setting up the-emergency command center 29.'RRP 1740-5 Emergency equipment storage and location
30. RP 1740-6 Radioactive liquid spills 5

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Attachment B (Con't)

- Trainee Sinnature/Date'

,C. 10CFR20 STANDARDS FOR PROTECTION AGAINST RADIATION

, D. 10CFR50 LICENSING OF PRODUCTION AND UTILIZATION FACILITIES With Emphasis of Appendicies A,B,

> E H.I,J.K and R 1R. 10CFR55 OPERATOR LICENSES Paragrapahs 55.1 thru 55.6, 55.20 thru 55.23, 55.30 thru 55.50 F. '10CFR100 REACTOR SITE CRITERIA G. . ZION FINAL SAFETY SMALYSIS REPORT (FSAR)

~ 1. Chapter 9 - Auxiliary and Emergency Systems 1.11 General design criteria 9.1 1.2 CVCS design' bases 9.2.1-1.3 Component cooling system evaluation 9.3.3.3 1.4 Spent Fuel pit cooling system 9.5'

'1.5 Reactor components and fuel handling

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sys. 9.7 1.6 Plant rentilation 9.10.

[-

2.' Chapter 11 - Radioactive wastes and radiation protection i-l-

3. Chapter 12 - Conduct of operation l 3.1 Precautionary planning section 12.3 l'~ 3.2 Records section 12.4 h 3.3~ Review and-audit section 12.5 4.- Chapter 14 - Safety analysis
5. Volumes.VII and VIII - Review the questions

[ and answers between the NRC and CWE i

l. 6

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Attachment B (Con't)

-Trainee Signature /Date H. ZION UNIT'1 STARTUP TEST REPORT I. GENERATING STATION EMERGENCY PLAN

1. Generic GSEP
2. EPIFs J. ZION STATION CHEMISTRY PROCEDURES-
1. ZCP-200 Primary System Sampling Procedure
2. ZCP-300 Zion Station Liquid Releases
3. ZCP-304 Containment Venting & Purging Analysis _
4. ~ZCP-306 Continuous Gaseous Release Calculations K. PLANT MODIFICATIONS
1. Review recent modifications and setpoint changes.

L. OPERATING EXPERIENCE REPORTS (OPEX)

1. - Read major operating experience ceports from other plants.
2. Read major and recent (last year) Zion LER's.

M. ZION SETPOINT STUDY WCAP 7922 N. INSTRUMENT FAILURE RESPONSE MANUAL

1. ' Review plant response to instrument failures.

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0-Job Oualification Checklist Addendem Loa

. Item

Description:

(P) or (F)

SE/2F/SCRE Sign /Date

Ltem

Description:

(P) or (F)

SE/SF/SCRE Sign /Date Item

Description:

(P) or (F)

SE/SF/SCRE Sign /Date

Item

Description:

(P) or-(F)

SE/SF/SCRE Sign /Date

\

. Item

Description:

(P) or (F)

SE/SF/SCRE Sign /Date

-Item

Description:

(P) or (F) t' SE/SF/SCRE Sign /Date b

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~i Attachsent C--

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Rev. 1-

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.IM PLANT HOT PARTICIPATION JOB QUALIFICATION CHECKLIST

1. : Participate in the .inste.11stion or removal of temporary jumper cables, the g lifting of terminated wires, the bypassing of alarms, or the installation-

!' of mechanical' blocks or bypasses. (ZAP 3-51-4)

[q' (P)'or (F) /

SF- Date h L2. Participate in a fire drill as a Fire Brigade Member- (ZAP-02) n (P)-or (F) /

SF Date F:sil 3. Discuss ~ the procedure for or perform an entry into a high rarliation area (ZAP 5-51-15).

(Performance Optional) (P) or (F) /

SF Date

4. ' Participate in an auxiliary electrical room entry (ZAP 5-51-17).

(P) /

SF Date

5. Perform the-Equipment Attendant rounds under his cognizance. (ZAP

'10-52-1).

(P) Dayshift (T 2) /

SF Date

-(P) Afternoon (TI) /

SF Date (P) Mids (Aux Blds) /

, SF Date

6. Participate in a shift turnover (ZAP 10-52-3).

' EA (P) /

SF Date EO (P) /

SF Date

7. Participate in the lubrication of equipment (ZAP 10-52-9).

(P) /

l SF Date 1

1825P O288A L:

Attachment C (Con't)

Rev. 1 b

8. Take vibration readings on category I equipment. (ZAP 10-52-10).

(P) /

SF Date

9. Participate in the inspection, tagging out, testing and return to  ;

. service of plant equipment. (ZAP 14-51-2)- l EA (P) /

SF -Date EO (P) /

1 SF Date 10; Initiate a work request. (ZAP 3-51-1)-

(P) /

SF Date

11. Stand an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift at the Radwaste Panel.

(P) /

SF Date

12. Discuss refueling operations and tools with Fuel Handling Foreman.

/

Fuel Handling Foreman Date

13. Verify / Change lineup of Waste Gas System for release or use as Cover gas.

(P) or (F) /

- Radwaste Foreman Date 2

1825P-0288A

Attachment D Rev. 1 REACTOR OPERATOR HOT PARTICIPATION JOB QUALIFICATION CHECKLIST NOTE The trainee shall participate in the control room during the following evolutions.

1. 6 weeks operation above 20% Reactor Power.

/

SF Date

2. - A. refueling outage or a plant startup fcilowing an outage.

/

SF Date NOTE During this period, the trainee should perform or demonstrate. familiarity with the following duties of a control room operator under the direct supervision and guidance of a qualified control room operator.

.3. Reactor Startup:

a) Suberitical to Critical.

(P) /

NSO/SF Date b) Critical to 2% power.

(P) /

NSO/SF Date c) Reactor power increase from 2% power to 20% power.

(P) /

NSO/SF Date

4. Reactor Shutdown:

E a) Reactor power decrease from 20% power to Hot Standby (mode 3).

(P) /

NSO/SF Date b) Hot Standby to Mode 4 Hot Shutdown.

(P) /

NSO/SF Date c) Mode 4 Hot Shutdown to Mode 5 Cold Shutdown.

(P) /

NSO/SF Date 1

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Attachment D (Con't)

Rev. 1

.5.- Manual control.of, steam generator' levels during plant ' start-up and/or shutdown.

(P) '/

NSO/SF Date

6. Boration during power. operation.

(P) /

NSO/SF Date 7.t Dilution'during power' operation.

(P) /

NSO/SF Date 8.. Reactor power changes of 10% or greater when rod control is in manual.

D (P) /

NSO/SF Date 9 .- -Operation'of turbine controls during turbine start-up.

(P) /

NSO/SF Date

10. Synchronization of the main generator with the grid.

-(P) /

NSO/SF Date

11. Control room operations during 3 shifts of refueling.

(P) /

NSO/SF Date.

~12. Residual heat' removal system startup and shutdown.

(P) /

- NSO/SF Date

13. Control of primary pressure u'nder solid water conditions.

(P) /

NSO/SF Date 2

1825P 0288A

7-Attachment D (Con't)

Rev. I 14 . - Incore instrumentation-system operation.

(P) /

NSO/SF Date

-e 15. Large change in Reactor Power.

(P) /

NSO/SF Date

16. Large rate of change in Reactor Power (Rate of change greater than required for normal operatior.s i.e. abnormal condition)

--(optional).

(P) /

NSO/SF Date

17. Participate in a fire drill as a Control Room Operator.

. (ZAP -02)

- - (P) or (F) /

NSO/SF Date

~

18. Discuss the-NSO responsibilities in the Station Organization.

(ZAP.1-51-1)

/

NSO/SF Date

19. Originate a Work Request (ZAP 3-51-1)
  • . /

NSO/SF Date

' :20. Discuss the actions required by the KSO during a containment entry (ZAP 5-51-7)

/

NSO/SF Date 3

1825P 0288A

y--,,

Attachment D.(Con't)

Rev. 1

21. . Maintain unit operators logbook-for entire shift. (ZAP

'10-52-2)'

(P) Day /

NSO/SF Date' (P) Afternoon '/

NSO/SF Date (P) Mids /

NSO/SF Date

22. MEintain center desk operators logbook (ZAP 10-52-2)

(P) Day /

NSO/SF Date (P) Afternoon /

NSO/SF Date (P) Mids /

NSO/SF Date

23. ' Participate in a shift turnover (ZAP 10-52-3)

(P) /

Center Desk Date (P) /

Unit Operator Date

25. Calculate an estimated critical condition.

(P) or (F) /-

NSO/SF Date-

25. Perform or_ assist with the following surveillance tests:

1-PT-0 Unit Shift Surveillance Appx B/B-1. Shutdown Margin Verification (Modas 2, 3, 4, 5, &

6).

