TXX-7066, Final Deficiency Rept CP-86-81 Re Calculations for balance-of-plant safety-related Instrument Setpoints. Initially Reported on 871107.S&W Concluded Condition Has No Safety Significance.New Calculations Being Performed
| ML20238C772 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/23/1987 |
| From: | Counsil W, John Marshall TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-86-81, TXX-7066, NUDOCS 8712310206 | |
| Download: ML20238C772 (2) | |
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MM Log # TXX-7066 h
File # 10110
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907.6 Ref. # 10CFR50.55(e)
MfELEC7RIC 1
December 23, 1987 William G. Counsil' faccurne Usce Presnier l
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 B0P SAFETY-RELATED INSTRUMENT SET POINTS SDAR: CP-86-81 (FINAL REPORT)
Gentlemen:
On November 7,1986, we verbally notified your Mr. T. Westerman of a deficiency involving the calculations for B0P safety-related instrument setpoints, indicating that omissions of required data or use of incorrect information occurred in performing the calculations required per Regulatory Guide 1.105, Rev. 2.
Our latest interim report was logged TXX-6982, dated November 18, 1987. We have concluded that.this issue is not reportable under the provisions of 10CFR50.55(e).
Stone and Webster Engineering Corporation (SWEC) has reviewed the B0P instrument setpoint calculations affected by this issue and concluded the condition has no safety significance.
SWEC is in the process of performing new calculations using revised methodology to supercede the previous Balance of Plant (B0P) setpoint calculations.
To date, forty-four'(44) of the approximately fifty-four (54) new calculations have been' completed, with no significant deficiencies resulting.
Based on the satisfactory results of the review of the original B0P setpoint l
calculations as well as the population of new calculations already redone, no I
significant deficiencies are anticipated in the remaining calculations.
If any deficiency is found during the completion of the remaining new calculations, the existing CPSES deficiency reporting' program will be utilized to document and determine the safety significance of the condition.
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'8712310206 871223
{DR ADOCK 05000445 i0 Nonh Olive Street LB lil Dallas, Texas 7201 a
i TXX-7066 December 23, 1987 Page 2 of 2 Records supporting these conclusions are available for review by your inspectors at the CPSES plant site.
Very truly yours, 0.6
%n W. G.
ounsil By:
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J.~S. Marshall Supervisor, Generic Licensing RDD/grr c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)
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