ML20093N984
| ML20093N984 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/18/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-29990-TDS, DER-83-59, NUDOCS 8408020229 | |
| Download: ML20093N984 (5) | |
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Arizona Public Service Company n
193iJJL 23 FH 2 27 July 18, 1984 ANPP-29990-TDS/TRIEN M
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.U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park
~1450 Maria Lane - Suite 210 I
~ Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs i
Subject:
Final Report, Revision 1 - DER 83-59 A 50.55(e) Reportable Condition Relating to IEEE-384 Separation Criteria Violated by Wiring In Unit 2 Post Accident j
Control Roos Cabinet And Safety Radiation Monitoring Cabinet.
i File: 84-019-026; D.4.33.2 i
Reference:
A) Telephone Conversation between P. Narbut and R. Tucker on August 30, 1983 B) ANPP-27912, dated October 3,1983 (Interim Report) j.
C) ANPP-28312, dated November 30, 1983 (Interim Report, Rev. 1)
D) ANPP-29039, dated March 9,1984 (Final Report) i
Dear Sir:
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Attached is Revision 1 of our final written report of the deficiency j
referenced above, which has been determined to be Not Reportable under i
the requirements of 10CFR50.55(e). This Revision restaten Analysis of l
Safety Implications and clarifies the Corrective Action.
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Very truly yoirs
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E. E. Van Brunt, Jr.
4 APS Vice President I
Nuclear Production ANPP Project Director i
EEVB/TRE:dh At tachment cc:
See Page Two I
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. Mr. T. W. Bishop DER 83-59 Page Two cc:
Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.
D. B. Karner W. E. Ide D. B. Fasnacht A. C. Rogers L. A. Souza D. E. Fowler T. D. Shriver C. N. Russo J. Vorees J. R. Bynum J. M. Allen J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher H. D. Foster D. R. Hawkinson L. E. Vorderbrueggen R. P. Zimmerman S. R. Frost J. Self D. Canady T. J. Bloom Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339 e
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FINAL REPORT - DER 83-59 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 2 I.
Description of Deficiency Inspection of the Radiation, Monitoring System (RMS) Class 1E Control and Indication Cabinets JSQA-C01/JAQB-C01 and JSQAC05/JSQBC05 in all 3 units, revealed that.some internal wiring separation did not meet' Class 1E separation requirements as defined in IEEE-384. These cabinets were supplied by Kaman Instrumentation. These circuits include microcomputer signal wiring (5V-de or less) and the associated Class 1E wiring circuits.
I' II.
Analysis of Safety Implications The Engineered ' Safety Feature _ Actuation System (ESFAS) monitors the RMS for normally energized contacts. These contacts open on high radiation, high radiation rate, equipment failure, or any power failure. Equipment failure includes high cabinet temperature, l
incorrect voltages and abnormal signal condition. The failure to seet separation criteria could cause inadvertent actuation of ESFAS.
Inadvertent actuation could result in (1) exhausting the Fuel Building HVAC through HEPA filters, (2) securing the containment purge, (3) placing the control room air on internal recirculation.
Thus an RMS failure would lead to a fail safe condition. Lack of separation has no adverse safety consequence. The system is not required for safe shutdown.
Analysis of non-1E effects on IE wiring within cabinet 13JSQA/BC01.
A.
The purpose of this analysis is to demonstrate that there is no l
credible source of fire from the non-1E, low power, computer signal wiring contained in the 1E cabinet.
B.
The only non-1E wiring in the cabinet connects the non-1E minicomputer, JSQNC03A with each channel of the safety-related isolation modules (SRMS). This is shown on Kaman drawing 430041 (N997-162) and 430036 (N997-370. There are two Greenlee flexible metal conduits which contain non-1E wiring. One set of non-1E wiring runs from TB9B to the SRMS "B".
The other set of non-lE wiring runs from TB7A to the SRMS "A".
C.
These non-1E wires terminate in the optical isolator assembly of the SRMS. This is shown on Kamen drawing 430034 (Log 4
13-10407-N997-370). The optical isolator is a proven and accepted method of providing information transfer from 1E to i
non-1E systems.
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- Mr. T. W. Bishop
- Page Two D.. The power source to drive the non-1E components is contained _ in the minicomputer (13JSQNC03A) and is manufactured by Power One.
The power supply data sheet (dwg. 50220B)_ states that the computer power supply can provide 51 05 or 121 07 volts dc.
Since the data for.the 5 volt supply _is more conservative, it is used in the analysis. The 5V-dc power supply will
" current-limit" to 4.5 amps. Per Bechtel to Kaman telephone notes (TN-3671, dated 2-24-84), the _ cable can carry 16 amps continuously. A cusparison of the current rating of the cable
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with the maximum current.of.the power supply shows that the RMS Computer Signal and Information cables can be considered as low-energy circuits which cannot damage any associated cabling given a fault condition.
E.
There are no other Kasan cabinets with a non-1E Lo 1E interface except for those already reviewed. The control room -cabinets are unique as they provide intornation to both IE and non-lE interfaces. All other Kaman cabinets provide either 1E or non-1E interface, but not both. This may be cerified by checking the wiring "From-To" List (Log 13-10407-N997-209).
Based on the ribove, this condition is evaluated as not reportable under the requirements of 10CFR50.55(e) and.
10CFR Part 21, since if this condition were to remain uncorrected, it would not represent a significant safety condition.
III. Corrective Action A.
SAR Change Notice 1183 has been issued to reflect this justification and analysis. SAR Change Notice 1114 has been superseded by SAR Change N tice 1183.
o B.
To enhance reliable operation and to preclude potential damage to circuits, particularly during maintenance periods, sheet metal barriers will be added between terminal blocks group 38, 39, 40 and 41 and terminal blocks group 47, 48, 49 and 50 as indicated by Kaman letter (KI-BP-83-090). In addition, an existing metal barrier will be extended to a point above terminal block 37, due to the routing of non-Class 1E wiring into the cabinets.
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Mr. T. W. Bishop ANPP-29990 Page Three C.
The above physical changes have.been implemented in Unit 1 by dispositioning NCRs SE-2327, 2350 and 2351 as " Rework" under the direction of the Kazan field representative. Unit 2 changes vill be implemented by disposition of " Rework" on Bechtel NCR EJ-3219. The cabinets for. Unit 3 will be updated with these changes by Kaman prior to delivery to the jobsite. All work is scheduled tc he c >mpleted prior to fuel load for the respective units.
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