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date 4

1825P 0288A t

p.:

k' _

Attachment D'(Con't)

>: Rev. 1

Appx D Operating Surveillance Checksheet ,

-(P) Shift 1

/

NSO/SF Date-(P) Shift 2 / ,

NSO/SF Date (P) Shift 3 /

NSO/SF Date

~Appx E Operating Surveillance.

(P) Shift 1 /

NSO/SF

~

Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx F, Operating Surveillance Checksheet (Modes 3 & 4)

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF -Date Appx C, Operating Surveillance checksheet (Modes 1 & 2)

~

(P) Shift 1 /

NSO/SF Date

<(P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date 5

1825P 0288A

r - __

.- - p.

.J-=

Attachment D'(Con't)

. Rev. 1-j .

Appx H. Control Ro,d Alignment Checksheet (Modes 1 & 2)

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx I, Excore Detector Outputs and Quadrant Power Tilt Ratio

'(Mode 1 > 50%).

(P)' Shift 1 /'

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx J-1. Normal and Reserve Off Site AC Power Availability.

(P) Shift 3 /

NSO/SF Date Appx J-2, Onsite AC & DC Power Availability.

(P) Shift 3 /

NSO/SF Date Appx K, Station Battery Daily Record (P) Shift 2 /

NSO/SF Date Appx L, Reactor Protection Channel check & E.S.S.

Instrumentation Channel check (Modes 1, 2, 3, & 4).

(P) Shift 1. /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SP Date 6 l l

1825P~

0288A

'_O'.

Attachment-D (Con't)

Rev. 1

. .e ,

Appx M, Calormetric j

'(P) Shift 2 / ,

NSO/SF Date Appx N, Radiation Monitor Check (P) Shift 1 /

NSO/SF Date Appx P.-Power History Log (P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date PT-1 Rod Cluster Exercise (P) or (F) /

NSO/SF Date PT-2A Safety Injection Pump Tests (P) or (F) /

NSO/SF Date

-PT-2C ECCS Valve Interlock Test (P) or (F) /

NSO/SF Date PT-2E Spurious Valve Actuation Group De-energization Check (P) or (F) /

NSO/SF Date PT-2I' Centrifugal Chg. Pump Tests (P) or (F) /

NSO/SF Date PT-2J RHR Pump Tests (P) or (F) /

NSO/SF Date PT-2R . Penetration Press. Compressor Test (P) or (F) /

NSO/SF Date 7

1825P 0288A

. - . . . _ . . - . - _ - - _ - - , - . . - _ . . _ - _ - - - . - - _ _ ~ - . , - - _ . . . - - . . . ~ , - , . . ~ . _ , . - _ - .

q l

.s . _, ;

. v ':.

Attaciunent D (Con't) .

rRev. 1.

PT-3B ' Isolation Valve seal Water-(P) or (F) /

'~

NSO/SF Date PT-3C1-Penetration Pressurisation Tests (P) or.(F) -/'

NSO/SF Date PT-3D 'MSIV Test -

(P) or_(F) /-

-NSO/SF Date ,

.PT-4A 'N.I.S. Functional Test S.R.

(P) or (F) /

NSO/SF Date PT-4B N.I.S. Functional Test I.R.

(P) or-(F) /

NSO/SF. 'Date PT Reactor Protection Logic

~(P).or (F) /

NSO/SF Date PT-5A Reactor Protection Logic (P) or (F) /

NSO/SF Date

.PT-5B . Reactor-Protection Logic (P) or (F) /

NSO/SF Date

PT-6, Containment Spray Pump Test.

(P) or (F) /

NSO/SF Date PT-7 Aux. Feedwater Pump Test (P) or (F) /

l} -

NSO/SF .Date ~

PT-9 Service Water Valve Tests (P) or (F)

~

/ ,

MSO/SF Date PT-10 Safeguards ~Actuations Tests (P)'or (F) /

NSO/SF Date PT-10A Safeguards Logic Test (P) or (F) /

NSO/SF Date

, , PT-10B Safeguards Logic Test (P) or (F) /

~

NSO/SF Date r

8 1825P 0288A-

f

~

.. -l Attachment D'(Con't) s Rev. 1 1

?T-10C Safeguards Logic Test (C.S.D. only).

(P) or (F) /

NSO/SF Date PT-11. Diesel Generator-Load Test-Locally Control Room (P) or (F) ~/

NSO/SF Date PT-12 Boric Acid Heat Trace Test (P) or (F) /

NSO/SF Date PT-14 Inoperable-Equipment Sury.. Tests-(P) or (F) /

NSO/SF Date PT-15 Ex Containment Fan Cooler Tests (P) or (F) /

NSO/SF Date PT-16 Boric' Acid Transfer Pump Tests (P) or (F) /

NSO/SF Date PT-17 Gas Decay Tank & Containment Purge Auto Valve Tests (P)or (F) /

NSO/SF. Date .

PT-20 Centrifugal Charging System Valve Tests (P) or (F) /

NSO/SF Date PT-21 R.C.S. Leak Rate Test, Manually (P) or (F) /

NSO/SF Date PT-24 Unit to System Aux. Transformer Auto Feed Transfer (P) or (F)

/

NSO/SF 'Date PT-101 Turbine Protective Device Tests

. (P) or (F) /

" NSO/SF Date

PT-102 Intercept &' Reheat Stop Valve Test (P) Or (F) /

NSO/SF Date

'PT-103 Turbine Stop & Gov. Valve Tests (P) or (F) /

NSO/SF Date PT-105 Jumper /Lif ted Lead Verification (P) or (F) /

NSO/SF Date PT-106 Key Audit (P) or (F) /

NSO/SF Date PT-201 Fire Protection Pump Tests (P) or (F) / ,

NSO/SF Date 9

1825P 0288A.

.- . ._ . _ , _ . ~ . . _ . . _ _ . _ , _ _ . . - _ _ _ _ , . _ _ - _ _ _ . . _ . . - _ , _ . . . - . . _ . _ _ , - . . . _ . . - _ _ _ .

r - _ _ _ . _

L . '

^ :,[

4 Attachment D (Con't)

Rev. 1

26. l Manus 11y control Steam Generator. level while operation at > 80% power. '

(P) or -(F) /

NSO/SF Date

-27. Shift steam Generator _ Level Control system from manual to automatic

- during start-up.

(P) or (F) /

NSO/SF. Date ,

28. shift Steam Generator Level control system from manual to automatic while operation.at > 80% power.

(P) or (F) /

-NSO/SF Date

'29. Control Auxiliary Feedwater flow to Steam Generator during start-up, ir . shutdown or trip recovery.

(P) or (F) /

NSO/SF Date 30.. . Adjust the negavar loading on the main generator using appropriate

' curves.,

,, -(P) or (F) /

,, NSO/SF Date Operate the P-2500 computer console:

! '- 31.

1 Digital ~ Display (P) or (F) /

NSO/SF Date Add / Remove from Scan (P) or (F) /

NSO/SF Date Digital Trend (P) or (F) /

l NSO/3F Date L ,7 Analog Trend -(P) or (F) /

h , ,

NSO/SF Date p 32. Adjust Accumulator level:

s-

[>._

U a). Raise level with RCS pressure > 1600 psi.

y - (P) or (F) /

NSO/SF Date 3

b) Raise level with RCS pressure < 1600 psi.

! (P) or (F) /

NSO/SF Date

{ 33. -Adjust Accumulator nitrogen pressure.

[ (P) or (F)- /

p .

NSO/SF Date

[ 34. Control & I during steady state conditions.

[ .

(P) or (F) /

NSO/SF Date

[

I b

t 10 -

1825P. ,

L 0288A

.; _ -_ , _ . _ _ _ . . . . _ _ . _ _ _ . _ . ~ . _ . - _

s Attachment D (Con't).

Roy. - l' 35.
' Discuss control'of A I following a power ch'ange and the procedure for dampening Axial Ienon 0xcillations.

_(P) or (F). /

NSO/SF- Date

. 36. Complete a Containment Purge & Vent form.

