ML20064N265

Final Deficiency Rept Re Excore Neutron Monitor Cables Having Greater Length & Attenuation than Design.Initially Reported on 820216.New Cable Meeting Attenuation Requirement Purchased.Condition Not Reportable Under 10CFR50.55(e)

ML20064N265
Person / Time
Site:	Palo Verde
Issue date:	08/26/1982
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, ANPP-21685-GHD, DER-82-1, NUDOCS 8209080287
Download: ML20064N265 (14)

Text

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s' Docket Nos. 50-528/529/530 f

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50. 55 (e) Report

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STA. 3001 P.O. BOX 21666 PHOENIX, ARIZONA 85036 August 26,j.1982 ANPP-21685-GHD/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 i

Walnut Creek, California 94596-5368 Attention:

Mr. T. W. Bishop, Chief Reactor Construction Project Branch

Subject:

Final Report - DER 82-1 A 50.55(e) Report Relating to Ex-Core Net.

on Monitor Cables Having Greater Length and Attenuatioa Than Design File: 82-019-026 D.4.33.2

Reference:

(A) Telephone Conversation between J. Eckhardt and G. Duckworth on February 16, 1982 (B) ANPP-20462, dated March 18,1982 (Interim Report)

(C) ANPP-20965, dated May 14, 1982 (Time Extension) l

Dear Sir:

Attached, is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).

Very truly yours, O.1l d thl i

E. E. Van Brunt, Jr.

APS Vice President Nuclear Project Management ANPP Project Director i

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See Attached Page 2 8209000287 820026 PDR ADOCK 05000528 3y.

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r U. S. Nuclear Regulatory Commission August 26, 1982 Attention:

Mr. T. W. Bishop, Chief ANPP-21685-GHD/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. Hawkinson L. E. Vorderbrueggen G. A. Florelli Lynne Bernabei, Esq.

Ilarmon & Weiss 1725 "1" Street, NW ~

Suite 506 Washington, D. C. 20006 R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 l

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FINAL REPORT - DER 82-1 DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE COMPANY (APS)

I.

DESCRIPTION OF DEFICIENCY The Excore Neutron Monitoring System design is currently impacted by the following facts:

1.

Combustion Engineering interface criteria specify a maximum cable length of 500 feet using cable meeting RG71 B/U electrical characteristics or equivalent.

The 500 foot length is controlled by the attenuation of the cable which is approximately - 0.8dB/100 Ft. (at 3.0 MH )-

z 2.

Due to the physical configuration of the system, the cable lengths from preamplifier to processing drawer are in the 700 to 800 foot range.

3.

The Project Design Criteria requires that cabling be fully qualified for Class IE applications in the LOCA/MSLB environment, and meet flammability requirements per IEEE 383. The cable purchased by Bechtel procurement specification 10407-13-EM-060 meeting the design cri teria is Brand-Rex Part Number CD95146; however, this cable is significantly h(her in attenuation than that specified in MIL-C-17E for RG-71 B/U Coax Cable. Using this cable the installed length cannot exceed 340 feet for proper system operation.

The design as it currently exists has not been finalized and accepted by Bechtel and Combustion Engineering, since the startup/ logarithmic power channels may be affected to the extent that no signal or a minimum signal is available, which would defeat the logarithmic power level trip function of the monitoring system.

II. ANALYSIS OF SAFETY IMPLICATIONS The Excore Neutron Monitoring System design is not complete nor accepted by either Bechtel Engineering or Combustion Engineering. This system has not been submitted for turn-over for startup testing. There exists a background of design interface correspondence between Bechtel and C-E concerning this design condition.

In summary, Bechtel transmitted engineering information indicating to C-E that installed cable lengths would be greater than 500 i

feet, and asked C-E if the system could be modified to accommodate up to 650 feet of cable length.

In Attachment (A), C-E provided test data indicating the Brand-Rex cable does not meet the required electrical characteristics for long cable lengths, and in Attachment (B), Bechtel indicated to APS the proposed resolutions which would allow the design to be completed. There fore, this condition is evaluated as Not Reportable.

III. CORRECTIVE ACTION APS has purchased new cable which meets the attenuation requirements for 700 to 800 foot lengths, and Unit 1 cable has been replaced under Design Change Package ISESE002.

(Unit 2 cable was not installed, and has been placed on hold until additional new cable for Units 2 & 3 is delivered, currently scheduled for September 15, 1982.) This brings the design into compliance with Chapter 15 of CESSAR-F.

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. December 22, 1981 V-CE-15641 Mr. W. G. Bingham Bechtel Power Corporation 12400 East Imperial Highway Norwalk, CA 90650

Subject:

Arizona Nuclear Power Project Excore Cable Test Program

Reference:

Y-CE-15530 of November 23, 1981

Attachment:

Excore Cable Test Report

Dear Mr. Bingham:

The attachment provides the results of our test program to determine the acceptability of the current Excore System cabling as promised by the reference.

If you have any questions or coments, please call.

