View source for 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

{{Adams
| number = ML20087H738
| issue date = 02/27/1984
| title = 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
| author name = Curtis N
| author affiliation = PENNSYLVANIA POWER &amp; LIGHT CO.
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000388
| license number = 
| contact person = 
| case reference number = REF-PT21-84
| document report number = PLA-2089, NUDOCS 8403210145
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 4
}}

=Text=
{{#Wiki_filter:-           -
: y. y .~ .                                       .                                                             ..
x+                                                       PP&L Pennsylvania Power & Light Company Two North Ninth Street
* Allentown, PA 18101
* 215 1 770'5151
                                                                   ~
                                         ~
                                                                     ,s Norman W. Curtis                      .
Vice President-Enginecting& Construction-Nuclear
          ,4                           215/770-7501
                                 ^ FEB 271984 -                         -
                                                                 ~
3.Dr. Thomas E. Hurley
                  ,~                   Pegional Administrator, Regioa.I
                                    . U.S. Nuclear Regulatory _Comruission
                                     '631 Park Avenue:                          (            i lrini of Prussia, PA ,19406
                               ~ SUSQUEHANNA STEAM ELECTRIC STATION s
FINAL REPORT ON : A = DEFICIENCY INVOLVING
                                                            ~
1N,                  iSPDS TEC MODEL^156(ISOLATORS ER 1D050,8' ';                .b                   FILE 821-10 PLA-2089 ~                                           '
                                                                                                       ,                              Docket No. 50-388 LReferenceA                 (1) PLA-2063 dated 2/06/84
                                                       -f ; V

==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
                                                           .p
       +
:N. W. Curtis h                      '
                                                                                          ~
                                " Vice President-Engineering & Construction-Nuclear
                         ~ VAtrachment-
                                         ?..               f Y                                8403210145 840227
                                             'i '
PDR ADOCK 05000388                                                                           g-hS                                      PDR                                                               y L
m                                       -                                                                        a

a
:. . ~         .
Se,              .
            . sa . > ,,.
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
34-S s
(
.         m

r * > w 1 .-~ w                                     n   x.'
&, !? .f;;                                                   "y,, m-
                                                                              +
m a
v.
O n .:                                                                                                                      '
                                                     ~
,        f; '                                                                                      ,
                 .s r g                            <
                                                           . 38c :
3.
.,                     q q a f.- x                                        .
                                                                                                         " +-
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 y
: input land' output signal connections. Two instances have been identified where a Class!1E power source:isLused tesulting'in'a violation in separation 1 requirements..
g iDESCRIPTION'
                                        !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 q                  ? power supplies.also serve'as;the power source for the relays that provide a
     ,                           ,      ' 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.
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                        3 be inoperable.L
              +
tin both deficiencies: discussed above, there is adequate protection on the Class"1Eipowerl supplies to prevent their failure from propagating and a      f             Laffecting'ad:litional safety related functions, u-
      ) ',
s = y %,                                 ,%                _
                        '                                        ~
                                             'h_f_*_         .%        w                n
&] ' ;                                                                    ,
                                                         ^
in-        ,
i

                      .p                       --. , .
e 7            h hikl , ' - -                                                                              ,
x;y yey..
                     ,j                                ~-CORRECTIVE' ACTIONS
     - 4
                - M,                                   ; Unit 1^;&' Common:
g;; "
[~                                 -((1)lThepower.. supply lon-theisolatorforHPCIinputstointerimERCSis         _.
y_v
: disconnected.1 A non-1E power. supply-will'be provided for the isolator by vg y 7 PMR 84-3011 prior;to;the-endlof-the first" refueling outage.
                                                                                                                    ~
I[.1                             [(2) Afnon-1E power; source has been.provided for the' isolator'on the APRM p                             ,
inputs to',SPDS under DCP 82-174C, Rev.-5.
y h- F                                '
(3) The remaining Unit.1 and common-TEC Model 156' isolators procured under
                                                                          . Purchase;0rder-8856-J-049-AL were reviewed by an' examination of the design "y   :g '
                                                                          # drawings;and/or a. field inspection.-- This review ~is~ documented under NCR-84-026.-
J fUnit:2:-                                             -
7[ "] . ;                                                ,,
Iq.                              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.
                      .<                              ; .                     t.
                                                                                      ~
Q'
               ' ' ' - " -(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 i
8856-J-049-AL will be reviewed by'an examination of the design drawings-
                  ,~~ y.                                                - and/orra field. inspection."1This review will'be documented under NCR n
027..
is
(              *R      -''
s                "
                             .sr                             'as J
f 4           '
i M
f n$ _'I^'
h      j s
Q-
[N[''
   ,,    {,''
5                                     Y
   -2                     d'.
(    7 s
: y.                                    '
y.
                                 .' M'4
(
* ___1---Y----N-.------1--}}