ML17298B101
| ML17298B101 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/12/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-29947-EEVB, NUDOCS 8407180193 | |
| Download: ML17298B101 (6) | |
Text
REGULATOf INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8407180193 DOC ~ DATE>> 84/07/12 NOTARIZED:
NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Stations Unit 1F Ar3zona Publi 05000528 STN-50-529 Palo Verde Nuclear Stations Unit 2F Arizona Publi 05000529 STN 50-530 Palo Verde Nuclear Stations Unit 3F Arizona Publi 05000530 AUTH,NAME AUTHOR AFFILIATION, VAN BRUNTEE,ED Arizona Public Service Co.,
RECIP,NAME.
REClPIENT AFFILIATION KNIGHTONrG>>
Licensing Branch 3
SUBJECT:
Clarifies preliminary RCS demonstration test description.
Cond)tion for 200 h steady staterun test changed to 565 F
to iincorporate other plant testing during same period.
DISTRIBUTION CODE:
8001S COPIES RECEIVED-'LTR Q ENCL, SIZE:
Q TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8 Related Correspondence NOTES:Standardized plant.
Standardized plant.
Standardized plant.
05000528 05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1
NRP LB3 BC 1
LICITRAEE 01 COPIES LTTR ENC 1
1 INTERNAL: ELD/HDS3 IE/DEPER/EPB 36 IE/DQASIP/QAB21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DS I /PSB 19 NRR/DS I/RSB 23 RGN5 EXTERNAL>>
ACRS 41.
DMB/DSS (AMDTS)
LPDR 03 NSIC 05 1
3 1
1 2
1 1
1 1
1 1
1 1
3 IE F ILE
'E/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB
?8 NRR/DE/MTEB 17 NRR/DE/SGEB 25*
NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12 N
AB 2?
04 RM/DDAMI/MID BNL(AMDTS ONLY)
FEMA REP DIV 39 NRC PDR 02 NTIS 1-1 1
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIREO:
LTTR 55 ENCL
0 II e
n P
) I A.
~r
,i n
II
Arizona Public Service Company ANPP-29947-EEVBJr/THQ July 12, 1984 Director of Nuclear Reactor Regulation Attention:
Mr. George Knighton, Chief Licensing Branch No.
3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3
Docket Nos.
STN 50-528/529/530 File:
84-056-026 G.1.01.10
Reference:
Letter from E. E.
Van Brunt,.Jr.,
APS, to G.
W. Knighton,
- NRC, dated February 24,
- 1984, ANPP-28939.
Subject:
Preliminary PVNGS Reactor Coolant System Demonstration Test Description.
Dear Mr. Knighton:
During a telephone conversation with Messrs. Licitra and Jackson of your staff, clarification to the referenced letter was discussed.
The clarification is discussed below and is provided for your information.
The referenced letter provided details of our Unit 1 Demonstration Test.
We indicated that one portion of the test would be a 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, 565'2 5'F, steady state run with all Four Reactor Coolant Pumps.
Since then, (in development of our overall test plan and details), it has become necessary to change the Reactor Coolant System (RCS) conditions during the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> run.
The 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> run will now be with. the RCS at a temperature plateau of 565'F with a number of temperature transients induced during the test.
Prior to the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> period is a 550'F steady state run.
The 550'lateau is to accommodate some instrumentation temperature limita-tions.
The 565'lateau will incorporate other plant testing to be performed during this period (i.e.
Steam Bypass Valve Testing, Main Steam Isolation Valve Testing, Atmospheric Steam Dump Testing, etc.).
All Four Reactor Coolant Pumps will remain running during this 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> period.
, 8407180i'P3 8407i2
'DR ADOCK 05000528 A'DR'o
I,
Mr. George Knighton
" Preliminary PVNGS Reactor Coolant System Demonstration, Test Description ANPP-29947 Page 2
This does not lessen the severity of the condition on the Reactor Coolant Pumps during the overall test.
The Reactor Coolant Pumps total hours and each individual pumps runout flow running time will remain the same as originally planned.
Please contact me if you have any questions on this matter.
Very truly
- ours, QU E. E.
Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVBJr/TFQ/mb cc:
E. A. Licitra A. C. Gehr
I I