ST-HL-AE-1736, Forwards Updated List of Ref Matls Applicable for 861113 Written Reactor Operator & Senior Operator Licensing Exams, Per 860811 Request.Related Correspondence

Forwards Updated List of Ref Matls Applicable for 861113 Written Reactor Operator & Senior Operator Licensing Exams, Per 860811 Request.Related Correspondence

ML20215B164
Person / Time
Site:	South Texas
Issue date:	08/27/1986
From:	Wisenburg M HOUSTON LIGHTING & POWER CO.
To:	Gagliardo G, Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CON-#486-0572, CON-#486-572 OL, ST-HL-AE-1736, NUDOCS 8610060388
Download: ML20215B164 (10)

Text

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The Light gygo comPuy ><"es"- 'is n'i"s & re-er e.o. n"x >>"" ><""s'"". Tex s '7""> <'is> 228-92ii

% SEP ~3 pg; 3; August 2/, 1986 CkTfk:

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ST-HL-AE-1736 File No.: G25 Mr. G. E. Gagliardo, Chief Reactor Projects Branch, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Reactor Operator and Senior Operator Licensing Examinations

Dear Mr. Gagliardo:

In response to your letter of August 11, 1986, enclosed is an updated list of reference materials that will be applicable for the November 13, 1986 written examinations.

A copy of the actual referenced materials was Federal Expressed to your Mr. J. E. Whittemore, Examiner, on August 28, 1986.

Please note on the updated list that an asterisk indicates a revision to material used for July 24, 1986 examination, while a plus sign indicates new material additions to that used for the July 24 examination.

If you have any questions, please contact Mr. M. A. McBurnett at (512) 972-8530.

Sincerely, M. R.aWisenburg Manager, Nuclear nsing FAW:ljm Attachment

- 8610060388 860327 PDR ADOCK 05000498 V PnR L3/NRC/an

ST-HL-AE-1736 Ilouston Lighting & Power Company File No.: G25 Page 2 cc:

Hugh L. Thompson, Jr., Director Brian . Berwick, Esquire Division of PWR Licensing - A Assi.et nt Attorney General for Office of Nuclear Reactor Regulation the hate of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 N. Prasad Kadambi, Project Manager Lanny A. Sinkin U.S. Nuclear Regulatory Commission Christic Institute 7920 Norfolk Avenue 1324 North Capitol Street Bethesda, MD 20814 Washington, D.C. 20002 Claude E. Johnson Oreste R. Pirfo, Esquire Senior Resident Inspector /STP Hearing Attorney c/o U.S. Nuclear Regulatory Office of the Executive Legal Director Commission U.S. Nuclear Regulatory Commission P.O. Box 910 Washington, DC 20555 Bay City, TX 77414 Charles Bechhoefer, Esquire M.D. Schwarz, Jr., Esquire Chairman, Atomic Safety &

Baker & Botts Licensing Board One Shell Plaza U.S. Nuclear Regulatory Commission Houston, TX 77002 Washington, DC 20555 1.R. Newman, Esquire Dr. James C. Lamb, III Newman & Holtzinger, P.C. 313 Woodhaven Road 1615 L Street, N.W. Chapel Hill, NC 27514 Washington, DC 20036 Judge Frederick J. Shon Director, Office of Inspection Atomic Safety and Licensing Board and Enforcement U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Citizens for Equitable Utilities, Inc.

T.V. Shockley/R.L. Range c/o Ms. Peggy Buchorn Central Power & Light Company Route 1, Box 1684 P.O. Box 2121 Brazoria, TX 77422 Corpus Christi, TX 78403 Docketing & Service Section H.L. Peterson/G. Pokorny Office of the Secretary City of Austin U.S. Nuclear Regulatory Commission P.O. Box 1088 Washington, DC 20555 Austin, TX 78767 (3 Copies)

J.B. Poston/A. vonRosenberg Advisory Committee on Reactor Safeguards City Public Service Board U.S. Nuclear Regulatory Commission P.O. Box 1771 1717 H Street San Antonio, TX 78296 Washington, DC 20555 Revised 5/22/86

