ML17305A640
| ML17305A640 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/26/1990 |
| From: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-B-56, REF-GTECI-EL, RTR-REGGD-01.055, RTR-REGGD-1.055, TASK-B-56, TASK-OR 161-03025-WFC-G, 161-3025-WFC-G, NUDOCS 9004090338 | |
| Download: ML17305A640 (8) | |
Text
ACCELERATED DISTRIBUTION DEMONSTPA.TION SYSTEM 0
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9004090338 DOC.DATE: 90/03/26 NOTARIZED: NO DOCKET's FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.
Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides addi clarification to util 890414 response re station blackout.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES: Standardized plant.
Standardized plant.
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RECIPIENT ID CODE/NAME PD5 LA PETERSON,S.
INTERNAL: ACRS NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC LF B FI 01 EXTERNAL: LPDR NSIC NOTES:
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RECIPIENT ID CODE/NAME PD5 PD NRR/DET/ECMB 9H NRR/DST 'E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WAS'ONTACTTHE,DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 28 ENCL 26-A D
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Arizona Public Service Company P.O. BOX 53999
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PHOENIX, ARIZONA95072<999 WILLIAMF. CONWAY EXECUTIVEVICEPRESIDENT NUCI.EAII 161-03025-WFC/GS March 26, 1990 Docket Nos.
STN 50-528/529/530 Document Control Desk U.
S. Nuclear Regulatory Commission Mail Station Pl-37 Washington, D.
C.
20555
References:
(1)
Letter to the U.
S.
- NRC, 161-01842-DBK/GS dated April 14, 1989 (2)
Letter from Nuclear Management and Resources Council (NUMARC) to NUMARC Board of Directors dated January 4,
1990
Dear Sirs:
Sub) ect:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2',
and 3
Submittal of Supplemental Information on Station Blackout File:
90-056-026; 90-014-000 The purpose of this letter is to provide additional clarification of the response submitted by Arizona Public Service (APS) in Reference 1
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This clarification letter is being transmitted to the NRC at the request of NUMARC in Reference (2).
APS'as reviewed the original response (Reference
- 1) to the Station Blackout
- Rule, 10 CFR 50.63, and supporting documentation to conclude the following:
(a)
The Reference (1) submittal has been based on the use of NUMARC 87-00 document, "Guidelines and Technical Basis for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors,"
except where Regulatory Guide 1.155 takes precedence.
(b)
Implementation of NUMARC87-00 document at PVNGS is consistent with the supplemental guidance provided as attachments to Reference (2).
(c)
Deviations from the accepted NUMARC 87-00 guidance have been clearly indicated in the Reference (1) submittal except as noted in the attachment to this letter for the purpose of clarification.
9004090338 900326 PDR ADOCK 05000528 I
PDC oot
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Document Control Desk U.
S. Nuclear Regulatory Commission Page 2
161-03025-WFC/GS March 26, 1990 (d)
The Emergency Diesel Generator (EDG) target reliability for PVNGS is.0.95 as indicated in Reference (1) submittal; the present PVNGS EDG reli'ability program contains elements consistent with Regulatory Guide 1.155.
- However, APS recognizes the fact that the program may be modified depending on the resolution of Generic Issue B-56 (EDG Reliability).
If you have any further questions or require any additional information, please contact Hr. A. C. Rogers of my staff at (602) 340-4041.
Sincerely, WFC/GS/jle cc:
T. L. Chan S.
R. Peterson J.
B. Martin D. H.
Coe A. H. Gutterman A. C. Gehr (all w/attachment)
I tg
Attachment Section A.l.d of the Attachment to Reference 1
It was stated in Reference (11 submittal that Section 3.2.1, Part IB ~ae 3-d of NUMARC 87-00 indicates ESW group of 2.
The page number quoted should be 3-6 instead of 3-4.
This editorial change has no impact on the four-hour coping category for PVNGS.
Section 4.a of the Attachment to Reference 1
In assessing the effects of loss of ventilation for the Auxiliary Feedwater (AFW) pump
- room, a plant specific computer
- code, which is similar to NUMARC 87-00 methodology was used in calculating the AFW pump room temperature as 150'.
A subsequent testing of the computer code against NUMARC 87-00 methodology produced identical results.
The evaluation included the effects of design basis steam leakage during station blackout event.
This additional heat source was not taken into account in NUMARC 87-00 document.
Based on experience with the PVNGS AFW
- pump, the results which consider steam leakage is more credible.
The AFW pump room temperature would have been below 120' if this effect of steam leakage were not consi'dered in the evaluation.
Incorporation of steam leakage which is not required in the NUMARC 87-00 methodology resulted in a more realistic result for PVNGS.
Section 6 of the Attachment to Reference 1
The adequacy of Condensate Storage Tank (CST) inventory during a four hour station blackout period was demonstrated using the integrated auxiliary feedwater usage data derived from a PVNGS natural circulation study, which is a plant specific analysis rather than the NUMARC 87-00 methodology.
Subsequent calculation performed using NUMARC 87-00 methodology confirmed the results obtained from the plant specific study.
Both of those methods indicate that the expected rates of reactor coolant inventory loss under station blackout conditions do not result in core uncovery in four (4) hours.
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