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{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM.(RIDS)ACCESSION NBR:8106090406 DOC~DATE!81/06/05 NOTARIZED:
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM.                                     (RIDS)
NO DOCKE.T'FACIL:50 387 Susquehanna Steam Electrf c Stations Unf t 1>Pennsyl va 0500~087 50 388 Susquehanna Steam Electr f c Statf one Unf t 2'P Pennsyl va 05'I)038 AUTH',NAME AUTHOR AFFILI ATTON CURTIS E N~W~Pennsyl vanf a Power L Lf ght Co~RECIP~NAMEl RECIPIENT AFFILIATION GRIERiB~H~Region ii Phfladelphfar Office'f the Director (81/03/01)
ACCESSION NBR:8106090406                   DOC ~ DATE! 81/06/05 NOTARIZED: NO                               DOCKE.T' FACIL:50 387 Susquehanna Steam Electrf c Stations Unf t 1 > Pennsyl va                                       0500~087 50 388 Susquehanna             Steam Electr f c Statf one Unf t 2'P Pennsyl va                       05 'I)038 AUTH',NAME           AUTHOR AFFILIATTON CURTIS N ~ W ~
E              Pennsyl vanf a Power L Lf ght Co ~
RECIP ~ NAMEl         RECIPIENT AFFILIATION GRIERiB ~ H ~         Region         ii Phfladelphfar     Office'f                     the Director (81/03/01)


==SUBJECT:==
==SUBJECT:==
Interim deficiency rept re lack of required special conduit separation for certain-safety>>rel'ated electrical cfrcuftsr fnftfally r epor'ted on 810408 Safety related electrical circuits will be correctly separated, DISTRIBUTION CODE':: BOI9S'OPIES RECEIVEDiLTR
Interim deficiency rept re lack of required special conduit separation   for certain- safety>>rel'ated electrical cfrcuftsr fnftfally r epor'ted on 810408 Safety related electrical circuits will be correctly separated, DISTRIBUTION CODE'::   BOI9S'OPIES RECEIVEDiLTR ~NCI./                                             SIZE TITLE,: Construction     Deficiency Report (10CFR50 55K)                   ~
~NCI./SIZE TITLE,: Construction Deficiency Report (10CFR50~55K)NOTES!Send IEE 3 copfes FSAR 5 al 1 amends,1 cytBWR>>LRG PM(L RIB')Send IEE 3 copies FSAR 8 all amends,i cy:BWR~LRG PM(L~RIB)05000387 05000388 RECIPIENT ID'ODE/NAMEI ACTION: A/D LICENSNG 04 LIC BR¹2 LA 06 INTERNAL'SLBP/J',HARD EDO 8 STAFF 19 HYD/GEO BR 22'E/EES MPA 20 OELD 21 QA BR 14 STANDRDS DEY 21 COPIES'TTR'NCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT'D CODE/NAME" LIC BR¹2'C 05 STARKERS 07 D/DIR HUM FAC15'QUIP QUAL BR1 1 ILE Oo LIC QUAL'R 12'RC PDR 02'REV 13 ,EG FILE 01 COPIES LTTR'NCI.1 1 1 1 1 1 f 1 1 1 1 1 i.1 1 1 1 1 EXTERNAL: ACRS NSIC 1 6.08 16 16 1 1 LPDR 03 1 1 gag 10 1981$v'g TOTAL NUMBER.OF COPIES REQUIRED: LTTR~ENCL TWO NORTH NINTH STREET, ALLENTOWN, PA.18101 PHONE~(215)7/0-5151 NORMAN W.CURTIS Vice pfesidenl-Engineeting d Construction-Nuclear 770 5381 June 5, 1981 Mr.Boyce H.Grier Director, Region I U.S.Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 r-'(gyes,', S 1aI 0r C0 SUSQUEHANNA STEAM ELECTRIC STATION FINAL REPORT OF A DEFICIENCY RELATING TO ELECTRICAL SEPARATION ER's 100450/100508 FILES 840-4/900-10 PLA-827
NOTES!Send     IEE 3 copfes           FSAR 5   al 1 amends,1           cytBWR>>LRG PM(L RIB')               05000387 Send   IEE 3 copies           FSAR 8   all amends,i           cy:BWR~LRG PM(L ~ RIB)             05000388 RECIPIENT                 COPIES'            RECIPIENT'D COPIES ID'ODE/NAMEI                 TTR'NCL                      CODE/NAME"                LTTR'NCI.
ACTION:     A/D LICENSNG 04                 1      1    LIC           BR  ¹2'C          05        1    1 LIC  BR ¹2 LA 06               1      1    STARKERS                          07        1    1 INTERNAL'SLBP/J',HARD                               1    D/DIR            HUM                      1    1 f
FAC15'QUIP EDO   8 STAFF     19             1      1                      QUAL BR1              1        1 HYD/GEO BR                       1      1    ILE                              Oo        1    1 22'E/EES 1       1     LIC QUAL'R                                  1    1 02' 12'RC MPA            20              1      1                    PDR                         i. 1 OELD            21              1       1                         REV 13                1     1 QA BR            14            1       1     ,EG          FILE              01        1     1 STANDRDS DEY 21                  1       1 EXTERNAL: ACRS               1       6. 16     16     LPDR                              03        1     1 NSIC            08              1       1 gag 10 1981 TOTAL NUMBER. OF COPIES REQUIRED: LTTR                   ~$      v'g    ENCL


