TXX-7082, Final Deficiency Rept CP-87-87 Re Chemical Vol & Control Sys Relief Valve Piping.Initially Reported 870903.Valve Will Be Relocated in Order to Comply W/Asme Boiler & Pressure Valve Code Requirements
| ML20237D952 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/14/1987 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-87-87, TXX-7082, NUDOCS 8712280052 | |
| Download: ML20237D952 (2) | |
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e too # 1XX-7082 M
Tile # 10110 llllllll" ':lllllll:
909.3 Ref. # 10tFR50.55(")
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1UELECTRIC December 14, 1987 WWien G. Counxil Erwmne V,w Penniem V. 5. Nuclear Regulatory Con' mission Attn: Document Control Dec.k Washinuton, D. C.
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5pNLC h EOMAIKill PEAK S1EAM ELECTRIC STATION (CPSES)
DOCLET N05. 50-445 AND 50-446 CVCS RElILF VALVE PIPlHG 5DAR: CP-87-87 (FINAL REPORT)
Gentlemen:
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On September 3, 1987, we verbally notified your fir. H. S. Phillips of a l
possible t eportable deficiency involving the potential overpressurirat ion of the Chemical Volume and Control System (CVCS) letdown line due to the pipinq configuration of the relief valve. Our latest report was logged Txt-loll, dated flovember 30, 1987.
After further evaluation we have concluded this issue is not reportable under the provisions of 100fR50.55(e).
A design deficiency report (TODR ME-86-375, dated May 19,1986) and subseepient Westinghouse evaluation (WPI-8744, dated February 10,1987)'disclosedthatth"
<lesign pressure of the CVCS letdown line would be exceeded by as much as 21.',
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percent when a relief valve (1-8117) is relieving with isolation valves of the thiee letdown orifices open.
This overpressure could cause a high eneigy 1ine lo eal (illt U) out side the containment and release of radioactivity at ihe he val location.
l The possible iuptuie of the section of piping in the CVCS letdown line whirh l
is pintected by the relief valve has been analyzed for offsite radiological dose elf ects under the HELD-out side-containment analysis program SPI'-3'.f,. I l
(CPLE5 F5AR, Section 15.6.2, as amended).
The release would be isolable; lyowever, the results of the llELD analysis for this section of pipina (ii not isolated) indicate the release of radioactivity wonld be well within the design basis.
No credit is talen for this pip'ing ielativo to t he mit igat ion I
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6 K 05000445 Il &
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Jorth Ohve Street I.B 81 Dalkn. Texas 75201 J
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lxx-7082 December 14, 1987.
Page 2 of 2 of the c' consequences of a DBA-LOCA or safe shutdown of the plant. The valve will be relocated in order to comply with ASME B&PV Code requirements, y
however, the Code discrepancy, if uncorrected, would not have adversely affected safe operations of the plant.
i Very truly yours,
//
($4 W. G. Counsil I
MCP/grr c - Mr. R. D. Marti:, Region IV t
Resident inspe. tors, CP5ES (3) 1 I
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