.(P) or (F) /

NSO/SF Date 37.- _ Complete a Liquid Radweste Discharge form.

(P) or (F) /

~

NSO/SF Date.

38. - : Demonstrate familiarity.with curves and graphs associated with-the Radiation Monitor system.

(P) or (F) /

NSO/SF Date

39. Source check.and operate the following radiation detection instruments:

R0-1 Rad. Owl- (P) /

Date NSO/SF

~PRM-4 Alpha Survey (P) /

l NSO/SF Date PRN-4 Neutron Survey (P) /

NSO/SF Date Teletector Hi-Range Beta / Gamma (P) /

NSO/SF. Date

~40. . Discuss the significance of changes in VCT and/or PRT level (s) i when operating at steady state.

/-

J6 NSO/SF Date

41. Demonstrate familiarity with the location, operation and/or function of the following Control Room equipment:

On-Site Communications Equipment (P) or (F) /

NSO/SF Date Off-Site Comununications Equipment (P) or (F) /

  • NSO/SF Date

' Emergency Equipment (P) or (F) /

NSO/SF Date Fire & Evacuation Alarms (P) or (F) /

NSO/SF Date l Emergency Keys (P) or (F) /

NSO/SF Date Loose Parts Monitor (P) or (F) /

NSO/SF Date I

11 1825P 0288A

'T. .

' Attachment D (Con't) '

Rev. 1

42. Shift source of Aux. Steam from unit to unit or to Aux. Boiler. .

.(P) or (F) /

NSO/SF Date

43. Discuss your responsibilities under the GSEP.

/

NSO/SF Date

-44. Operate:345 KV OCB's'from the General Services panel and coordinate operations with LD.

(P) or (F) /

NSO/SF Date s.

l 12 1825P 0288A

J H(,-L * > .j l Attachment E-Rev. 1 y

9, 4

, SHIFT SUPERVISOR HOT PARTICIPATION .i I

' JOB QUALIFICATION CHECKLIST

1.  : Discuss the responsibilities of the S.E. in the station organization (ZAP 1-51-1).

7

-SE Date

.2. Discuss the responsibilities'of the S.F. in the station J, organization.(ZAP-1-51-1).

/

SF Date 3 .~ ~ Discuss the responsibilities of the SCRE/STA in the station ,

organization (ZAP 1-51-1).

/

SCRE Date

4. l Discuss the requirements for the admission and control of Westinghouse-trainees in the plant (ZAP-01).

/

SE Date

'- 5. Participate in a fire drill as Fire Chief (ZAP 02)

(P) or (F) /

SF Date N 6 .' ' . Process a Work Request (ZAP 3-51-1).

(P) or (F)

/

SE/SF Date

7. Implement the procedure governing the use of temporary jumper cables, the lifting of terminated wires, the bypassing of alarms, or the installation of mechanical blocks or bypasses (ZAP:3-51-4)

(P) or (F) /-

SE/SF Date

8. Prepace's non-routine valvo lineup. (ZAP 3-51-48)

(P) or (F) /

< SE/SF Date 4 1 1825P

.0288A

_ . - -.. - _ _ -. . ~ _ - _ . . . - _ . - . . . . . . , - _ . . _ _ _ - - _ _ _ - . _ _ . . . . _ _ _ . , _ . . .

I i

'1 Attachment E-(Con't) l Rev. 1 o 9. Perform the Annunciator Alaam Review (ZAP 3-51-7)

(P)~or (F) /

SCRE Date 110. ' Process'a Station Procedure Change Request '(ZAP 5-51-4).

(P) or (F) /

SE/SF Date o

ll. Discuss the requirements for a confined space entry

'(ZAP 5-51-6).

/

SE/SF Date

12. Participate in a containment entry (ZAP 5-51-7).

(P) /

't SF Date

13. Discuss access requirements for the control room (ZAP 5-51-8).

/

SCRE Date

14. _ Perform.the' duties of'SE during the discharge of liquid radioactive waste to the lake (ZAP 5-51-9).

(P) or (F) /

SE Date

15. Discuss the requirements for authorizing'an entry into a high radiation area (ZAP 5-51-15).

(P) or (F) /

q, - SE/SCRE/SF Date 4, 16. Discuss the requirements for authorizing an Auxiliary Electrical Room entry.'(ZAP 5-51-17).

f (P) or.(F) /

SF/SE Date

17. Accompany the Shift Foreman on each shift (ZAP 10-52-1).

(P) Day /

SF Date

,1 (P) Afternoon /

SF Date (P) Mids /

SF Date 2

1825P 0288A

Attcchment E (Crs't)

Rev. I

18. Accompany.the SE on each. shift (ZAP 10-52-1).

(P) Day. / .

SE Date

-(P) Afternoon /

~SE Date

.(P) Mids. /-

SE Date

19. Conduct a review of the SE/SF log book (ZAP 10-52-2).

(P) or (F) /

SF/SE Date

20. Participate.in a shift turnover (ZAP 10-52-3).

(P) /

SE Date (P) /

SF Date (P) /

SCRE Date

21. Verify proper shift manning levels (ZAP 10-52-3).

~

'L- i (P) /

SE/SF Date

22. Verify proper control room manning levels (ZAP 10-52-3).

(P) /

SCRE Date 23.. Review the RCS mass balance (ZAP 10-52-4).

(P) or (F) /

SE Date 24._ Complete a lubrication report form (ZAP 10-52-9).

L (P) or (F) /

SE Date

25. Discuss-actions taken when Category I equipment exceeds vibration specifications (ZAP 10-52-10).

(P) /

SE/SF Date I6. Perfona'the duties of the SE for receiving new fuel on site.

(ZAP 13-51-1).

(P) or (F) /

i SE Date 3

1825P 0288A

. _ . _ . . . _ . . __ - - ~ . . . . _._,__-___.. .._ ,, .. ._.. , . . . - . . _ . . . _ . . _ _ _ _ , - _ _ _ _ . .

1 1.L Attachment E.(Con't)

Rev. 1 2 7 .- -Discuss the role of the SE in the preparation and shipment of radioactive waste offsite (ZAP 13-52-8).

(P) or (F) /

SE Date

28. Participate'in the inspection, tagging out, testing, and return to service of plant equipment (ZAP 14-51-2).

(P) or (F) /

SE/SCRE/SF Date t 29. Determination of operability requirement for Tech Spec Related Equipment.

(P) or (F) /

SE/SF/SCRE Date

30. . Determination of Tech Spec compliance prior to changes in operational modes.

(P) or (F) /

SCRE Date

. 31. . Trouble shoot various system malfunctions.*

(P) or (F) /

SCRE Date (P) or (F) /

SCRE Date (P) or (F) /

SCRE Date

  • List those systems on which the trainee participated.
32. -Coordinate tests performed by station personnel.

(P) or (F) /

SCRE Date

33. Coordinate power changes with the Load Dispatcher.

(P) or (F) /

SE/SCRE Date 4

1825P 0288A

(Attachment E)

Rev. 1

34. . Evaluate power distribution during~sud after power level changes.
(P) or (F) /

SCRE Date

~

-35. Perform trend analysis of various parameters.*

/

SCRE Date

/

SCRE Date

/

SCRE Date

  • List permaeters which trainee has trended.

l' i:

i 5 f 1825P 028SA -

r L [.

' Attachment F m.

[ BRAIDWOOD NUCLEAR. STATION HOT PARTICIPATION EXPERIENCE RECORD HAS SUCCESSFULLY COMPLETED Trainees Name

.THE BRAIDWOOD NUCLEAR STATION HOT PARTICIPATION PROGRAM WHICH INCLUDES THE FOLLOWING REQUIREMENTS:

1. _6 MONTHS HOT PARTICIPATION AT ZION STATION.
2. 6 WEEKS OPERATION ABOVE 20% POWER..
3. STARTUP FROM SUBCRITICAL TO 2C%' POWER.
4. SHUTDOWN FROK 20% POWER TO COLD SHUTDOWN. -

1 4 .

't i=

TRAINING SUPERVISOR, BRAIDWOOD STATION l

ASS'T SUPERINTENDENT OF OPERATIONS I BRAIDWOOD STATION i 1 l 1825P

, 0288A'

m

, jw -4 -m - - - - -- - - - --

-s"" -._ 9jy_7q

. j .

g 7*-  : ATTACHMENT 2 ms_ .

