ML20028B444
| ML20028B444 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/15/1982 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, ANPP-22277-GHD, DER-82-45, NUDOCS 8211300389 | |
| Download: ML20028B444 (5) | |
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Docket Nos. 50-528/529/530 4
50.55 (e) Report 4ECElVED liRC Arizona Public Service CompaqY2 f,'7,r y b[f f! [7 f Po BOX 21666. PHOENIX, ARIZONA 85036 EEGID!,' V13'=
November.15, 1982 ANPP-22277-GHD/BSK U. S. Muc12ar Regulatory Commission Region V Creekside Oaks Office Park 1450 Macia Lane - Suite 210 Walnut Creek, California Attention:
Mr. D. M. Sternberg, Chief Reactor Projects Branch 1
Subject:
Final Report - DF.R 82-45 A 50.55(c) Reportable Cond'. tion Relating to C. E./Borg-Warner Safety Injection System Valves Installed With Hotor Operators Not Qualified For Inside Containment File: 82-019-026 D.4.33.2
Reference:
(A) Telephone Conversation between J. Eckhardt and G. Duckworth on August 26, 1982 (B) ANPp-21836 dated September 15,1982 (Interim Report)
Dear Sir:
Attached, is our final written report of the Reportable Deficiency, under 10CFR50.55(e), referenced above.
Very truly yours, l
h f. g tb E. E. Van Brunt, Jr.
i APS Vice President j
Nuclear Projects Management ANPP Project Director EEVBJr/GllD:db Enclosure cc: See Attached rage 2 k bM B211300597 821115 PDR ADOOh 05000528 S
U. S. Nuclear Regulatory Commission November 15, 1982 Attention:
Mr. D. M. Sternberg, Chief ANPP-22277-Gild /BSK Page 2 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.
J. A. Roedel D. B. Fasnacht G. C. Andognini A. C. Rogers B. S. Kaplan W. E. Ide J. Vorces J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Ilawkinson L. E. Vorderbrueggen G. A. Fiorelli Lynne Bernabei, Esq.
liarmon & Weiss 1725 "1" Street, NW Washington, D. C. 20006 R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 l
k FINAL REPORT - DER 82-45 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 1, 2 & 3 I.
DESCRIPTION OF DEFICIENCY A review of Combustion Engineering (CE) letter V-CE-6506 dated iby 28, 1982, indicated motor operators for CE Tag Numbers SIC-UV-653 and SID-UV-654 were supplied by CE's valve vendor, Nuclear Valve Division of Borg Warner, with "autside-containment" motor operators instead of the qualified and specified "inside-containment operators". No documentation for this substitution was provided.
II.
ANALYSIS OF SAFETY IMPLICATION This condition is evaluated as reportable. As stated in the attached CE letter V-CE-17115, dated September 21, 1982, these valves normally provide the path for shutdown cooling suction flow of the reactor coolant from the hot legs to the pumps used during shutdown cooling. These valves would also provide this path after recovery from a small break LOCA and from a MSLB. The "outside-containment" motor operator meets all the requirements for "inside-containment" use except maximum temperature.
"Outside-containment" motor operators were qualified to 250F for twenty-four (24) hours and 200F for sixteen (16) days.
Post-accident service requires qualification at least to 350F for ten (10) minutes, then to 300F for approximately sixteen (16) hours, then decreasing to 200F over approximately the next twenty (20) days.
Since these operators were not fully qualified :o the post-accident conditions inside containment, it cannot be conc,usively demonstrated that they would have been capable of perforning their l
safety function.
III. CORRECTIVE ACTION Nonconformance Reports (NCR's) SM-1107, NC-861, and NC-862 will be l
dispositioned to replace the subject motor operators with the l
qualified "inside-containment" operators. Bechtel will request CE to initiate action to preclude recurrence by (1) notifying the vendor of this report, and (2) by reviewing the CE vendor surveillance program to assure adequate inspections are made prior to future shipments from this vendor.
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In addition to reportability under 10CFR50.55(e), PVNGS Project considers the deficiency to be reportable under the requirements of 10CFR Part 21, by the supplier. Deficiency Evaluation Report 82-45 addresses the reporting requirements specified under 10CFR 21.21.(b) (3) w'.th the exception of sub-part (vi) which requires the number and location (customers and/or facilities) of possible defective equipment. A copy of this report has been sent to CE for transmittal to Borg 11arner, requesting their review for reporting under 10CFR Part 21, including number and location of all components supplied.
Since Bechtel has notified CE, and this 10CFR50.55(e) report is being submitted to the NRC by Arizona Public Service, Bechtel will not file a 10CFR Part 21 report with the NRC.
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C E Pgw:r Systems Tel. 203/6881911 Combusnon Engineering. Inc.
Telex 99297 1000 Prospect Hill Road Windsor. Connecticut 06095 Attachment to DER 82-45 S
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Mr. W. G. Bingnam Bechtel. Power Corporation 12400 East Imperial Highway Norwalk, CA 90650
Subject:
Inside Containment Motor Operators, DER-82-45
Reference:
Letter No. B/CE-E-41197, August 18, 1982
Dear Mr. Bingham:
At Bechtel's request, C-E has reviewed our previous recommendation concerning the reportability of the supply of incorrect valve operators on certain valves.
C-E's valve vendor Nuclear Valve division of Borg Warner, can not provide technical justification for supplying "outside" vs "inside" containment motor operators on valve tag nos51-653 and -654. We have therefore concluded that our original recommendation of "not reportable" appears incorrect and-that we would recommend tnis item be reported based on the following discussion, l
These valves normally provide the path for shutdown cooling suction flow of the l
reactor coolant from the hot legs to the pumps used during shutdown cooling.
These valves would also provide this path after recovery from a small break LOCA and from a MSLB.
It is noted that the "outside" containment motor operator meets all the requirements for "inside" containment use except maximum temperature.
"Outside" containment motor operators were qualified to 250F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and to 200F for 16 days. Post-accident service requires qualification at least to 350F for 10 minutes, then to 300F for approximately 16 nours, then decreasing to 200F over approximately the next 20 days.
Since these operators were not fully qualified to the post-accident conditions inside containment, it cannot be conclusively demonstrated that they pgp been capable of performing their safety function.
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