ST-HL-AE-1671, Submits Response to NRC 860307 Request for Addl Info Re Generic Ltr 83-28,Sections 1.2,4.2.3/4 & 4.3.List of post- Trip Review Parameters Encl

Submits Response to NRC 860307 Request for Addl Info Re Generic Ltr 83-28,Sections 1.2,4.2.3/4 & 4.3.List of post- Trip Review Parameters Encl

ML20195E477
Person / Time
Site:	South Texas
Issue date:	05/30/1986
From:	Wisenburg M HOUSTON LIGHTING & POWER CO.
To:	Thompson H Office of Nuclear Reactor Regulation
References
CON-#286-439 GL-83-28, OL, ST-HL-AE-1671, NUDOCS 8606090097
Download: ML20195E477 (5)

Text

---

The Light Company ii.,iisi ugiiiing m>.- m m,x im ii-si.,n.wxas moi oimumii May 30, 1986 ST-HL-AE-1671 File No.: G3.8 Mr. Hugh L. Thompson, Jr., Director Division of PWR Licensing - A Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Response to Request for Additional Information Regarding NRC Generic Letter 83-28

Dear Mr. Thompson:

This letter is in response to the NRC request for additional information regarding resolution of the concerns of Generic Letter 83-28 as they apply to the South Texas Project (STP). The request was conveyed by letter dated March 7, 1986, from N. P. Kadambi which listed the status of the various sections of the Generic Letter as they applied to STP. The information provided herein is intended to enable closure of the open items identified on the list.

Section 1.2 Post-Trip Review - Data and Information Capability

_ Sufficient analog and digital parameters are not recorded for use in post-trip review.

Data retention procedures, as described in the submittal, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.

Response

A list of the major parameters monitored is provided with the attached table.

Note that control rod position is not included as a parameter. Required sequence information on rod insertion is derived from the reactor trip breaker position inputs.

Additional rod position information can be obtained from the long-term data storage files provided by the Proteus and ERFDADS computer systems.

8606090097 860530 PDR ADOCK 05000498 A PDR L3/NRC/ac )f

• Ilouston Lighting & Power Company ST-HL-AE-1671 File No.: G3.8 Page 2 Retention of the Post-Trip Review Report for the life of the plant is required by procedure. The report will be retrievable through the Operations Document Control Center.

Section 4.2.3/ Reactor Trip System Reliability (Preventive Maintenance 4.2.4 and Surveillance Program for Reactor Trip Breakers)

Resolution of life cycle testing is contingent upon submittal of the WOG report.

Response

WCAP-10835, " Report of the DS-416 Reactor Trip Breaker Undervoltage and Shunt Trip Attachments Life Cycle Tests,"

was submitted to the Equipment Qualification Branch of the NRC by the Westinghouse Owners Group via OG-167.

Section 4.3 Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment for Westinahouse and B&W Plants)

" Action 11" has been added to Table 3.3-1 of the STP Technical Specifications, but was not referenced in Item No. 19.

Response

" Action 11" is referenced in Item 19 of Table 3.3-1.

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

Veryt%yyours, M. R. l?isenburg Manager , Nuclear Licensing PLW/1jm

Attachment:

Table 1 - Post-Trip Review Parameters L3/NRC/ac

Houston Lighting & Power Company ST-HL-AE-1671 File No.: G3.8 Page 2 cc:

Robert D. Martin Brian E. Berwick, Esquire Regional Administrator, Region IV Assistant Attorney General for Nuclear Regulatory Commission the State of Texas 611 Ryan Plaza Drive, Suite 1000 P.O. Box 12548, Capitol Station Arlington, TX 76011 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 Attnrney c/o U.S. Nuclear Regulatory Office of tne 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 J.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 j H.L. Peterson/G. Pokorny Office of the Secretary City of Austin U.S. Nuclear Regulatory Commission I 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

TABLE 1 POST-TRIP REVIEW PARAMETERS PROTEUS PROTEUS ERFDADS ERFDADS SOE PRE / POST PRE / POST TRANSIENT PARAMETER LOG TRIP LOG TRIP LOG LOG

1. Reactor Trip X X X X ESF Initiations X Manual Initiations X

2. Safety Injection Actuation X ESF Initiations X Manual Initiations X

3. Containment Isolation X Containment Vent. Isol. X

4. Turbine Trip X X X X ESF Initiations X Manual Initiations X

5. Generator Trip X X

6. Neutron Flux Source Range X X Intermediate Range X X Power Range X X

7. Containment Pressure X X

8. Containment Radiation RCB ATM NG Noble Gas X RCB ATM Particulate X

9. Containment Sump Level X

10. Primary System Pressure PZR. Press X X RCS Press X

11. Primary System temperature OPDT (per Loop) X OTDT (per Loop) X Compensated T-cold (per Loop) X Delta-T (per Loop) X T-Average (per Loop) X Wide Range T-Hot (per Loop) X Wide Range T-Cold (per Loop) X W6B/dw1/fx

TABLE 1 POST-TRIP REVIEW PARAMETERS PROTEUS PROTEUS ERFDADS ERFDADS SOE PRE / POST PRE / POST TRANSIENT PARAMETER LOG TRIP LOG TRIP LOG LOG

12. Pressurizer Level X X

13. Reactor Coolant Pump Status X

14. Primary System Flow Per Loop X X

15. Safety Injection System HHSI Pump Flow _

X HHSI & LHSI Pump Status X HHSI Pump Discharge Pressure X

16. MSIV Position X

17. Steam Generators Pressure (per SG) X X Level (W/R & N/R) (per SEG) X X

18. Feedwater System Flow (per TRN) X Pump Status (per TRN) X X Booster Pump Status (per TRN) X

19. Steam Flow X

20. Auxiliary Feedwater System Flow (per TRN) X Pump Discharge Press (per TRN) X Pump Status (per TRN) X

21. Electrical Systems 13.8 KV Status X 13.8 KV Bus Voltages X ESF Load Sequencers ._ X ESF Diesel Generators X X 125 VDC Bus Voltages X

22. PORY Position SG PORV X PZR PORV X W6B/dwl/fx

- _ _ - .