. ATTACHMENT

. ST HL AE /N 8/27/86 PAGE / OF F j s A. Administrative Procedures Procedure Title Rev. Effective Date

1. PGP03-ZO-04 Plant Conduct of Operations 00 08/27/86

2. PGP03-ZO-05 Reactor Operations Conduct of Operations 00 04/15/86

(*)3. PGP03-ZA-02 Plant Procedures 05 07/15/86

4. PGP03-ZA-10 Plant Procedure Compliance 02 03/03/86

5. PGP03-ZE-04 Plant Surveillance Program 02 02/28/86

6. PGP03-ZF-01 Fire Protection Program 00 04/02/84 i

(*)7. PGP03-ZM-02 Preventive Maintenance Program 05 06/11/86

8. PGP03-ZM-03 Maintenance Work Request 03 04/16/86

9. PGP03-20-01 Equipment Clearance 02 03/25/85

(*)l0. PGP03-ZO-02 Qualification and Operations of Cranes 02 06/27/86

(*)ll. PGP03-ZO-03 Disconnect and Jumper 01 07/24/86

12. PGP03-ZO-Il Plant Curve Book 00 09/27/85

13. PGP03-ZO-15 Caution Tagging 00 07/11/85

14. PGP03-ZO-18 T.S. Interpretation Control 00 10/05/84

15. PGP03-ZO-22 Post Trip Review 00 11/05/85

16. PGP03-ZR-01 Radiation Protection Program 00 09/10/85

17. PGP03-ZR-06 Personnel Exposure Extension Authorization 00 10/07/85 IS. OTGP02-ZA-01 Operations Department and Startup Interface 02 05/31/85

19. OPRP08-ZC-02 Personnel Decontamination 02 11/18/85 B. General Operating Procedures Procedure Title Rev. Effective Date