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Excore Coaxial Cabje Test Program Results f;g During the week of November 9, a Cable Testing Program was performzd at stinghouse IGTO. The purpose of this Program was to evaluate the Excorc System Performance with coaxial cables well in excess of the specified 500 ft, maximum interface requirement. Currently, ANPP has installed Excore Signal Cables in the 700 to 800 foot range.

In addition to the physical length, it appears th'at a problem in the form of " Alternate" Electrical Characteristics is becoming a major factor. Several cable vendors, in order to meet flame retardant and post-accident criteria, are providing RG-71B/U " Alternate" Cable which is significantly higher in atternation than that specified in HIL-C-17E for.RG-71B/U Coax Cable. This higher attenuation, when coupled with excessive cable lengths, can result in Excore signals being reduced in amplitude below the normal noise levels.

4 The Excore Preamplifier output pulse can be most appropriately described by a frequency component at 3.0 MHZ. This will be the limiting case for at-tenuation since the MSV Bandpass Filter region will result in lower attenua-tion values.

In the pulse mode, the discriminator setpoint at the drawer must correspond to a detector pulse of 0.09pC for proper calibration. This detector p91se will produce a nominal 72 mV (peak) pulse at the preamplifier output.

Based upon experience from other installations, this pulse must be at least 45 eV at the drawer input for reliable system operation. Therefore, the Cable Sys-tem from the Preamplifier to the drawer must not have an attenuation of greater than -4.0 dB at 3MHz.

The specification governing RG type Coaxial Cable is MIL-C-17E.

For RG71B/U Cable, the maximum attenuation is specified to be -B.0 dB per 100 ft. at 400 MHz.

Using a conserative straight line approximation down to 3 MHz yields a limiting value for attenuation of -0.77 dB per 100 ft.

During the Cable Test Program, four types of cable from two different manufacturers were actually tested.

In addition, data on Nuclear Grade Cable has been obtained and evaluated for two additional manufacturers. Of the cables tested, all were flame retardant in accordance with IEEE-3B3 with one of the cables being qualified for LOCA/MSLB Service. The at-tenuation of these cables ranged from -0.29dB to -0.56dB per 100 feet at 3MHz.

• 7 The cables tested were manufactured by Boston Insulated Wire and ITT Suprenant.

Data on Nuclear Grade Cable was recieved from Rockbestos and Brand-Rex. The Rock-bestos Cable claims to be LOCA qualified and still meet the MIL-C-17E requirements.

Brand-Rex supplies "RG-XX Alternate" cables which meet the standard RG character-istic impedance but deviate in other properties, including attenuation. Re-stating the Functional E.xcore System requirement addressed above, the system will perform properly with up to 500 feet of Coaxial Cable which has an attenuation of approximately -0.8dB/100 ft (at 3.0 MHz). Actual usable physical length will depend directly on attenuation, with the limit that total attenuation not exceed -4.0dB.

For evaluation of the ANPP Cabling, a detailed Engineering Data Package was obtained from Brand-Rex. The data received was for an RG-71B/U Alternate.

Brand-Rex Part Number CD95146. The attenuation of this cable is -22.5dB per 100 feet at 400MHz, or 2.8 times that specified in MIL-C-17E. At 3.0MHz, the attenuation is -1.18dB per 100 feet. To meet the total attenuation require-mmt, the installed length with this cable cannot exceed 340 feet for proper system operation.

This length is less than any of the currently planned cable runs based on information received from Bechtel. Unless the cable layout can be changed to comply with the 340 foot maximum length, it is our evaluation that the proposed cable is not acceptable for use with the Excore System.

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R. R. Stiens W. J. Stubblefield D. R. Bonano B. L. Aley T. E. Hartman J. Schuh B/ANFP-E-84327 J. T. Boyle IOC 183340 January 27, 1982 Arizona Nuclear Power Project P. O. Box 21666 - Mail Station 3003 Phoenix, Arizona 85036 i

Attention: Mr. Edwin E. Van Brunt, Jr.

APS Vice President, ANPP Project Director

Subject:

Arizona Nuclear Power Project Bechtel Job 10407 EX-Core System Cable Lengths Pile: NM-001

Reference:

Letter ANPP-19899-JMA/SLK, January 13, 1982

Dear Mr. Van Brunt:

Confirming our telephone discussion of January 22, 1982, we are proceeding with the following plans to achieve the problem resolution.

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1) Arrangements are being made to conduct the field test on the installed ex-core system cables between the preamplifiers and the esfety drawers.

We are scheduling this test for the week ending January 29, 1982.

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2) We are exploring the possibilities of replacing part of the cables by IDCA/MSLB qualified cables meeting the system attenuation requirements.

3) Adding an amplifier outside the containment will be considered as the last alternative.

We will take necessary action towards resolving the problem to meet the required schedule depending on the outcome of the field test. We will keep you informed of the progress made, cost / schedule impsets if any. Please advise it you need any additional information. This closes Bechtel action on Reference (A).

Very truly yours, BECHTEL POWER CORPORATION Original Signed Dy /2.0. h

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