ML20102A582: Difference between revisions

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=Text=
=Text=
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                                                                                          ''YCD;'r..
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Arizona Nuclear Power Project ~*D                             /~,  ,
Arizona Nuclear Power Project ~*D
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P O. BOX 52034 e PHOENIX ARIZONA 85072-2034
P O. BOX 52034 e PHOENIX ARIZONA 85072-2034
                                                                                    ' g ., ,
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January 24, 1985 ANPP-31792-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:   Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
January 24, 1985 ANPP-31792-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects


==Subject:==
==Subject:==
Line 30: Line 32:


==Dear Sir:==
==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.
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 February 28, 1985, at which time a complete report will be submitted.
Due to the extensive investigation and evaluation required, an Interim Report is attached.
It is now expected that this information will be finalized by February 28, 1985, at which time a complete report will be submitted.
Very truly yours
Very truly yours
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E. E. Van Brunt, Jr.
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APS Vice President, Nuclear Production ANPP Project Director EEVB/TRB/pik Attachment               8502080456 050124 PDR ADOCK 05000520 cc:   See Page Two       S                         PDR I
APS Vice President, Nuclear Production ANPP Project Director EEVB/TRB/pik Attachment 8502080456 050124 PDR ADOCK 05000520 cc:
See Page Two S
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                -cc       Richard DeYoung, Director Office of Inspection and-Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. C. Woods, Jr.
-cc Richard DeYoung, Director Office of Inspection and-Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 T. C. Woods, Jr.
D. B. Karner.
D. B. Karner.
                          -W. E. Ide D. B. Fasnacht A. C. Rogers
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                                                          ' INTERIM REPORT - DER 84-106                                 ,
' INTERIM REPORT - DER 84-106 POTENTIAL REPORTABLE DEFICIENCY
POTENTIAL REPORTABLE DEFICIENCY
' ARIZONA PUBLIC SERVICE COMPANY (APS) i E-PVNGS UNIT 1 F
                                                    ' ARIZONA PUBLIC SERVICE COMPANY (APS)                             i E-PVNGS UNIT 1 F
:I.-
:I.-       . Potential Problem Two spurious load. sheds and lock up of the train B, BOP ESFAS that shed the 4160V swgr. SO4 feeder bkr. and associated 480V load . centers, occurred on 12/13/84. The plant condition at that time was as follows:
. Potential Problem Two spurious load. sheds and lock up of the train B, BOP ESFAS that shed the 4160V swgr. SO4 feeder bkr. and associated 480V load. centers, occurred on 12/13/84. The plant condition at that time was as follows:
The plant was.in normal ~ operating configuration and alignment, no test-
The plant was.in normal ~ operating configuration and alignment, no test-
                                      -ing or change of operating conditions were toing performed.
-ing or change of operating conditions were toing performed.
The actuations occurred four hours apart.
The actuations occurred four hours apart.
II.         Approach To and Status'Of Proposed Resolution.
II.
                                      - Bechtel. Engineering.is currently studying this problem to determine re-portability and technical ~ justification for corrective action.
Approach To and Status'Of Proposed Resolution.
III.        :  Projected Completion of Corrective Action and Submittal of the Final Report The complete: evaluation and final report are forecast to be completed by February 28.-1985. 1The ANPP has determined'this system is not.
- Bechtel. Engineering.is currently studying this problem to determine re-portability and technical ~ justification for corrective action.
l                                     necessary until Mode 2 operations.'
Projected Completion of Corrective Action and Submittal of the Final III.
Report The complete: evaluation and final report are forecast to be completed by February 28.-1985. 1The ANPP has determined'this system is not.
l necessary until Mode 2 operations.'
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Latest revision as of 04:50, 13 December 2024

Interim Deficiency Rept DER 84-106 Re Spurious Load Sheds on balance-of-plant Esf.Initially Reported on 841227.Bechtel Determining Reportability & Corrective Actions.Next Rept Expected by 850228
ML20102A582
Person / Time
Site: Palo Verde 
Issue date: 01/24/1985
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Kirsch D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-31792-TDS, DER-84-106, NUDOCS 8502080456
Download: ML20102A582 (3)
v • d • e


Text

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Arizona Nuclear Power Project ~*D

/~,

P O. BOX 52034 e PHOENIX ARIZONA 85072-2034

' g.,,

January 24, 1985 ANPP-31792-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:

Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects

Subject:

Interim Report DER 84-106 A 50.55(e) Potentially Rep'ortable Deficiency Relating to Spurious Load Sheds On BOP ESFAS File: 85-019-026; D.4.33.2

Reference:

Telephone Conversation between P. Narbut and T. Bradisk on December 27, 1984.

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 February 28, 1985, at which time a complete report will be submitted.

Very truly yours

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E. E. Van Brunt, Jr.

APS Vice President, Nuclear Production ANPP Project Director EEVB/TRB/pik Attachment 8502080456 050124 PDR ADOCK 05000520 cc:

See Page Two S

PDR I

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-cc Richard DeYoung, Director Office of Inspection and-Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 T. C. Woods, Jr.

D. B. Karner.

-W.

E. Ide D. B. Fasnacht A. C. Rogers

- L. A. Souza D. E. Fowler T. D.-Shriver s

-C. N. Russo B. S. Kaplan J. R. Bynum' J. M. Allen D.'Canady A. C.-Cehr W. J. Stubblefield W. G. Bingham

' R. L.'

Patterson -

R. W. Welcher-

~'

H. D. Foster D. R. Hawkinson R. P. Zimmerman

- H. L. Clyde L

M. Matt T. J. Bloom-Records Center Institute of Nuclear Power Operations

.1100 circle.75 Parkway, Suite 1500 Atlanta, CA 30339 i

2

F i

l'.

7 s._

i-

' INTERIM REPORT - DER 84-106 POTENTIAL REPORTABLE DEFICIENCY

' ARIZONA PUBLIC SERVICE COMPANY (APS) i E-PVNGS UNIT 1 F

I.-

. Potential Problem Two spurious load. sheds and lock up of the train B, BOP ESFAS that shed the 4160V swgr. SO4 feeder bkr. and associated 480V load. centers, occurred on 12/13/84. The plant condition at that time was as follows:

The plant was.in normal ~ operating configuration and alignment, no test-

-ing or change of operating conditions were toing performed.

The actuations occurred four hours apart.

II.

Approach To and Status'Of Proposed Resolution.

- Bechtel. Engineering.is currently studying this problem to determine re-portability and technical ~ justification for corrective action.

Projected Completion of Corrective Action and Submittal of the Final III.

Report The complete: evaluation and final report are forecast to be completed by February 28.-1985. 1The ANPP has determined'this system is not.

l necessary until Mode 2 operations.'

J 4-i ^

._

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