(*)l. IPOP03-ZG-01 Plant Heatup from Cold Shutdown 01 06/18/86

(*)2. IP0?03-ZG-02 Plant Heatup 340 F to No Load 01 01/24/86

3. IPOP03-ZG-03 Secondary Plant Startup 01 01/31/86

(*)4. IPOP03-ZG-04 Reactor Startup 01 03/18/86

5. IPOP03-ZG-05 Plant Startup 00 02/07/86

6. IPOP03-ZG-06 Plant Shutdown 35% to Hot Standby 00 03/10/86

7. IPOP03-ZG-07 Plant Cooldown 00 Not Approved

8. IPOP03-ZG-08 Power Operations 01 01/31/86 C. Engineering Procedure Procedure Title Rev. Effective Date

1. OPEP02-ZG-08 ECP Calculation 00 08/23/85

(+)2. IPEP04-ZL-01 Initial Core Loading Pre-requisites 00 08/02/85

(+)3. IPEP04-ZL-10 Initial Core Loading 00 10/23/84

• Revision to previous reference material

+New reference material

• ATTACHMENT ST44L AE > ?3b PAGE 4 OFJ' 8/27/86~

, D. Emergency Operating Procedures Procedure Title Rev. Effective Date

1. IPOP05-E0-E000 Reactor Trip or Safety Inj ection 00 Not Approved

2. IPOP05-EO-ES00 Rediagnosis 00 Not Approved

3. IPOP05-EO-ES01 Reactor Trip Response 00 Not Approved

4. IPOP05-EO-ES02 Natural Circulation Cooldown 00 Not Approved

5. IPOP05-E0-ES03 Natural Circulation Cooldown With Void In Vessel 00 Not Approved

6. IPOP05-E0-E010 Loss of Reactor or Secondary Coolant 00 Not Approved

7. IPOP05-EO-ESil Safety Injection Termination 00 Not Approved

8. IPOP05-EO-ES12 Post-LOCA Cooldown and De-pressurization 00 Not approved

9. IPOP05-E0-ES13 Transfer to Cold Leg Recircu-lation 00 Not Approved

10. ' POP 05-EO-ES14 Transfer to Hot Leg Recircu-lation 00 Not Approved

11. IPOP05-EO-E020 Faulted Steam Generator Isolation 00 Not Approved

12. IPOP05-E0-E030 Steam Generator Tioe Rupture 00 Not Approved

13. IPOP05-E0-ES31 Post SGTR Coolcown Using Backfill 00 Not Approved

14. IPOP05-EO-ES32 Post SGTR Cooldown Using Blowdown

15. IPOP05-EO-ES33 Post SGTR Cooldown Using Steam Dump 00 Not Approved

16. IPOP05-EO-EC00 Loss of All AC Power 00 Not Approved

17. IPOP05-E0-EC01 Loss of AC Power Recovery Without SI 00 Not Approved

18. IPOP05-EO-EC02 Loss of AC Power Recovery With SI 00 Not Approved

19. IPOP05-E0-ECll Loss of Emergency Coolant Recirculation 00 Not Approved

20. IPOP05-E0-EC12 LOCA Outside Containment 00 Not Approved

21. IPOP05-EO-EC21 Uncontrolled Depressurization l of All SG's 00 Not Approved

22. IPOP05-EO-EC31 SGTR With RCS Subcooled l Recovery Desired 00 Not Approved

23. IPOP05-EO-EC32 SGTR With RCS Saturated

Recovery Desired 00 Not Approved 1

24. IPOP05-E0-EC33 SGTR Without Pressurizer l Pressure Control 00 Not Approved

25. IPOP05-E0-F001 Subcriticality Safety Function Safety Status Tree 00 Not Approved i 26. IPOP05-E0-FRSI Response to ATWS 00 Not Approved j 27. IPOP05-E0-FRS2 Response to Loss of Core

Shutdown 00 Not Approved i 28. IPOP05-EO-F002 Core Cooling Safety Function Status Tree 00 Not Approved

29. IPOP05-EO-FRCl Response to Inadequate Core l Coolinx Function 00 Not Approved i

,~

• Revision to previous reference material

+New reference material i

i'

I

' ATTACHMENT

. ST.HL.AE- /1X ,8/27/86 PAGE.F OF3+

.. 30. IPOP05-EO-FRC2 Response to Degraded Core Cooling 00 Not Approved

31. IPOP05-E0-FRC3 Response to Saturated Core Cooling

32. IPOP05-EO-F003 Heat Sink Safety Function Status Tree 00 Not Approved

33. IPOP05-EO-FRH1 Response to Loss of Secondary Heat Sink 00 Not Approved

34. IPOP05-EO-FRH2 Response to Steam Generator Overpressure 00 Not Approved

35. IPOP05-EO-FRH3 Response to High Steam Gener-ator Level 00 Not Approved

36. IPOPOS-EO-FRH4 Response to Loss of Normal Steam Release Capabilities 00 Not Approved

37. IPOP05-EO-FRHS Response to Steam Generator Lo Level 00 Not Approved

38. IPOP05-E0-F004 Integrity Safety Function Status Tree 00 Not Approved

39. IPOP05-EO-FRP1 Response to Imminent Pres-surized Thermal Shock 00 Not Approved

40. IPOP05-EO-FRP2 Response to Anticipated Pressurized Thermal Shock 00 Not Approved

41. IPOP05-EO-F005 Containment Safety Function Status Tree 00 Not Approved

42. IPOP05-EO-FRZ1 Response to High Containment Pressure 00 Not Approved

43. IPOP05-EO-FRZ2 Response to Containment Flooding 00 Not Approved

44. IPOP05-EO-FRZ3 Response to High Containment ,

Radiation Level 00 Not Approved

45. IPOP05-E0-F006 Inventory Safety Function Status Tree 00 Not Approved

46. IPOP05-EO-FRIl Response to High Pressurizer Level 00 Not Approved

47. IPOP05-E0-FRI2 Response to Low Pressurizer Level 00 Not Approved

48. IPOP05-E0-FRI3 Response to Voids in Reactor Vessel 00 Not Approved E. Abnormal Operating Procedures Procedure Title Rev. Effective Date

(+)l. IPOP04-AC-0003 Loss of Closed-Loop Auxiliary Cooling Water Off-Normal 00 06/02/86