.v y s

,, , ' [? ~

p -

+

1 i s  :-BRAIDWOOD NUCLEAR STATION '

_' ' SENIOR REACTOR OPERATOR EIGHT WEEK-HOT PARTICIPATION PROCEDURE

g a ,

A. ~ STATEMENT OF APPLICABILITY

^ The. purpose'of this procedure'is to describe the steps necessary for .the successful' completion of the Braidwood Nuclear Generating Stations' Senior Reactor Operator Eight Week- Hot

.. Participation' Program. When this program has been completed the.

-participant will have gained -8 weeks of Hot Participation Experience at a plant similar to Braidwood. During this period, theLSRO trainee sill be involved in the review and discussion-11eading to decisions relative to' operating a nuclear. power plant. _

, -. B . : ' REFERENCES' l'. J. H. Miller's presentation to-the NRC Commissioners,

" Industry Evaluation of Operating Shift ~ Experience Requirements", February 24, 1984.

~

2. -INPO Guideline 83-022, June 1983, PWR Control Room Operator, Senior Control Room Operator, and Shift Supervisor

_ Qualification.

.. 3. , Nucle'ar Station Directive, A09, Conduct of Operations.

'4. Zion Administrative Procedure:2-52-1, Station Training.

Administrative. Program.

C. PREREQUISITES

c Individuals shall successfully complete an SRO Certification Program _on a similar plant before beginning the Hot.

-Participation Program.

F D. . MAIN BODY

1. ' Complete'the SRO Hot Participation Training Resume (Attachment A) as follows:

~

J /, i' a ',

.i 4

8 -

9 g

7 E . j .- 1

'-  ?.

3.

,, ,r.-..., 4%...., , <~ . . . - , - . . - . , , , , - ...,m.- .., . . -w,.,e-... , , , . , ~ . , . . -m, - . - , - .-v

e

a. :- The trainee or a member of the Braidwood Station

~

, . Training Department shall: complete Section A (General Information) as follows:

1) Name: Fill in name of trainee.

2)- CECO Service Date: Fill in trainee's Company

-Service Date.

b. :The trainee or a member of the Braidwood Station-Training: Department shall complete Section B (Education) as follows:

' ~

1) List the formal training completed by the trainee at accredited colleges and/or universities.

LIndicate Major / Minor, date of graduation, and the .

. school which issued the: diploma.

c. A member.of ths Braidwood Station Training Department shall complete Section C (Commonwealth Edison Training Courses) as follows:
1) Senior. Reactor Operator / Reactor Operator Training Program:

a) Indicate location and date of certification.

b) JIf licensed, indicate Unit on which licensed and date of license.

2) Other Technical courses:

a) Indicate course name location and date of completion.

3) Ceco Management Courses:

i-a) Indicate course name, and date of completion.

2. The trainee should read all required reading items listed on the-SRO Hot Participation Required Reading Form (Attachment B) before going on shift at Zion.

-3. After-completion of each required reading item, the trainee shall document that the required reading is complete by signing his/her name in the space provided on Attachment B.

4. The Job Qualification Checklists (Attachments C and D) contain those tasks which shall be completed by the trainee while on shift at Zion Station.

b 2

L 2713P 0173A s

+

- ~ a'. _ General Instruction-Each: task description.is followed by a'(P) or an (F).

. .Those~ tasks descriptions:followed by's (P) must be actually performed or observed by the trainee while on-

. shift. The trainee is further required to demonstrate

~

. adequate knowledge. relative to the performance of the

-evolution. .The task descriptions followed by an (F),

s may be fulfilled by demonstrating adequate familiarity

-thecush simulation or discussion with designated on shift personnel. The~ preferred method of fulfilling a

-task is by performance (P). -The option of demonstrating

! familiarity-(F) should be used only when a perform (P) lis'not possible or practical.

The Job Qualification Checklist Addendum Log will be completed by the trainee listing those activities which are not specifically listed on the Job Qualification Checklist.

b. Checklist Instructions-There are 2 Hot Participation Job Qualification

. Checklists:

1) ' Reactor Operator H9t Participation Job oualification Checklist:

The objective of this checklist is to directly involve the trainee in day to day control room activities, survelliances, periodic tests, and various plant evolutions. . Items in which the trainee participates that are not listed on the-Qualification Checklist should be documented on the

-Job Qualification Checklist Addendum Log-

2) Shift Supervisor Hot Participation Job oualification Checklist:

The objective of this checklist is to directly involve the trainee in the review and discussion leading to decisions relative to operating a nuclear power plant. The trainee is to complete all items on the Shift Supervisor Hot Participation Job Qualification Checklist and to document all additional items on the Job Qualification Checklist Addendum Log.

Reactor Operator Candidates shall complete the Reactor Operator Hot Participation Job Qualification Checklist as a minimum. Shift Supervisors shall complete both checklists.

3 2713P

- 0173A

5. -The Braidwood Station Training Supervisor and the Ass't Superintendent of_ Operations shall sign the Braidwood

. Nuclear Station Hot Participation Experience Record

.(Attachment F) after verifying the trainee has successfully

. completed the Hot Participation Program requirements. .

b l

r 4

2713P 0173A

t

(_ ~i Attachment A f

Hot Participation Training Resume A.- General Information 1.- Name:

2. Ceco. Service Date:

B.- Education Major / Minor Fields Date School 1.' B.S.

2. M.S.
3. PhD
4. Other C. Commonwealth Edison Training Programs
1. Senior Reactor Operator Training Program Location /Date Unit on Which of Certification Licensed /Date of License
2. Other Technical Courses Title of Proxram Location Date of Completion e

1 2713P

' 0173A

Attachment-A (Con't)

3. Ceco Management-Courses A. Comununication and Motivation-(SAI)

Date-B. LRational Situation Management (KT)-

Date C. Others Date Date

$ Date M

9 6

2 2713P 0173A

Attachment B Hot Participation Required Reading The trainee shall read the following documents:

Trainee Sinnature/Date-A. ZION ADMINISTRATIVE PROCEDURES-

1. ZAP O Conduct of Operation
2. ZAP 01 Admitting and Control of Westinghouse Trainees 3.- ZAP 02 Station Fire Fighting Forces
4. ZAP 02A Fire Protection Surveillance Procedure -
5. -ZAP 02B Control of Flammable and Combustibla Liquids

-6. ZAP 0-3 Press Releases-

7. ZAP 1-51-1 Station Organization
8. ZAP 2-52-1 Station Training Program
9. -ZAP 2-52-3 Operating. Experience Feedback
10. ZAP 2-54-1 On-Site Station Review
11. ZAP 2-54-2 Plant Nuclear Safety Review Committee
12. ZAP 2-54-3 ' Emergency Operating Procedure Review Committee
13. ZAP 3-51-1 Origination and Routing of Work Requests
14. ZAP 3-51-18 Plant Modification Program
15. ZAP 2-51-2 Non-Production Plant Work Orders
16. ZAP 3-51-4 Procedure Governing the Use of Temporary Jumper Cables, the Lifting of Terminated Wires. The Bypassing of Alarms, or The Installation of Mechanical Blocks or Bypasses 2

1 2713P

-0173A

_ _ _ ~ --._ ,._ -.. _ ,~.. _ __ _ . _ _ _ ._. _ _ - __ -

l n- Attachment B (Con't) i Trainee Sinnature/Date .

