View source for 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

{{Adams
| number = ML20215B164
| issue date = 08/27/1986
| title = Forwards Updated List of Ref Matls Applicable for 861113 Written Reactor Operator & Senior Operator Licensing Exams, Per 860811 Request.Related Correspondence
| author name = Wisenburg M
| author affiliation = HOUSTON LIGHTING &amp; POWER CO.
| addressee name = Gagliardo G, Gagliardo J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000498, 05000499
| license number = 
| contact person = 
| case reference number = CON-#486-0572, CON-#486-572
| document report number = OL, ST-HL-AE-1736, NUDOCS 8610060388
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 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:
UP/'  f &-
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
     #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}}