ML17297A784
| ML17297A784 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/01/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| ANPP-18813-JMA, NUDOCS 8109080089 | |
| Download: ML17297A784 (10) | |
Text
REGUI.A Y INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION>> NSRi810 FACILCSTN~SO 528 STN 50 529 STN 50 530 AUTH~,NAME'AN BRUNTr Els E' REC IP ~ iVAMEI TEDESCO R,f.t, 9080089 DOC ~ OATEN'. 81/09/Oi NOTARIZED; YES D>> ¹ Palo Verde Nuclear StationP Unit lr Arizona Publi 0
Palo Ve'r dei Nucle'ar>> Stations Unit 2r, Ar)zona Publi 05000529.
Palo Vei'de Nuclear Station<
Unit 3r Arizona Publi 05000530 AUTHOR'FF ILIAT'ION Arizona Public S'er vice Co ~
RKC'IPIKNT AFFIL>>IATION Assistant" Dire'ctor>> for Licensing SUBJECT!: For wards response to opeh Item 32'r om Containmenti Sys Branch>> independentl design reView. Marked up FSAR Page(
6' 2 '
7 re SPRACO nozzles used in containment spray sys encl,Ihfo will be incorporated in future FSAR amehd.
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P.o. BOX 21666 PHOENIX, ARIZONA85036 September 1,
1981 ANPP-18813-JMA/KWG Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
+i~'b) /
Subject:
Palo Verde Nuclear Generating Station (PUNGS) Units 1, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
81-056-026 G.l.10
Reference:
Letter from E.
E. Van Brunt, Jr. to R. L. Tedesco ANPP-18669 dated August 17, 1981
Subject:
Containment Systems Open Items
Dear Mr. Tedesco:
Please find attached, our response to open item No. 32 from the Contain-ment Systems Independent Design Review.
Also attached is a marked-u'p copy of the PVNGS FSAR, page 6.2.2-7, which addresses concerns regarding the SPRACO nozzles used in our containment spray system.
This information will be incorporated in a future FSAR amendment.
As a result of continued discussion with Energy Incorporated, APS has begun the process of adding ASME III, Class 2 isolation valves to the main steam drain valve lines.
These isolation valves will be as close as is practical to the containment building, fail closed, close on MSIS and have control room indication.
This modification will also be reflected in a future FSAR amendment.
If you have any questions, please contact me.
Very truly your E. E. Van Brunt, Jr.
APS Vice President, Nuclear Projects ANPP Project Director EEVBJr/KWG/bj cc:
J. Kerrigan (w/a)
P. Hourihan. (w/a)
A. C. Gehr (w/a) 8109080089 810901 PDR ADOCK 05000528 A
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ACTION //32 Examine and resolve the possibility of hydrogen accumulations of higher concentration in closed regions of the containment, particularly in the reactor drain tank room and elevator shaft.
(p. 182)
RESPONSE
A review of the possible hydrogen sources i'n the regions identified demonstrated that tne only credible post LOCA source would be radiolysis of the water in the compartment.
To determine the hydrogen concentrations anticipated in these compartments following the postulated
- accident, the radiolysis sources from the contain-ment sump water (l.lxlO ft. ) was proportioned to the volume of water 5
.3 within each compartment (3300 ft.
for the RDT room and 630 ft.
for the 3
elevator shaft).
This factor was then used to determine the mass of hydrogen expected to be generated as a function of time in each compartment.
Under the worst case conditions, the elevator shaft always remains at a
'r concentration below the 4.0 volume percent limit.
Even at the end of a 30 day period, assuming a zero removal rate, the concentration only reaches 3.2 volume percent.
The RDT room will reach the 4.0 volume percent level approximately 3.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the postulated accident.
The only potential sources of electrical ignition in the room are 3 incandescent, vaporproof lights which are not "spark producing. "
Failure of the RDT rupture disk at this
/
STATE OF ARIZONA
)
) st COUNTY OF MARICOPA)
I, Edwin E. Van Brunt, Jr., represent: that I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
~ - ~~
. n~
Edwin E. Van Brunt, J '.
Sworn to before me this'ay of 1981.
otary Public My Commission expires:
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Page 2
late a time in the postulated accident scenario (i.e., following 3.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
is not a credible event.
The following precautions are recommended while performing pose-LOCA activities:
1.
Power should not be applied to the elevator until the shaft has been adequately ventilated and the shaft sampled for hydrogen.
2.
The RDT room also should be ventilated to assure that a safe atmos-phere is reached prior to entry.
Activities which could possibly cause ignition should be restricted until the compar'tment atmosphere is shown to be habitable.
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