17. Ju@ 3-51-4B ' Procedure for Non-Routine Valve Line-Ups 2

o, 18. ZAP 3-51-5 Field Change-Requests

' 19. "J@ 3-51-6 . Evaluation of Component Parts

. c:

. Annunciator Alarm Review-

~

'20. ZAP 3-51-7

21. ZAP 3-52-1: Change of Instrument Setpoint/ Scaling
22. ZAP 3-52-2 OAD Periodic Relay Testing and' Instrument Calibration Procedure

.Reportability to Zion Station

23. ZAP 3-52-3 Zion Scaling Procedure
24. ZAP 3-52-4 Change of Protective Relay Setpoint 1
25. ZAP 4-51-l' Establishing Quality Requirements for Requests for Purchase and lI Requisition Cards

~

26. ZAP 5-51-2 Guidelines for an ALARA Review 27 ZAP 5-51-3 -Procedure Periodic Review
28. ZAP 5-51-4 Procedure Control and Approval
29. ZAP 5-51-5 Procedure Content and Format
30. ZAP 5-51-6 Confined Space Entry

!! 31. ZAP 5-51-7 Containment Access Control

32. ZAP 5-51-8 Access Control to the Control Room
33. ZAP 5-51-9 Liquid Waste Management
34. ZAP 5-51-15 High Radiation Area Access Control
35. ZAP 5-51-16 Reactor Cavity (Incore Shaft)

Access Control

36. ZAP 5-51-17 Entry and Exit to Auxiliary Electrical Room 2

2713P 0173A

.c. ,

t. W A

- Attachment'B (Coa't)

Trainee Sinnature/Date 37.: ZAP.5-51-18 Personnel Termination Procedure i

38.; ZAP 5-51-19 Personnel Qualifications

~

39. ZAP 6-52 .

Zion Station Drawing Change:

Request Program' 40.' ZAP 6-52-2 Zion Station Document Control

~

141. ZAP 6-52-3' Zion Station Mail Receipt Control

.42. ZAP 6-52-4 Zion Station General Office

. Master File Control

43. ZAP 10-52-1 Inspection Plan for Operations
44. ZAP 10-52-2 Operating Log Books

.45. ZAP 10-52-3 Shift Manning, Relief. and Turnover

46. ZAP 10-52-4 Leak Reduction and Control Program b

47.' ZAP 10-52-5 Housekeeping 48 ZAP 10-52-9 Station Lubrication Report

'49; ZAP 10-52-10 Vibration Monitoring / Analysis Program _

s 50. ZAP 10-53-1 Inspection Plan - Surveillance

51. ZAP 13-51-1 Responsibilities, Novements, and Reporting Related to Safeguarding Nuclear Fuel
52. SUU? 13-52-1 Receiving Handling, Storage, Packaging, and Shipping of Items in the Storeroom -

.53 ZAP 13-52-2 Preventive Maintenance & Limited Shelf Life of Safety-Related and ASME Code Items

54. ZAP 13-52-3 Receiving and Storing Chemicals
55. ZAP 13-52-4 Handling, Storage and Control of Welding Materials 3

2713P 0173A

-- . - _ . _ _ . . . _ . _ _ _ _ _ . _ _ . . _ _ . . _ , _ _ _ _ . ~ . _ . _ _ _ _ _ _ . _ _ , _ . . _ . _

Attachme . B (Con't)

Trainee Sianature/Date

-56. ZAP 13-52-8 . Preparation and Shipment of Radioactive Material 5'7 '. ZAP 14-51-2 Inspection, Test and Operating Status Tagging of Equipment

58. ZAP 16-51-1  : Zion Station Action Item Record Program B. ZION STATION RADIATION PROCEDURES
1. RP 1190-1 Zion radiation protection general procedures
2. RP 1210-3 Personnel neutron monitoring
3. RP 1210-4 Dose calculations, time limits and timekeeping
4. RP 1230-1 Lost film badge procedure-
5. RP 1240 Survey instrument calibration

. Series (1-22) and use

6. RP 1280-1 Rs liation surveys _.
7. RP 1280-2 Radiation level area surveys
8. RP 1310 Use of respiratory protective Series (1-12) equipment __
9. RP 1320-1 Personnel injury in controlled area
10. RP 1330-1 Working in radioiodine & tritium atmosphere
11. RP 1340-1 Personnel contamination procedure
12. RP 1350-8 Radiation monitor out of service and return to service procedure
13. RP 1350-20-23 Testing of breathing & working environments 4

2713P 0173A

7

. o.

N Attachment B (Con't)

Trainee Sinnature/Date

14. RP 1350-37 High Radiation Monitor Alarm
15. RP 1360-4 Testing of breathing & working environments
16. RP 1410-1 Protective clothing
17. RP 1410-2 Washing protective clothing 18..R? 1430-1 . Unconditional release of materials
19. RP 1470-3 Area and material decon
20. RP 1470-4 Personnel decontamination
21. RP 1480-2 Contamination surveys
22. RP 1490-1

. Contamination control. points

23. RP 1520-1&2 Radioactive waste shipments
24. RP 1610-5 Containment entry procedure
25. RP 1610-6. Gas leaks in Aux. Building or Containment
26. RP 1610-8 Reactor coolant leak detection
27. RP 1740-1 . Monitoring of high activity gas release during an accident
28. RP 1740-2 Setting up the emergency command center
29. RP'1740-5 Emergency equipment storage and
i. location
30. RP 1740-6 Radioactive liquid spills 5

! 2713P

[. 0173A

.s

ve

-Attachment B (Con't) r

-Trainee Simnature/Date i

.C. 10CFR20 STANDARDS FOR PROTECTION AGAINST RADIATION D. 10CFR50 LICENSING OF PRODUCTION AND

. UTILIZATION FACILITIES With Emphasis of Appendicles A,B, E.H.I.J.K and R' E. 10CFR55 OPERATOR LICENSES

Paragrapahs 55.1 thru 55.6, 55.20 thru 55.23, 55.30 thru 55.50 F.- 10CFR100 REACTOR SITE CRITERIA G. GENERATING STATION ENERGENCY PLAN
1. Generic GSEP

-2. EPIPs H. ZION STATION CHEMISTRY PROCEDURES

,1. ZCP-200 Primary System Sampling Procedure

2. ZCP-300 Zion Station Liquid Releases
3. ZCP-304 Containment Venting & Purging Analysis
4. -ZCP-306 Continuous Gaseous Release calculations

'I. PLANT MODIFICATIONS-

-1. Review recent modifications and setpoint changes.-

J. OPERATING EXPERIENCE REPORTS (OPEI)

1. - Read major operating experience reports from other plants.
2. Read major and recent (last year) Zion LER's.

K. INSTRUNENT FAILURE RESPONSE MANUAL

1. Review plant' response to instrument fallures.

6 2713P 0173A

, 1 Att:chmert C REACTOR OPERATOR HOT PARTICIPATION JOB QUALIFICATION CHECKLIST

. . M9II

The trainee shall participate in the control _ room during.

the following' evolutions.

1. 6 weeks operation above 20% Reactor Power.

/

r SF Date

2. A refueling outage or a plant startup following an outage.

/

SF Date

M9T1 4 The trainee should perform or demonstrate familiarity with the following duties of a control room operator under the direct-supervision and guidance of a qualified control room operator.
3. Reactor Startup:

a) . Cold Shutdown to Hot Shutdown.

(P) /

NSO/SF Date b) Hot Shutdown to Hot Standby.

I NSO/SF Date c) Suberitical to critical.

(P) /

NSO/SF Date d) Critical to 2% power.

(P) /

NSO/SF Date s e) Reactor power increase from 2% power to 20% power.

(P) /

NSO/SF Date

4. Reactor Shutdown:

I a) Reactor power decrease from 20% power to Hot Standby.

(P) /

l NSO/SF Date I b) Hot Standby to Hot Shutdown.

(P) /

l- NSO/SF Date c)- Hot Shutdown to Cold Shutdown.

i (P) /

NSO/SF Date l 1 l 2713P 0173A .

f Attachment C

5. Ma'nual~ control of steam generator. levels during plant start-up and/or shutdown.

(P) /  :

MSO/SF -Date

6. Boration during power operation.

(P) /

NSO/87 Date

7. Dilution during power operation.

(P) /

NSO/SF Date

8.- Reactor power changes of 10% or greater when rod control is in manual.

(P) /

NSO/SF Date

9. Operation of turbine controls during turbine start-up.

(P) /

NSO/SF Date 1 10. Synchronization of the main generator with the grid.

(P) /

NSO/SF Date

11. Control room operations during 3 shifts of refueling.

(P) /-

, NSO/SF Date

' 12. Residual heat removal system startup and shutdown.

(P) /

NSO/SF Date

- 13. Control of primary pressure under solid water conditions.

(P) /

NSO/SF Date i

2 .

2713P 0173A

I 4

Attcahmert C-  !

[14. Incore' instrumentation system operation. I (P) /

NSO/SF Date

15. Large change in Reactor Power. ]

(P) /

NSO/SF Date

16. Large rate of change in Reactor Power (Rate of change greater than required for norma 1' operations i.e. abnonmal condition)

--(optional).

(P) /

NSO/SF Date

17. -Participate in a fire drill as a Control Room Operator.

