ML17300A779
| ML17300A779 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/13/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 023-02164-JGH-D, 23-2164-JGH-D, DER-84-30, DER-86-25, NUDOCS 8704280280 | |
| Download: ML17300A779 (10) | |
Text
DOCKET 4 05000528 05000529 05000530
SUBJECT:
Revised Deficiency Evaluation Repts DER 84-30 Zc 86-25 Te U-2 diesel generator valves 5
kaman radiation monitors>
respectively. Chanqes to repor+ed info or corrective ac+ions noted.
DISTRIBUTION CODE:
IE27D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: 50. 55(e) Construction Deficiency Report REQULAT INI.OR!'IATI0"~ DISTRIBUTION TEN (R IDS)
"ACCESSION NBR: 8704280280 DOC. DATE: 87/04/13 NOTARIZED:
NO FACIL:STN-50..528 Palo Verde Nuclear Station" Unit li Arizona Pub li STN-50-529 Palo Verde Nuclear Station>=-., Unit 2> Arizona Pub li STN-50-530 Palo Vende Nuclear Station.
Unit 3> Arizona Pub li AUTH. NANE AUTHOR AFFILIATION HAYNESp J. Q;.
Arizona Nuclear Po~~er Prospect (forms rig Ari zona Pub) ic Serv RECIP. NANE RECIPIENT AFFILIATION KIRSCHi D. F.
Reqi on 5i Office of Director NOTES: Standardized plant. N. Davis'!NR: 1Cg.
Standardi zed plant. N. Davis> h!KR: 1Cg.
Standar dized plant. N. Davis. I"RR: 1Cg.
05000528 05000529 05000530 REC IP IENT ID CODE/NANE PD5 LA I. ICITRAiE COPIES LTTR ENCL 1
1 RECIPIENT I D CODE/MANI="
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AEOD/DSP/TPAB NRR/DLPG/GAB I'!RR/DOEA/QCB OQC/HDSl RES SPEISe T NRC PDR 1
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TOTAL NUNBER OF COPIES, REQUIRED:
LT I R 28 ENCL 28
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I
Arizona Nuclear Power Project
. "" A.";.~.-.,
P.O. BOX 52034
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PHOENIX. ARIZONA85072-2034 g
I I' c810r'q y 023-02164-JGH/DRL 4-'pril 13, 1987 U. S. Nuclear Regulatory Commission Region V
1450 Maria Lane Suite 210 Walnut Creek, CA 94596-5368 Attention:
Mr. D. F. Kirsch, Director Division of Reactor Safety'nd Projects Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, 3
Docket Nos. 50-528,
- 529, 530
Subject:
Dear Sir:
Deficiency Evaluation Report Revisions File:
87-006-216 I
In reviewing information and implementing the corrective action to resolve deficiencies identified in Deficiency Evaluation Reports submitted to the NRC, a few changes in the reported information or corrective action being accomplished have been identified.
Attached is a summary description and evaluation of the impact of these changes which may be substantive.
Those changes which are identified and evaluated as not substantive, e.g. typographical errors, have been so noted in our files.
If you have any questions on this matter, please contact W. E. Ide.
Very truly yours, J.
G. Haynes Vice President Nuclear Production JGH/DRL:kp cc:
See Page Two 8704280280 870413 PDR ADOCK 05000528 8
~ 8939Q/1663Q 7/
97
I
023-02164-JGH/DRL April 13, 1987 Page Two Nr. D. F. Kirsch Director DER Revisions cc:
J.
H. Taylor, Directcr Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A. C. Gehr (4141)
R.
P.
Zimmerman (6295)
Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway Suite 1500 Atlanta, Georgia 30339
Attachment Summar of DER Revisions Paelof 2
DER No.
Ori inal Deficienc or Commitment Summar of Chan e
I Im act of Chan e
84-30 Rev.
1 During ASME code documentation review for the U-2 diesel generators, a deficiency was I
identified which showed a lack of supporting documentation for 30 valves which had not been "N"
stamped.
These valves were replaced in all 3 units.
The original review, as identi-I fied in CAR C83-186N, only I
addressed needle valves (30)
I subsequently, during a later I
review to clarify code boundary on the diesel fuel oil day tank it was discovered that an additional 18 valves per unit, globe valves associated with the Diesel Generators, also lacked anl "N" stamp as required.
The I
additional valves, nine (9) valves per train, will be re-placed during a future outage.
No impact although none of the 18 valves per unit are "N" stamped, 14 of 18 have adequate documentation to support interim usage.
A calculation was performed to demonstrate that the remaining 4 valves would not impair operation of the Diesel Generator even with a complete failure of these valves.
Summar Attachment of DER Revisions Pae2of 2
DER No.
Ori inal Deficienc or Commitment Summar of Chan e
I Im act of Change 86-25 Rev.
1 As part of the original commitment, ANPP forecast to have (1) a software control evaluation program in place for Kaman radiation monitors by January 31,
- 1987, (2) firmware in EPROM's updated per DCP's 10J-SQ-043, 20J-SQ-043, and 30J-SQ-043 and implemented by February 28, 1987, and (3)
FSAR Section 5.2.5.2.3.1 modified by SARCN 2242 to show quantifications of RCS leakage instead of detection of RCS leakage.
1 I
1 0 2 ~
The software control evalua-tion program for Kaman I
Radiation monitors, which wasl postponed due to a delay in implementation of corrective action for CAR CP86-0'132, is now forecast for completion by A ril 16, 1987 (Procurement Quality The firmware in EPROM's, which is being delayed until closure of CAR CP86-0132, will be updated and imple-mented and is forecast for u date/June 15, 1987 im lement.
- Computer Engineering/OPS Engineering)
No impact These are programmatic issues to enhance operation of the Radiation Monitoring System.
The system at present meets all of the requirements necessary to perform its intended safety function.
3 ~
FSAR Section 5.2.5.2.3.1 willi be modified by SARCN 2242, which was delayed due to comment resolution, to show quantification of RCS leak-age and is forecast for completion by June 1, 1987 (Licensing)
l II