2. IPOP04-AE-0001 Electrical Troubles Main Transformer Off-Normal 01 05/16/86

3. IPOP04-AE-0003 Standby Transformer Off-Normal 01 04/30/86

4. IPOP04-CR-0001 Main Condenser - Loss of Vacuum Off-Normal Procedures 01 03/27/86

(+)S. IPOP04-CV-0001 Malfunction of Reactor Coolant Makeup System 01 05/29/86

(+)6. IPOP04-CV-0002 Loss of Charging 01 06/18/86

(+)7. IPOP04-CV-0003 Emergency Boration 00 06/27/86

• Revision to previous reference material

1. New reference material

ATTACFMAENT

. ST HL AE- /M PAGEo/ OF b' 8/27/86

• (+)8. IPOP04-EW-0001 Loss of Essential Cooling Water 00 06/18/86

(+)9. IPOP04-FH-0001 Accident Involving Spent Fuel in the Reactor Containment Building 01 06/02/86

10. IPOP04-FH-0002 Accident Involving Spent Fuel in the Fuel Handling Building 01 05/20/86

(+)l1. IPOP04-FH-0003 Accident Involving New Fuel in Fuel Handling Building 01 05/21/86

12. IPOP04-FW-0001 Loss of Feedwater Flow or Control 01 05/16/86

(+)l3. IPOP04-IA-0001 Loss of Instrument Air 00 07/31/86

(+)l4. IPOP04-NI-0001 Source Range Nuclear Instru-ment Malfunction 00 07/22/86

(+)15. IPOP04-NI-0002 Intermediate Range Nuclear Instrument Malfunction 00 07/22/86

16. IPOP04-CC-0001 Loss Open-Loop Auxiliary Auxiliary Cooling Water Off-Normal Procedure 01 05/16/86

17. IPOP04-RA-0001 Area High Radiation 00 04/07/86

18. IPOP04-RA-0002 Process and Effluent High Radiation 00 04/07/86

19. IPOP04-RC-0001 High Reactor Coolant System Activity 01 05/16/86

(+)20. IPOP04-RC-0002 Reactor Coolant Pump Off-Normal 01 06/18/86

21. IPOP04-RC-0003 Excessive RCS Leakage 00 05/15/86

(+)22 1 POP 04-RC-0004 Stean Generator Tube Leakage 00 06/18/86

23. IPOPO4-RH-0001 Loss of Residual Heat Removal 01 04/07/86

(+)24. 1 POP 04-RP-0001 Loss of Automatic Pressurizer Pressure Control 01 07/31/86

(*)25. IPOP04-RS-0001 Stuck or Dropped Control Rod 01 06/30/86

(*)26. IPOPO4-RS-0002 Malfunction Rod Control 01 04/07/86

(+)27. IPOPO4-TM-0001 Turbine Load Rejection 01 07/31/86

(+)28. IPOP04-TM-0002 Turbine Vibrations Off-Normal Procedures 00 08/07/86 F. Emergency Plan and Implementing Procedures Procedure Title Rev. Effective Date

1. EPP01-ZA-01 Emergency Classifications 00 03/06/86

2. EPP01-ZA-02 Emergency Direction 01 05/05/86

3. EPP01-ZA-03 Emergency Offsite Notification 00 05/08/86

4. EPP01-ZA-04 Emergency Response 00 03/11/86

5. EPP01-ZA-05 Radiation Controls 00 03/11/86

6. EPP01-ZA-06 Search and Rescue 00 03/11/86

7. EPP01-ZA-08 Dose Calculations 00 05/20/86

8. EPP01-ZA-09 Notification of Unusual Event 00 05/08/86

9. EPP01-ZA-10 Alert, SAE, Emergency 00 05/08/86

10. EPP01-ZA-Il Recovery 00 05/08/86

11. STPEGS Emergency Plan 02 04/29/86

• Revision to previous reference material

+New reference material

ATTACHMENT

. ST-HL AE- NM PAGE4" OFS' 8/27/86

. G. System Operating Procedures Procedure Title Rev. Effective Date

(*)l. POP 2-RC-03 Filling and Venting RCS 00 06/06/86

2. POP 2-P C-04 Operation of RCP's 00 05/15/86

3. POP 2-RH-01 RHR System Operation 01 03/10/86

(*)4. POP 2-CV-01 Makeup to RCS 01 06/18/86

(*)5. POP 2-CV-02 BTRS 01 07/08/86 (Delete)6. POP 2-CV-03 Immediate Boration 01 06/18/86