(ZAP -02)

(P) or (F) / _,

NSO/SF Date

18. Discuss the NSO responsibilities in the Station Organization.

(ZAP 1-51-1)

/

NSO/SF Date

19. Participate in a shift turnover (ZAP 10-52-3)

(P) /

Center Desk Date (P) /

Unit Operator Date

20. Calculate an estimated critical condition.

(P) or (F) /

NSO/SF Date

21. Perform or assist with the following survelliance tests:

PT-0 Unit Shift surveillance Appx B/B-1, Shutdown Mergin Verification (Modes 2, 3, 4, 5, & 6).

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date 3

2713P 0173A

)

Attachment C

/

'Appx D, Operating Surveillance Checksheet P

(P); Shift 1 / ,

NSO/SF Date (P) Shift 2 /

NSO/SF Date

-(P) Shift 3 /

NSO/SF Date Appx E' Operating Surveillance, (P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx F, Operating Surveillance Cuscksheet-(Modes 3 & 4)

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF 'Date Appx G, Operating Surveillance Ch3cksheet (Modes 1 & 2)

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date i

i E

4

' 2713P 0173A

Attachment C

'2

'Appx H, Control Rod Alignment Checksheet (Modes 1 & 2)

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx I, Excore Detector Outputs and Quadrant Power Tilt Ratio (Mode 1 > 50%).

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date Appx J-1, Normal and Reserve Off Site AC Power Availability.

(P) Shift 3 /

NSO/SF Date Appx J-2, Onsite AC & DC Power Availability.

(P) Shift 3 /

NSO/.*F Date Appx K. Station Battery Daily Record (P) Shift 2 /

NSO/SF Date Appx L. Reactor Protection Channel check & E.S.S.

Instrumentation Channel Check (Modes 1, 2, 3, & 4).

(P) Shift 1 /

NSO/SF Date (P) Shift 2 /

NSO/SF Date (P) Shift 3 /

NSO/SF Date 5

2713P 0173A

<  : e.-

0 , . 3 7+ , Attachment C v '

Appa M.'Calormetric

~

. 3, ,

(P) Shift 2; /

NSO/SF Date

,{' <

Appx N, Radiation Monitor Check' (P) Shift 1 /

NSO/SF Date Appx P. Power Nistory Log (P) Shift 1 /

NSO/SF Date (P) Shift 2 /

-NSO/SF Date

-(P) Shift 3 /

NSO/SF Date PT-1 Rod Cluster Exercise (P) or (F) /

NSO/SF Date PT-2A- Safety Injection Pump Tests (P) or (F) /

NSO/SF Date PT-2C ECCS Valve Interlock Tust (P) or (F) /

NSO/SF Date PT-2E Spurious Valve Actuation Group

' De-energization Check (P) or (F) /

NSO/SF Date PT-2I Centrifugal Chg. Pump Tests (P) or (F) /

NSO/SF Date PT-2J .RNR Pump Tests (P) or (F) /

NSO/SF Date PT-2R ' Penetration Press._ Compressor Test

! (P) or (F) /

NSO/SF Date l

6 2713P

! 0173A L

, o ~ -

F -1,'- /

, : Attachment C m.

PT-3B 'Isoletion Valve Seal Water (P) or (F)

~

/

NSO/SF Date

PT-3C - Penetration Pressurization Tests (P).or (F) /

NSO/SF Date PT-3D NSIV Test (P) or (F) /

NSO/SF Date-PT-4A N.I.S. Functional Test 8.R.

(P) or (F) /

NSO/SF Date PT-4B N.I.S. Functional Test I.R.

(P) or (F) /

M80/8F Date PT-5 Reactor-Protection Logic (P) or (F) /

NSO/SF Date PT-5A Reactor Protection Logic (P) or (F) /

NSO/SF Date PT-5B Reactor Protection Logic (P) or (F) /

NSO/SF Date PT-6 Containment Spray Pump Test (P)'or (F) /

NSO/SF Date PT-7 Aux. Feedwater Pump Test (P) or (F) /

NSO/SF Date PT-9 Service Water Valve Tests (P) or (F) /

NSO/SF Date PT-10 Safeguards Actuations Tests (P) or (F) /

NSO/8F Date PT-10A Safeguards Logic Test ,

(P) or (F) /

NSO/SF Date PT-10B Safeguards Logic Test.

(P) or (F) /

NSO/8F Date 4

k 7

2713P 0173A

~

, e

f. Attachment C PT-10C Safeguards Logic Test (C.S.D.'only)

(P) or (F) /

NSO/SF Date PT-11 Diesel Generator Load Test-Locally Control Room (P) or (F) /

NSO/SF Dato PT-12 Boric Acid Heat Trace Test (P) or (F) /

NSO/SF Date PT-14 Inoperable Equipment Sury. Tests (P) or (F) /

NSO/SF Date PT-15 Rx Containment Fan Cooler Tests (P) or (F) /

NSO/SF Date PT-16 Boric Acid Transfer Pump Tcats (P) or (F) /

NSO/SF Date PT-17 Gas Decay Tank & Containment Purge Auto Valve Tests (P)or (F) /

NSO/SF Date PT-20 Centrifugal Charging System Valve Tests (P) or (F) /

NSO/SF Date PT-21 R.C.S. Leak Rate Test. Manually (P) or (F) /

NSO/SF Date PT-24 Unit to System Aux. Transformer Auto Feed Transfer (P) or (F) /

NSO/SF Date PT-101 Turbine Protective Device Tests (P) or (F) /

NSO/SF Date PT-102 Intercept & Reheat Stop Valve Test (P) Or (F) /

NSO/SF Date PT-103 Turbine Stop & Cov. Valve Tests (P) or (F) /

NSO/SF Date

. PT-105 Jumper / Lifted Lead Verification (P) or (F) /

NSO/SF Date PT-106 Key Audit (P) or (F) /

NSO/SF Date PT-201 Fire Protection Pump Tests (P) or (F) /

NSO/SF Date 8

2113P 0173A

I-' i 1

j

, Attachment C i

26. -Manually control Steam Generator level while operation at > 80% power.

(P) or (F) /

-NSO/SF Date 2 7. - Shift steam Generator Level Control system from manual to automatic during start-up.

(P) or (F) /

NSO/SF Date 28.- Shift Steam Generator Level Control system from manual to automatic l while operation at > 80% power.

(P) or (F) /

NSO/SF Date

29. Control Auxiliary Feedwater flow to Steam Geneestor during start-up, shutdown or trip recovery.

(P) or (F) /

NSO/SF Date

30. Adjust the negavar loading on the main generator using appropriate curves.,

(P) or (F) /

NSO/SF Date

31. Operate the P-2500 computer console:

Digital Display (P) or (F) /

NSO/SF Date Add / Remove from Scan (P) or (F) /

NSO/SF Date Digital Trend (P) or (F) /

NSO/SF Date Analog Trend (P) or (F) /

NSO/SF Date

32. ' Adjust Accumulator levels a) Raise level with RCS pressure > 1600 psi.

(P) or (F) /

-NSO/SF Date b) Raise level with RCS pressure < 1600 psi.

(P) or (F) /

NSO/SF Date

33. Adjust Accumulator nitrogen pressure.

(P) or (F) /

NSO/SF Date

34. Control A I during steady state conditions. ,

(P) or (F) /

NSO/SF Date 9

2713P 0173A

l I

I l

Attachment C 35.- Discuss control of A I following a power change and the procedure for dampening Axial Xenon Oscillations.

(P) or (F) /

NSO/SF Date

36. Complete a Containment Purge &. Vent form.

(P) or (F) /

NSO/SF Date

37. Complete a Liquid Radwaste Discharge form.

(P) or (F) /

NSO/SF Date

38. Demonstrate familiarity with curves and graphs associated with the Radiation Monitor system.

(P) or (F) /

NSO/SF Date

39. Source check and operate the following radiation detection instruments:

RO-1 Rad. Owl- (P) /

NSO/SF Date PRM-4 Alpha Survey (P) /

NSO/SF Date PRN-4 Neutron Survey (P) /

NSO/SF Date Teletector, Hi-Range Beta / Gamma

~(P) /

N00/SF Date

40. Discuss the significance of changes in VCT and/or PRT level (s) when operating at steady state.

/

NSO/SF Date

41. - Demonstrate familiarity with the location, operation and/or function of the following Control Room equipment:

On-Site Communications Equipment L (P) or (F) /

NSO/SF Date Off-Site Communications Equipment (P) or (F) /

NSO/SF Date Emergency Equipment (P) or (F) /

NSO/SP Date Fire & Evacuation Alarms (P) or (F) /

NSO/SF Date Emergency Keys (P) or (F) /

NSO/SF Date Loose Parts Monitor (P) or (F) /

NSO/SF Date 10 2713P 0173A

2 e

(v Attachment C 42.' Shift source of Aux. Steam from unit to unit or to Aux. Boiler.

