ML17299A839
| ML17299A839 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/22/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM ANPP-34078-EEVB, NUDOCS 8512050229 | |
| Download: ML17299A839 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEI'I (RIBS)
ACCESSION NBR: 8512050229 DQC. DATE: 85/11/22 NOTARIZED:
NO DOCKET 0 FACIL:BTN-50-529'alo Verde Nuclear Station>
Unit 2i Arizona Publi 05000529 AUTH. NAI'IE AUTHOR AFFILIATION VAN BRUNT'. E.
Arizona Nuclear Potuer Pro Ject (formerly Arizona Public Serv REClP. NAME RECIPIENT AFFILIATION KNIGHTON> G. W Office of Nuclear Reactor Regulationi Director (pre-851125)
SUBJECT:
Provides justification +or interim operation of reactor coolant gas vent sos until entry into Node
- 4. Valve vill be tested prior to Node 4
8c during post-core not functional testing. Exception to commitment re NUREG-0737 II. B. 1 noted.
DISTRIBUTION CODE:
B001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 5 Related Correspondence NOTES: Btandardi zed plant.
05000529 RECIPIENT ID CODE/NANE PWR-B ADTB PWR-B PD7 LA INTERNAL: ACRB 41 ELD/HDB3 IE/DEPER/EPB 36 NRR BWR ADTB NRR PWR-B ADTS NRR/DHFT/HFIB R
R R
EG Rl >/DDAI'II/RIB 04 EXTERNAL 24X Dl'IB/DSB (AIIDTB)
NRC PDR 02 PNL GRUEL R
COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NANE.
PWR-B PD7 PD LICITRA. E 01 ADN/LFNB IE FII E IE/DGAVT/GAB21 NRR PWR-A ADTS NRR ROEi I'I. L NRR/DHFT/NTB NRR/DSRO/RRAB RGN5 BNL(ANDTB ONLY)
LPDR 03 NBIC 05 COPIES LTTR ENCL 1
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TOTAL NUI'IBER QF CQPIEB REQUIRED:
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Arizona Nuclear Power Project P.o. BOX 52034
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PHOENIX, ARIZONA85072-2034 ANPP"34078/EEVB/JKO November 22, 1985 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Project Director PWR Project Directorate II7 Division of Pressurized Water Reactor Licensing B U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2.
Docket No. STN-50-529 Justification for Interim Operation of Reactor Coolant Gas Vent System File: 85-056-026'.l.01.10
Dear Mr. Knighton:
The attachment to this letter is a justification for interim operation of the Reactor Coolant Gas Vent System until initial entry into Mode 4.
A valve in the system was inoperable during pre-core hot functional testing, so we have scheduled to test the valve prior to Mode 4 under the requirements of ASME Section XI test program.
This type of testing will also meet the surveillance requirements of any potential technical specification.
Additionally, we also plan to test the valve during the post-core hot functional testing.
This takes exception to PVNGS commitment concerning NUREG 0737 II.B.1, which is to have the system operable prior to fuel load.
The remainder of the system has been preoperationally tested.
If you have any further questions regarding this matter, please contact Mr.
W. Quinn of my staff.
Very truly yours, Executive Vice President Project Director EEVB/WFQ/JKO/rw Attachment cc: E.
M.
R.
R.
J.
A.
A. Licitra Ley P.
Zimmerman C. Sorenson B. Martin C. Gehr I 85i2050229 85i i22 PDR PDR ADOCK 05000529, 0>1
Attachment 1
JUSTIFICATION FOR INTERIM OPERATION
Valve Number HV108 Description Valve on Train B from the pressurizei in the Reactor Coolant Gas Vent System Projected Completion Prior to initial Mode 4
'History:
During the Reactor Coolant Gas Vent System preoperational
- test, valve HV-108 failed to operate properly.
I't was= written up as a test exception and scheduled for testing per the requirements of the ASME Section XI test program prior to initial Mode 4 entry.
Additional testing under the correct Reactor Coolant System temperature and pressure will be don'e during the post-core hot funtional testing (PCHFZ) phase.
Justification for Interim Operation:
The valve will be tested prior to initial Mode 4 entry. It is not possible to produce non-condensible gases in an accident situation prior to initial criticality.
The valve will be tested per the requirements of ASME Section XI test program prior to initial entry into Mode 4.
Proper Reactor Coolant System temperature and pressure for the testing of the valve will be reached during PCHFT and will be further tested at this time.
This valve is on Train B path.
Should the system be required prior to initial criticality, Train A is available.
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