ML20195J207

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Final Deficiency Rept CP-88-17 Re Control Room Habitability. Initially Reported on 880115.New Calculations Developed for Control Room Habitability & Existing Control Control Room Intake Radiation Monitors Upgraded
ML20195J207
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 01/18/1988
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-88-17, TXX-88102, NUDOCS 8801260476
Download: ML20195J207 (2)


Text

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# 'U""UU'00I'I 1UELECTRIC January 18, 1988 wmi m c. counw Lteturne Vke Preskient V. S. Nuclear Regulatory Commission

-Attn:

Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET HOS. 50-445 AND 50-446 CONTROL ROOM HABITABILITY SDAR: CP-88-17 (FINAL REPORT)

Gentlemen:

On January 15, 1988, we verbally notified your Mr. R. F. Warnick of a potentially reportable item involving control room habitability following radiological accidents.

Specifically, the radiation doses to control room operators for some radiological accidents could exceed the limits of 10CFR50, Appendix A, G0C-19. We have concluded this issue is reportable under the provisions of 10CFR50.55(e).

The required information follows.

DESCRIPTION OF DEFICIENCY Ouring recent validation efforts, it was noted that the control room habitability systems had not been analyzed for all radiological accidents.

Further evaluation of control room habitability following the additional radiological accidents resulted in radiation doses to the control room operators which exceed the limits of 10CFR50, Appendix A, GDC-19.

The cause of this deficiency is attributed to an inadequate analysis of the control room habitability systems for all postulated radiological accidents.

This issue is limited to control room habitability following postulated radiological accidents.

SAFETY IMPLICATIONS in the event this condition had remained uncorrected, the radiation doses to the control room operators resulting from a fuel handling accident or a radioactive gaseous waste tank rupture could exceed the limits of 10CFR50, Appendix A, GDC-19.

This issue represents a deficiency in that the design does not conform to the criteria and bases stated in the FSAR.

8801260476 880118 PDR ADOCK 05000445 q

S DCD 4n0 krth Olng Street LB81 Dallas. Tr.tas 73201 l

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TXX-88102 January 18, 1988 Page 2 of 2 CORRECTIVE ACTIONS The corrective actions for this issue consist of:

1.

Development of new calculations for the control room habitability following radiological accidents to validate that radiation doses to the control room operators are within the limits of 10CFR50, Appendix A, GDC-19.

2.

Upgrading the existing control room intake radiation monitors to safety-related Class lE requirements.

3.

Upgrading the power cables and control cables associated with the existing monitors to safety-related Class lE requirements.

4.

Installations of two additional safety-related Class lE radiation monitors, one in each control room intake, with power and control cables similar to the above.

Completion of these corrective actions will be accomplished no later than October 23, 1988.

In order to prevent recurrence of this issue, the design criteria have been documented in the Control Room Habitability Design Basis Document (DBD-ME-003) which was used as a basis for the design.

Very truly yours, k

A&M W. G. Counsil BSD/grr c-Mr. R. D. Martin, Region IV Resident inspectors CPSES (3)