(P) or (F) /

NSO/SF Date

43.  : Discuss your' responsibilities under the GSEP.

/

NSO/SF Date

44. Operate 345 KV OCB's from the General Services panel and coordinate operations with LD.

(P) or (F) /

MSO/SF Date 11

. ,- ~2713P d *,

0173A

._ - . . - _. _. - .~ . _.

s Y

r. -

Attachment D SHIFT SUPERVISOR' HOT PARTICIPATION r . JOB QUALIFICATION CHECKLIST ,

1. Discuss the responsibilities of the S.E, in the station-organization (ZAP 1-51-1).

/

SE Date

??:

2.- Discuss the responsibilities of the S.F. in the station organization ~(ZAP 1-51-1).

'/p /

, .\.  ;" ' SF - Date  ;

e . [ .,

rf[..

[ . . t, ;3. Discuss the responsibilities of the SCRE/STA in the station organization (ZAP 1-51-1).

]0, ' h ',_ .$.;;h, . ;

1

. a, f 1[

~

SCRE Date t~t n :

4. Prepare a non-routine valve lineup. (ZAP 3-51-48)

' OI -

(P) or (F) /

^

SE/SF Date

, ' ' ' e} .

5. ' Perform the Annunciator. Alarm Review (ZAP 3-51-7)

(P) or (F)- /

<- SCRE Date

5. Discuss the requirements for a confined space entry (ZAP.5-51-6).

/

SE/SF Date

7. Participato in a containment. entry (ZAP 5-51-7).

' ' - (P) /

SF Date .

8. Discuss access requirements for the control room (ZAP 5-51-8).

/

SCRE Date t

I i-I-

l' s 1

2713P 0173A

r-Attachment D

). t

-9. Parform the duties of SE during the discharge of liquid radioactive waste to the lake (ZAP 5-51-9).

(P) or (F) /

SE Date

10. Discuss the requirements for authorizing an entry into a high radiation area (ZAP 5-51-15).

(P) or (F) /

SE/SCRE/SF Date

11. Discuss the requirements for authorizing an Auxiliary Electrical Room. entry (ZAP 5-51-17).

(P) or (F) /

SF/SE Date

12. Accompany the Shift Foreman on each shift (ZAP 10-52-1).

(P) Day /

SF Date (P) Afternoon /

SF Date (P) Mids /

SF Date

13. Accompaoy c,he SE on each shift (ZAP 10-52-1).

(P) Day /

SE Date (P) Afternoon /

SE Date (P) Mids /

SE Date

14. Conduct a review of the SE/SF log book (ZAP 10-52-2).

(P) or (F) /

SF/SE Date 2

2713P 0173A L/.

y;= - -

e a

Attachment D

15. Participate in a shift turnover (ZAP 10-52-3).

(P) /

SE Date 3

(P) /

SF Date (P) /

SCRE Date

16. Verify proper shift manning levels (ZAP 10-52-3).

(P) /

SE/SF Date

17. Verify proper control room manning levels (ZAP 10-52-3).

(P) /

SCRE Date

.18. Review the RCS mass balance (ZAP 10-52-4).

-(P) or (F) /

4 SE Date 19.' Complete a lubrication report form (ZAP 10-52-9).

(P) or (F) /

SE Date

20. Discuss actions taken when Category.I equipment exceeds vibration specifications (ZAP 10-52-10).

(P) /

SE/SF Date

21. Perform the duties of the SE for receiving new fuel on site.

(ZAP 13-51-1).

t (P) or (F) /

SE Date

22. Discuss the role of the SE in the preparation and shipment of <

radioactive waste offsite (ZAP 13-52-8).

(P) or (F) /

SE Date 3

2713P-0173A-

f-Attachment D

.23. Participate in the inspection.. tagging out, testing, and return to servica of plant equipment (ZAP 14-51-2).

(P) or (F) /

SE/SCRE/SF Date p

24. Determination of operability requirement for Tech Spec Related

.3quipment.

(P) or (F) /

SE/SCRE/SF Date .

25. Determination of Tech Spec compliance prior to changes in operational modes.

(P) or (F) /

SCRE Date

-26. Trouble shoot various system malfunctions.*

(P) or (F) /

SCRE Date (P) or (F) /

SCRE Date (P) or (F) / __,

SCRE Date

  • List those systems on which the trainee participated.
27. Coordinate test performed by station personnel.

(P) or (F) /

SCRE Date

28. Coordinate power changes with the Load Dispatcher.

(P) or (F) ,

/

SE/SCRE Date

29. Evaluate power distribution during.and after power level changes.

(P) or (F) /

SCRE Date i

i-4 2713P 0173A-

e .

e

' Attachment D O 30.-Perform trend analysis of various parameters.*

(P) or-(F) /

SCRE Date (P).or (F) /

SCRE. Date (P) or (F) /-

. SCRE Date

  • L'ist parameters which~ trainee has trended.

+

4 L

t-t

}

}

5

. 2713P-0173A

- . -~ , - . --

n- r y-Attachment E HAS SUCCESSFULLY COMPLETED 4

Trainees Name THE BRAIDWOOD NUCLEAR STATION 8 WEEK HOT PARTICIPATION PROGRAM WHICH INCLUDES THE FOLLOWING REQUIREMENTS:

l. 8 WEEKS ONSHIFT AT ZION STATION.

4 2. 6 WEEKS OPERATION ABOVE 20% POWER.

1

3. STARTUP FROM SUBCRITICAL TO 20 PERCEitT POWER. *
4. SHUTDOWN FROM 20 PERCENT POWER TO COLD SHUTDOWN. A 4

4

' TRAINING SUPERVISOR, BRAIDWOOD. STATION l.

ASS'T SUPERINTENDENT OF OPERATING BRAIDWOOD STATION i

l'

  • Optional ITEMS - Circle those items which were completed during the course of the eight week Hot Participation Program.

(.

1 2713P' 0173

^M WEEK 1 I DAY 1 I DAY 2 1 DAY 3 i DAY 4 1 DAY 5 1

_g________________g________________g___________.____g________________l________________g_

l i I Shift Turnover i Shift Turnover 1 Shift Turnover I I I i Shift Muster i Shift Muster 1 Shift Muster i I I I Upcoming i Upcoming i Upcoming i I I i Evolutions l Evolutions l Evol u t i ons l l l l _____________-

l ______________ g ______________ g i I I I I i I I i l I 1 I I i SEMINAR I SEMINAR 1 SEMINAR I i 1 1 - ZAP 3-51-1 1 - RP 1740-5 I - Portable I i i 1 - ZAP 3-51-2 1 - RP 1190-1 1 Survey i I I I - ZAP 10-52-2 1 - RP 1210-3 I Instrumenta- 1 I I I - ZAP 10-52-3 1 - RP 1210-4 I tion 1 I I I - ZAP 14-51-2 I - RP 1210-3 1 1 I PLANT I PLANT TOUR I - ZAP 5-51-B 1 - RP 1410-1 1 RD-1 Rad Owl i I ORIENTATION I --------------

1 I I PRM-4 Alpha i i I ORIENTATION I I THEORY I Survey 1 I NGET l C/R OPERATIONS I I Gas-Filled i PRN-4 Neutron 1 I Mask Fit 1 - Board 1 -------------- 1 Detectors I Survey 1 -

I Whole Body I Walkdown I WATCHSTANDING I WATCHSTANDING l 1 1 Count 1 - Ccntrol Room I and C/R I and C/R I Telector 1 I F11m Be.dge I Administra- 1 OPERATIONS I OPERATIONS I HI Range i I Picture Badge I tion i Initiate Work 1 - Rad Equip in 1 Beta / Gamma l i I I Requests and l C/R I -------------- 1 I I I Equip Tagouts 1 - Coen Equ 1 p I WATCHSTANDING I I I I I - Off-Site I and C/R I I I I I Comm Equip i OPERATIONS I I I I I - C/R Emerg i Process Rad I I I I I Equip 1 Monitor I I I i 1 - Fire and i Operations I g i I I I Evac Alarm i 1 g i i l 1 - Emerg Keys i I g.

