PLA-2089, Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling

Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling

ML20087H738
Person / Time
Site:	Susquehanna
Issue date:	02/27/1984
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-84 PLA-2089, NUDOCS 8403210145
Download: ML20087H738 (4)

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PP&L Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215 1 770'5151

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,s Norman W. Curtis Vice President-Enginecting& Construction-Nuclear 215/770-7501

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^ FEB 271984 -

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3.Dr. Thomas E. Hurley

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Pegional Administrator, Regioa.I

. U.S. Nuclear Regulatory _Comruission

'631 Park Avenue:

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i lrini of Prussia, PA,19406

~ SUSQUEHANNA STEAM ELECTRIC STATION FINAL REPORT ON : A = DEFICIENCY INVOLVING s

1N, iSPDS TEC MODEL^156(ISOLATORS

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ER 1D050,8' ';

.b FILE 821-10 PLA-2089 ~

Docket No. 50-388 LReferenceA (1) PLA-2063 dated 2/06/84

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Dear Dr. Murley:

O 1s letter serves =to provide.the Commission with a final report on a deficiency initolving SPDS'TEC Model 156 isolators. This deficiency was

. freported. under'10CFR50.55(e)'by telephone to'Mr. G. Kelley of NRC Region I by g p Mr. J. Saranga'of PP&L on January 6, 1984.

e ' 'The attachment to this letter contains=a description of the problem, the.

safety-implications,-and the corrective actions.. This deficiency was addressed for' Unit'1 in PLA-2070 dated 2/03/84.(LER 84 003).

Since Ehe~ details of this report Trovide information relevant to the reporting "requireme'nts of'10CFR21 for Unit 2, this correspondence is considered to also L, discharge any. formal responsibility PP&L may have for reporting in compilance thereto.

I' We trust thelCommissien will find this report to be satisfactory,

- Veryj truly ' yourr,,4

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N. W. Curtis

" Vice President-Engineering & Construction-Nuclear

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8403210145 840227 g-

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PDR ADOCK 05000388 y

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Page 2 SSES PLA-2089 FEB 27 m ER 100508 Pii. 821-10

'Dr. Thomas E. Murley I

'_. Copy to:

-Mr.1 Richard C. DeYoung'(15)'

Director-Office of Inspection & Enforcement u U.S. Nuclear-_ Regulatory Comuission

. Washington, D.C.

20555-

-Mr. G.; Mcdonald,_ Director Office of Management:Information & Program Control

U.S.: Nuclear Regulatory Commission Washington, D.C.--20555 Mr. R. H. Jacobs U.S. Nuclear Regulat'ory Commission

-P.O.. Box 52

Shickshinny, PA 18655 Records Center.

Institute.of Nuclear. Power Operations liOO; Circle.75 Parkway,-Suite 1500 Atlanta, GA'30339 s

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FINAL REPORT v

' Attachment [ to PLA-2089 1

' SUBJECT l Technology for Energy Corporation Model 156 isolators procured under Bechtel

-Purchase Order 8856-J-049-AL-do not meet the requirements of the purchase sspecification which calls for ceparation of the power source from both'the

input land' output signal connections. Two instances have been identified where y'

a Class!1E power source:isLused tesulting'in'a violation in separation 1 requirements..

iDESCRIPTION' g

!Th$ safety' parameter' display system (SPDS) and the interim emergency response

' computer system (ERCS) '(both non-1E) require input. from safety related.

. systems.- 'To provide separation'for the safety related systems, TEC Model 156 isolators were purchased and installed. The purchase order for these isolators; required a minimum isolation of 600 VAC or 1000 VDC between the

- input, output, and power' supply circuits. After the installation of the Isolators, ~it was discovered that the power supply circuit was directly v>

connected to the output circuit. Consequently, use of the isolator in

cabinets with -1E power' results in' connection of a 1E s ource to a non-1E =

. circuit..- Two cases have been identified where a Class-1E power supply was

used for the isolator

l'. -average power range monitor.(APRM) inputs-to SPDS

2., high' pressure coolant injection (HPCI) inputs to interim ERCS dANALYSIS OF SAFETY IMPLICATIONS-The. configuration at'the isolators on the APRM inputs to SPDS could have led 1to the failure.of the-20 VDC power' supplies in all six APRM channels. These

? power supplies.also serve'as;the power source for the relays that provide a q

' trip, signal to the' RPS systera.. A fault within the SPDS system could propagate

through the: isolator and cause'the relays to.deenergize. When the relays

deenergize, a, reactor scram is initiated.

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w, iThe power supply 'for: the isolator on the HPCI system input to interim ERCS is also usedlas.the power. supply for the HPCI control loop.. Consequently, a

' failure originating in the interim ERCS system could have caused the loss of the HPCI control loop power ~ supply. Without the~HPCI control loop, HPCI would A

be inoperable.L

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3 tin both deficiencies: discussed above, there is adequate protection on the

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Class"1Eipowerl supplies to prevent their failure from propagating and f

Laffecting'ad:litional safety related functions, a

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~-CORRECTIVE' ACTIONS

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Unit 1^;&' Common

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-((1)lThepower.. supply lon-theisolatorforHPCIinputstointerimERCSis g;; "

disconnected.1 A non-1E power. supply-will'be provided for the isolator by y_v y 7 PMR 84-3011 prior;to;the-endlof-the first" refueling outage.

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[(2) Afnon-1E power; source has been.provided for the' isolator'on the APRM

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p inputs to',SPDS under DCP 82-174C, Rev.-5.

yh (3) The remaining Unit.1 and common-TEC Model 156' isolators procured under

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. Purchase;0rder-8856-J-049-AL were reviewed by an' examination of the design "y '

1. drawings;and/or a. field inspection.-- This review ~is~ documented under NCR-

g '84-026.-

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M ;;(1) A.non-lE power supply will;be'provided for the isolator on HPCI inputs to m

~.. interim-ERCS. prior to initial 1 criticality under PMR 84-3048.

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-(2)fAJnon 1EJpower. supply-will be'provided.for the isolator on the APRM inputs

.-to SPDS' prior.to fuel load.. This-work is being done under NCR 83-1110 and lNCRl83-1174.

-(3)..Th'e7 remaining Unit 2 TEC'Model 156 isolators procured under Purchase Order

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8856-J-049-AL will be reviewed by'an examination of the design drawings-i

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- and/orra field. inspection."1This review will'be documented under NCR

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