ML20062G530
| ML20062G530 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/22/1978 |
| From: | Short T OMAHA PUBLIC POWER DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812290176 | |
| Download: ML20062G530 (4) | |
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Omaha Public Power District 1623 HARNEY OMAHA. NteRASMA 68102 TELEPMONE 536 4000 AREA CODE 402 December 22, 1973 Director of :'uclear Reactor Pegulatic",
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4 2eference: Occhet :'c. 50-235
^.e.tlemen:
In respcnce tc a ecnversaticn with members Of ycur staff, the Craha Public Pcver District offers the following information in re-gar
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4 in the talve testing requirements.
It is agreed that these valves shculd be added tc the plan under Categcry C.
Ecvever, relief is requested frc: testing requirements due *c intractical'ty because o f. e s.,.
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-2 An apprcpriate revisicn to the progra.. plan is attached to reflect the above consideraticns.
l Sincerely, I
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e Assister.t General Manager
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cc: Le3ceuf, Lar.b, Leib-/
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l CATECCIU_C VALVr a l
Nonnal Test Exceptio s Feiar val;e Nder Tyre P&ID Narber Incation Position Frecuency to Icp2. dix 2C -
SI-204 Q1ccP
" -E-23866-210-130 F6 NC 10 Ex 2 of 2 SI-196 Orck G-E-23866-210-130 A6 NC 10 Ex 2 cf 2 SI-199 Check CE-E-23866-210-130 C6 NC 10 Ex 2 of 2 SI-202 Oteck G-E-23866-210-130 E6 NC 10 Ex l
2 of 2 SI-205 01eck G-E-23866-210-130 F6 IE 10 Ex 2 of 2 SI-194 Cicck G-E-23866-210-130 B5 NC 10 Ex 2 of 2 SI-197 Geck G-E-23866-210-130 C5 NC IO Ex 2 of 2 SI-200 01eck G, E-23866-210-130 ES NC 10 Ex 2 of 2 SI-203 Check G-E-2 3866-210-130 G5 NC 10 Ex l of 2 2
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AC-354 Pelief gIDR-ll405-M-lG B1 NC Table E W-3510-1 AC-341 Felief dIDR-11405-M-10 Cl NC Table E N-3510-1 AC-4A-IIx Palief Pelief diDR-11405-M-10 B3 NC Table EW-3510-1 7C-48-lix Palief Pelief GIDR-ll405-M-10 B4 1C Table E W-3510-1 AC-8-lix Pelief~
Relief GilDR-ll405-M-10 C4 NC Table E N-3510-1 i
IG-291 Felief GIDR-ll405-M-252 Al NC Table EN-3510-1 SI-175 Oleck G-E-23866-210-130 In IC Ex Ex 2 of 2 91-176 j
Chmk CE-E-23866-210-130 13 UC Ex Ex
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APPENDIX 2C (Continued)
These valves function to provent back-flow through SI-194 These the safety injection pump discharge headers.
195 valves cannot be stroke-tested during cold shutdowns 196 or quarterly during operation because to do so using 19 7 the safety injection system would require introducing 198 cold water into the reactor coolant system causing 199 thermal shock and possibly a reactor excursion.
200 To do so using the chemical volume control system 201 would disrupt charging and letdown flow to the 202 reactor coolant system causing chemical and volume 203 control to the system to be disrupted.
204 205 r
SI-175 These valves serve to provent back-flow from 176 the containment spray headers.
These valves cannot be tested to the open position since to do so could cause spray in containment.
Not stroking the valves poses no safety impact for i
the following reasons:
1.
Adequate heat removal from containment can be achieved during a DBA by use of only one r
containment spray header with three contain-ment spray pumps.
Hence, only one of the check valves is required to open.
2.
The ntainment air filtration and cooling i
syst is fully redundant to the containment spray system.
3.
The containment air filtration and cooling system contains redundant components.
During a DBA, sufficient iodine removal is effectuated with 50% of the system operating and sufficion:
I pressure reduction accomplished with any three air coolers operating.
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