ML20072P853
| ML20072P853 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/17/1983 |
| From: | Van Brunt E, Vanbrunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-23271-RQT, DER-83-10, NUDOCS 8304040396 | |
| Download: ML20072P853 (3) | |
Text
1 Docket Nos. 50-528/529/530 50.55(e)Reporty?!.TcgED Arizona Public Service Company
. kM p/
P o box 21666. PHOENIX. ARIZONA 85036 ei !2: cn March 17, 1933 ANPP-23271-RQW 3pYg,.
U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. D.
M.' Sternberg, Chief Reactor Projects Branch 1
Subject:
Interim Report - DER 83-10 A 50.55(e) Potentially Reportable Deficiency Relating to thin Steam Relief Valve Tests Exceed Specified Five Percent (57.) Blowdown Limit File: 83-019-026 D.4.33.2
Reference:
Telephone Conversation between P. Narbut and G. Duckworth on February 28, 1983
Dear Sir:
The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.
Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by May 24, 1983, at which time a couplete report will be submitted.
Very truly yours, 4
V Q
(N LW
(
E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects Management ANPP Project Director i
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Enclosure cc: See Attached Page 2 1
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830404o396 e30317 PDR ADOCK 05000528 S
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.U. S. Nuclear' Regulatory Commission March 17, 1983 Attention:
Mr. D. M. Sternberg,. Chief ANPP-23271-RQT/BSKL Page 2 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commissica:
Washington, D. C. 20555
-T. G. Woods, Jr.
J. A. Roedel D. B. Fasnacht G. C. Andognini J. R. Bynum
-A. C. Rogers D. S. Kaplan W. E. Ide J. Vorees-P. P. Klute/D. D. Green A. C. Gehr.
W. J. Stubblefield
-W. G. ~ Bingham R. L. Patterson R. W. Welcher R. H. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiore111 1
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C INTERIM' REPORT - DER 83-10 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS) 2 PVNGS UNITS 1, 2 & 3 I.
POTENTIAL PROBLEM The Unit 1 main steam safety valves had been received and installed.
.The valves were removed for Secondary Hydro Testing and stored in
- violation of ANSI-N45.2.2 and Dresser Installation / Maintenance Manuals.: A build-up of corrosion on parts requiring close
~ tolerances, and the potentia 1' misalignment of valve internals, precluded valve operation per their design intent. To assure valve performance to design intent, APS requested the valves be transmitted to Wyle Laboratories where the boiler capacity existed for full flow testing. Prior to testing, the valves were cleaned and refurbished as required.
Ten (10) of the twenty (20) relief valves were tested, and all valves exceeded the specified blowdown of five percent (5%).
Blowdown for the tested valves ranged from seven percent (7%) to fifteen percent (15%). Increased blowdown results in higher steam releases, increased cooldown rates of-primary and secondary systems and potentially higher offsite radiological doses. The aforementioned valves are Dresser Model No. 370RA-RT25. The following Tag Nos. are affected:
SGE-PSV-554 SGE-PSV-559 SGE-PSV-574 SGE-PSV-579 SGE-PSV-555 SGE-PSV-560 SGE-PSV-575 SGE-PSV-591 SGE-PSV-556 SGE-PSV-561 SGE-PSV-576 SGE-PSV-592 SGE-PSV-557 SGE-PSV-572 SGE-PSV-577 SGE-PSV-594 SGE-PSV-558 SGE-PSV-573 SGE-PSV-578 SCE-PSV-595
'II.
APPROACH TO AND STATUS OF PROPOSED RESOLUTION Bechtel Engineering is currently corresponding with Combustion Engineering to disposition this item.
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III. PROJECTED COMPLETION OF CORRECTIVE ACTION AND SUBMITTAL OF THE FINAL REPORT Evaluation of this condition and submittal of the Final Report is forecast to be completed by May 24, 1983.
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