ML17299A614
| ML17299A614 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/19/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-33526-EEVB, TAC-57419, NUDOCS 8509240183 | |
| Download: ML17299A614 (6) | |
Text
I REGULATOR'INFORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR; 8509200183.
DOC ~ DATE: 85/09/19 NOTARIZED:
NO DOCKET FACIL:STN~50"529 Palo Verde Nuclear Stations Unit 2< Arizona Publi 05000529 AUTH",gAME AUTHOR AFFILIATION VAN BRUNTgE,E, Ar,izona Nucle'ar Power Project (formerly Arizona Public Serv RECIP ~ NAME'ECIPIENT AFFILIATION KNIGHTONe G e H ~
Licensing Branch 3
SUBJECT; Submits addi i nfo re measured flows for spray pond nozzles L summary of temps in essential cooling. water sys flow~per 850820 requests DISTRIBUTION CODE:
B001D COPIES RECEIVED:LTR T'ITLE': Licensing Submittal:
PSAR/FSAR Amdts L
NOTES:Standardized plant ~
8 dischar'ge, pressures analysis confirmi,ng assuming.
max bypass Related C rrespondence-05000529 INTERNAL:
RECIPIENT IO CODE/NAME<
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NRA/OSI/ICSB 16 NRR/DSI/PSB 19 NRA/DS I /RSB 23<
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Arizona Nuclear Power Project P.O. 8OX 52034
~
PHOENIX, ARIZONA85072-2034 Director of Nuclear Reactor Regulation Mr. George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 September 19, 1985 ANPP-33526-EEVB/WFg/PGN
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No.
STN 50-529 Reexamination of Diesel Generator Cooling and Essential Cooling Water Systems on PVNGS Unit 2 File:
85-056-026.
85-004-419.06
Reference:
(1)
(2) 1 Letter from E.
E.
Van Brunt, Jr.,
- ANPP, to G.
W. Knighton,
- NRC, dated May 30, 1985 (ANPP-32744);
Subject:
Proposed Reexamination Scope.
Telecon between E.
A. Licitra (NRC),
D.
E.
Sachs (APS),
N. C. Hallas (APS),
and P.
G.
Nelson (APS),
dated August 20, 1985;
Subject:
Unit 2 Spray Ponds.
Dear Mr. Knighton:
Per the Reference (1) letter, APS committed to perform visual examination of two heat exchangers and accessible piping in the spray ponds system of PVNGS Unit 2.
The examinations were required to determine if corrosion (including microbiologically induced corrosion (MIC)) or stress corrosion cracking had occurred.
On June 28,
- 1985, PVNGS Unit 2 heat exchangers 2M-EWA-E01 (essential cooling water) and 2M-DGA-E05 (diesel jacket water) were opened and visually examined, including borescope examinations of the inside of several tubes.
No evidence of MIC or stress corrosion cracking was observed.
There were a few small rust spots at pinhole defects in the heat exchanger channel head epoxy lining.
The lining was in excellent overall condition, well bonded, and with no evidence of delamination.
Additional information was requested by E.
A. Licitra in the Reference (2) telecon.
This information was to include measured flows and discharge pressures for the Unit 2 spray pond nozzles and a
summary of the analysis
- confirming the temperatures in the ECWS assuming maximum bypass flow.
85P92+Qi83 85o90095~9 pgg
@DOCH, 0 A
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Mr. George W. Knighton Palo Verde Nuclear Generating Station Unit 2 Reexamination of Diesel Generator Cooling and Essential Cooling Water Systems on PVNGS Unit 2 Page Two Unit 2 measured flow rates and pump and nozzle discharge pressures of the ESP system are:
Pump discharge pressure Flow rate Nozzle discharge pressure A Train B Train 54 psig 53 psig 17,600 GPM 17,500 GPM 7.4 psig 7.5 psig The nozzle discharge pressure and flow rate for the A Train are unchanged from data taken on May 3, 1985.
The above values may be compared with the design flow rates and nozzle discharge values of 16,900 GPM and 7.0
- PSIG, respectively.
Unit 1 corresponding values are:
Pump discharge pressure Flow rate Nozzle discharge pressure A Train 50 psig 180100 GPM 8.0 psig B Train 50 psig 18,300 GPM 8.1 psig A review of the manufacturer's pump curves shows that the characteristic curves for both Unit 2 pumps demonstrate higher pressure and lower flows in the 17,000 to 19,000 GPM ranges than the Unit 1 pumps.
This and differences in as-built system resistances explains the difference between the Unit 1 and, Unit 2 measured values.
A calculation was performed by Bechtel to analyze the effects of bypass flow.
This calculation is applicable to all three Palo Verde units.
It shows that with a leakage flow of 800
- GPM, the essential cooling water heat exchanger outlet water temperature (to the shutdown cooling heat exchanger) remains below 125'F.
The actual calculated value is 124.6'F.
Please contact Mr. William F. guinn of my staff of you have any questions.
Very truly yours, ZEU~
/~g Executive Vice President Project Director EEVB/WFg/PGN/dim cc:
R.
P.
Zimmerman E. A. Licitra M. C. Ley A. C. Gehr
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