(*)7. POP 2-CV-04 CVCS Subsystem 01 08/07/86

8. POP 2-CD-01 Condensate System 00 Not Approved

9. POP 2-CR-01 Condenser Air Removal System 01 08/25/86

(*)l0. POP 2-AF-01 Auxiliary Feedwater 01 08/04/86

(*)11. POP 2-AC-01 Closed Loop Auxiliary Cooling Water 01 07/03/86

12. POP 2-CS-01 Containment Spray 01 Not Approved (Delete)l3. POP 2-CW-01 Circulating Water Pumps 01 06/'8/86

14. POP 2-DG-01 Emergency Diesel Generator #11 01 06/13/86

,H . Annunciator Response Procedures Procedure Title Rev. Effective Date

1. IPOP09-AN-0lM2 Annunciator Response (Safety Injection ESF Control Panel 1 00 Not Approved

2. IPOP09-AN-02M2 Annunciator Response (Con-tainment Luilding ESF Control Panel 2) 00 Not Approved

3. IPOP09-AN-02M3 Annunciator Response (CCW and ECW ESF Control Panel 2) 00 Not Approved

4. IPOP09-AN-02M4 Annunciator Response (CCW and ECW ESF Control Panel 2) 00 Not Approved

5. IPOP09-AN-03M2 Annunciator Response (DC and Instrument Powcr ESF Control Panel 3) 00 Not Approved

6. IPOP09-AN-03M3 Annunciator Response (Diesel Generators EbF Control Panel 3) 00 Not Approved

7. IPOP09-AN-04M7 Annunciator Response (Reactor Makeup and CVCS Control Panel 4) 00 Not Approved

8. IPOP09-AN-04M8 Annunciator Response (CVCS and Pressurizer Control Panel 4) 00 Not Approved

9. IPOP09-AN-05M2 Annunciator Response (RCP and RCS Reactor Control Panel 5) 00 Not Approved

10. IPOP09-AN-05M3 Annunciator Response (NI, Rod Control, and SSPS Control Panel 5) 00 Not Approved

11. IPOP09-AN-5M23 Annunciator Response (Protec-tion Status Contrcl Panel 5) 00 Not Approved

12. IPOP09-AN-5M24 Annunciator Response (Permis-sive and Control Interlock Status Control Panel 5) 00 Not Approved

• Revision to previous reference material

+New reference material NOTE: POP 2-CV-03 replaced by POP 04-CV-03 Abnormal Procedure

ATTACHMENT

. ST HL AE NA

+ PAGE 6 0F f 8/27/86

. 13. IPOP09-AN-05M4 Annunciator Response (Reactor Trip SI First Out Control Panel 5) 00 Not Approved

14. IPOP09-AN-06M3 Annunciator Response (SG A&B, AFW ll&l2 and SGFPil Control Fanel 5) 00 Not Approved

15. IPOP09-AN-06M4 Annunciator Response (SG C&D, AFW 13&l4 and SGFP 12&l3 Control Panel 6 00 Not Approved

16. IPOP09-AN-06M5 Annunciator Response (Turbine 4 Trip First Out Control Panel 6) 00 Not Approved

17. IPOP09-AN-07M1 Annunciator Response (Main Generator Control Panel 7) 00 Not Approved

13. I POP 09 -AN-07M3 Annunciator Response (Turbine Generator, Deaerator Control Panel 7) 00 Not Approved i 19. IPOP09-AN-08M3 Annunciator Resposne (Gland Seal, MSR, Heater Drips Control Panel 8) 00 Not Approved

. 20. IPOP09-AN-09M1 Annunciator Respose (Cire Water and Miscellaneous Control Panel 9 00 Not Approved