I I  ! I - Loose Parts i 1 g i I I I Monit. I I g i I I I I I w

I i 1 1 1 1 I I I I I I i ______________

i ______________

i _______________i_______________ i ______________ i g m

E0 M

C3 L _ . _ _ _ _ _

. WEEK.2 ,,

1 DAY 1 1 DAY 2. I 9AY 3 1 DAY 4 I DAY 5- I .*

_g________________q _______________;____.____________g________________g________________g_

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RP 1610-5 I I 2CP 300 and I l- I I - PT-1 1 I 304 1 1 I

[ l - PT-2C I I I- 1 1 l l ______________ i ______________ g ______________  ; ______________ g ______________ g

} -I WATCHSTANDING 1 WATCHSTANDING I WATCHSTANDING I WATCHSTANDING- I WATCHSTANDING I i i C/R OPERATIONS I C/R OPERATIONS I C/R OPERATIONS I C/R OPERATIONS 1 C/R OPERATIONS I i Simulate I Compute ECC i Fill Out i Simulate Doing i Simulate I

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. ~ . - . . _

WEEK 3.

1 DAY 1 1 ' DAY 2 l- DAY;3- 1 DAY 4' I DAY 5 1

_g________________g________________g________________g________________g________________g_

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i ______________ g ______________ i ______________ g ______________ g ______________ l l WATCHSTANDING 1 WATCHSTANDING 1 WATCHSTANDING I WATCHSTANDING 1 WATCHSTANDING 1~

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i

- . . ~ . . . , . . ~ - . _ . .

WEEK 4- -

.1 DAY 1- I DAY 2 1 DAY 3 1 DAY 4 1 DAY.5 'l ~

_l________________g________________l________________l________________l________________l_

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l ______________ g ______________ g ____-_________ g i l I I I i i SEMINAR I SEMINAR. I SEMINAR I SEMINAR I-SEMINAR l' I - RP 1230-1 I'- PT 11- I ZAP 10-52-4 1 - PT 17 1 'RP 1350-37 1 1 - RP 1200-1 1 - PT 12 1 - ZAP 10-52-9 1 .PT 20 1 - RP 1430-1 1 1 - RP 1280-2 1 - PT 14 I - ZAP 13-51-1 1 - PT 21 ~l - RP 1470-4 1 1 - RP 1310 _ l - PT 15 1 - ZAP 13-52-8 1 - PT 24 1 RP 1480-2 I I - RP 1320-1 1 - PT 16  ! I - PT 101 1 - RP 1520 1 i 1 - RP 1330-1 1 1 1 - PT 102 1 - RP 1610-6 I I - RP 1340-1 1 I I - PT 103 1 - RP 1610-8 I I - RP 1350-8 l l- t 1 - RP-1740-1 1 I I I I I:- RP.1740-6 I I THEORY I --------------

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1 I Rad Decay I WATCHSTANDING I WATCHSTANDING I WATCHSTANDING' I WATCHSTANDING 1 1 I and C/R l'and-C/R I and C/R 1 and C/R I I -------------- 1 OPERATIONS 1 OPERATIONS l OPERATIONS I OPERATIONS I I WATCHSTANDING I Discuss.and i Discuss and 1 Discuss and I. Discuss and i I and C/R I Simulate PT's i Simulate TAP's-l Simulate PT's i Simulate RP's i l OPERATIONS I I I I I I Discuss and i I I I I I Simulate RP's 1 1 1 I I i 1 1 I I I I I I I I I I I I I I I I I I i i I

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l l

WEEK 5 .

l DAY 1 i DAY 2 1 DAY 3 1 DAY 4 I DAY 5 1

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l Shift Turnover i Shift Turnover i Shift Turnover i Shift Turnover 1 Shif t Turnover i I Shift Muster i Shift Muster I Shift Muster i Shift Muster i Shift Muster i I Upcoming i Upcoming 1 Upcoming i Upcoming i Upcoming I I Evolutions i Evolutions l Evolutions l Evolutions l Evolutions l l ______________ g ______________ g ______________

l _.____________ g ______________ g i I I I i 1 1 THEORY I SEMINAR I. SEMINAR I SEMINAR I SEMINAR I I Pump Laws i Operating i Operating i Operating i LER's i I I Procedures i Procedures l Procedures 1 OPEX 1 11 i from Refueling i Hot S/D to I Plant S/D to 1 I I I to Hot S/D I Power i S/D I I I I I I I I I I I I i 1 I I I I I I l ______________

l ______________ g ______________ g ______________ l ______________

l 1 WATCHSTANDING 1 WATCHSTANDING 1 WATCHSTANDING I WATCHSTANDING 1 WATCHSTANDING I I and C/R 1 and C/R I and C/R I and C/R I and C/R I I OPERATIONS I OPERATIONS 1 OPERATIONS 1 OPERATIONS I OPERATIONS 1 1 - PT 2A 1 Normal I Normal I Normal i I l - PT 21 1 Procedures l Procedures l Procedures 1 I I - PT 2J l Req te Change i Reg to Change i Req to Change 1 I l - PT 6 i Modes 1 Modes I Modes l I I - PT 7 I I I I I i i i I I I I I I I I I I i 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 1 I I I I I I I I I I I I I I I I l ______________ g ______________ l __________..____l______---- _ _ _ .

l ______________ l

    • .3 % se s v' w - - o * *
  • n-WEEK 6
  • l DAY 1 l DAY 2 1 DAY 3 I , DAY 4 I DAY 5 I

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l ______________ l ______________ g ______________ g I WATCHSTANDING I WATCHSTANDING I WATCHSTANDING I WATCHSTANDING 1 WATCHSTANDING 1 I and C/R 1 and C/R I and C/R- I and C/R 1 and C/R I I OPERATIONS I OPERATIONS I OPERATIONS I OPERATIONS I OPERATIONS I I Load Dispatch l Instrument i Rad Monitor I-Use of Remote -1 Practice i 1 Co-ordination i Failures, 1 Alarms I S/D Panels 1 Or al Rx S/U 1 1 ADS 1 Tech. Specs., I i 1 Stressing i I Generators in I Trip Bistables I i i Admin. and i I Para 11e1 1 l- 1 I Theory i I Elec Equip I I I I i 1 00S I I I I I I (Non-Plant) 1 I I I I I I I I I I I I I I i l 1 I I I I I I I I I I I I I I I I I I I i 1 1 I I I I I I I I I I I I I I I I I I I I I I I i 1 l ______________ l ______________ g _______________g_______________ g ______________ l

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~

  • WEEK 7 j

l . DAY 1. I DAY 2 1 DAY 3 1 DAY 4 -l . DAY 5 'l '

c_g________________g________________g________________g________________g________________g_

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I Evolutions l Evolutions i Evolutions I . Evolutions I Evol u t i ons 1 i ______________ g ______________ g ______________ i ______________ i ______________ g ,

I l 1 I i i l l Emerg i Emerg i Abnormal 1 THEORY I Fire i I Procedures I. Procedures l Procedures l-Safety Limits 1 Protection 1 i 1. I Core Thermal I I I

l l I Limits 1 I I

I I I I I i 1 I I I i 1 i I I i I i I I i I i i I g ______________ g ______________ g ______________ g ______________ g ______________ g i WATCHSTANDING l WATCHSTANDING 1 WATCHSTANDING I WATCHSTANDING I WATCHSTANDING 1 I and C/R I and C/R I and C/R I and C/R 1 and C/R I I OPERATIONS I OPERATIONS 1 OPERATIONS I OPERATIONS I OPERATIONS I I Emergency i Emergency I Abnormal I-Transient i Fire Brigade i 1 Procedures I Procedures l Procedures i Operations I Responsibil- 1 I Oral Rx S/U l Oral Rx S/U 1 I I itles 1 1

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I I I I l 1 I i 1 1 I 1

I I I I I i I I i l i I I I I I I I

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I I I I l- 1 I I I I I I

___.__________ l ______________ i _______________g_______________ g ______________ g

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

i WEEK 0-

________________________ _____________________________________________________________ DAY 5 i

  • DAY 2 DAY.3 i DAY 4 I l DAY 1 l 1

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i I OPERATIONS I 3-4 hours 1 3-4 hours I  !

I I I Logic I I  !

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l i i 1 i I i I I I I l I I 1

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