21. IPOP09-AN-10M1 Annunciator Response (Elec-trical Distribution Control Panel 10) 00 Not Approved

22. IPOP09-AN-10M2 Annunciator Response (Elec-trical Distribution Control Panel 10) 00 Not Approved

23. IPOP09-AN-22M1 Annunciator Response (HVAC Control Panel 22) 00 Not Approved

24. IPOP09-AN-22M2 Annunciator Responce (HVAC Control Panel 22) 00 Not Approved

25. IPOP09-AN-22M3 Annunciator Response (HVAC

, Control Panel 22) 00 Not Approved I. Reactor Theory

1. Neutron Induced Reaction and Reaction Rates

2. Neutron Diffusion / Neutron Behavior ,

3. Neutron Life Cycle

4. Reactivity Variations

5. Neutron Kinetics

' 6. Suberitical Reactor Theory

7. Reactivity and Fuel Temperature Effects

8. MTC and Total Power Defect l 9. Fission Product Poisons

10. Chemical Shim Control

11. Control Rod Reactivity Effects

12. Shutdown Reactivity Considerations

13. Power Distribution

14. Reactor Core Control for Large PWR"s e

• Revision to previous refereace material

)

+New reference material

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

ATTACHMENT

. ST HL AE #80 PAGE 7 OF F 8/27/86

+ J. Systems

1. Refueling

2. Fuel Handling HVAC

3. Equipment and Floor Drains

4. Liquid and Gaseous Waste Processing

5. Radiation Monitoring Part I

6. Radiation Monitoring Part II

7. Radiation Monitoring Part III

8. Steam Generator Feed Pumps and Turbine

9. Main Steam

10. Turbine Gland Seal

11. Extraction Steam /MSR's

12. Feedwater Heaters

13. Condensate System

14. Feedwater

15. Digital Rod Position Indication

16. Rod Control System

17. Steam Generator Level Water Control

18. Reactor Protection

19. Steam Generators

20. Steam Dumps

21. CVCS

22. Reactor Makeup j 23. BTRS

24. Engineered Safety Features

25. RHR

26. Standby Diesel Generator

27. ECCS 28 Containment Spray

. 29. Containment Combustible Gas Control

30. Containment Isolation

31. Auxiliary Steam

32. Fire Protection

33. Service and Instrument Air

-I 34. Circulating Water

35. Open Loop Auxiliary Cooling Water

36. Closed Loop Auxiliary Cooling Water

37. Essential Cooling Water

38. Offsite Electrical Distribution

39. Post-Accident Sampling

40. Steam Generator Blowdown

41. Reactor Containment Building

42. RCB HVAC

43. RCB Chill Water

44. Mechanical Auxiliary Building HVAC

45. Mechanical Auxiliary Building Chill Water

46. Essential Chill Water

47. Technical Support Center HVAC and Chill Water

48. Electrical Auxiliary Building and Control Room Envelope HVAC

49. Non-Class IE Diosel Generators

50. ERFDADS

51. Auxiliary Power Distribution

52. Non-Class 480 Volt

• Revision to previous reference material

+New reference material

ATTACHMENT

. ST HL AE / 75(-

PAGE f OF F e/27/86 o 53. Non-Class DC

54. Non-Class 120 VAC

55. Class IE 4.16 KV, 480 VAC

56. Class IE 125 VDC

57. Class IE 120 VAC

58. Main Condenser Air Removal

59. Main Generator and Exciter

60. Stator Cooling Water

61. Isolated Phase Bus Duct Cooling

62. Generator Hydrogen Gas

63. Generator Seal Oil

64. Main Turbine

65. Turbine Generator Lube Oil

66. Electro-Hydraulic Control

67. RCS

68. Reactor Vessel and Internals

69. RCP's

70. Pressurizer, Pressure Relief Tank and RCDT

71. Pressurizer Pressure and Level Control

72. Temperature Monitoring

73. Component Cooling Water

74. Excore Nuclear Instruments

75. Incore Nuclear Instruments K. General Physics Heat Transfer and Fluid Flow L. Health Physics Handout M. Chemistry Handout N. Transient and Accident Analysis, Volumes I and II

0. Mitigating Core Damage P. Piping and Instrument Diagrams Q. Technical Specifications - January 1986 i

i i

i

• Revision to previous reference material

+New reference material