==Dear Mr.Grier:==
TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101        PHONE~  (215) 7/0-5151 NORMAN W. CURTIS Vice pfesidenl-Engineeting d Construction-Nuclear 770 5381 June 5, 1981                                                            r Mr. Boyce H. Grier Director, Region U. S.
This letter serves to provide the Commission with an interim report of a deficiency involving the lack of required special conduit separation for certain safety-related electrical circuits.The deficiency was originally reported to the NRC iTL General Electric letter TRR-26-81/MPN-065-91, dated April 8, 1981 under the provisions of 10 CFR 21.Recognizing its'esponsibility to review the condition for reportability under 10 CFR 50.55(e), PP&L determined this deficiency to be potentially reportable.
I Nuclear Regulatory Commission
Consequently, Mr.C.Z.McVicker of PPaL so advised NRC Region I Inspector Mr.L.Narrow by telephone on April 14, 1981.The attachment to this letter contains a desription of the deficiency, its cause, safety implications, and the corrective action taken and planned.The information is submitted as a final report pursuant to the provisions of 10 CFR 50.55(e).We trust the Commission will find the information forwarded by this letter to be satisfactory.
                                                                          -'(gyes,              ',
Very truly yours, N.W.Curtis Vice President-Engineering 6 Construction-Nuclear yoi~5 FLW/WHG/vs'.
631 Park Avenue King of Prussia,              PA    19406                            0r S 1aI C0 SUSQUEHANNA STEAM ELECTRIC STATION FINAL      REPORT OF A DEFICIENCY RELATING TO ELECTRICAL SEPARATION ER's 100450/100508                        FILES 840-4/900-10 PLA-827
PENNSYLVANIA POWER iL LIGHT COMPANY Mr.Boyce H.Grier cc: Mr.Victor Stello (15)Director-Office of inspection
 
&Enforcement U.S.Nuclear Regulatory Commission Washington, D.C.20555 Mr.G.McDonald, Director (1)Office of Management Znformation
==Dear Mr.         Grier:==
&Program Control U.S.Nuclear Regulatory Commission Washington, D.C.20555 Mr.Gary Rhoads U.S.Nuclear Regulatory Commission P.O.Box 52 Shickshinny, PA 18655  
 
.~Attachment to PLA-827 SUB JECT Special electrical separation for the G.E.supplied Power Generation Control Complex involving the High Pressure Coolant Injection (HPCX), Reactor Core Isolation Cooling (RCIC), and Automatic Depressurization Systems (ADS)as identified in NRC ZGE Information Notice 79>>32.DESCRIPTION OF DEFICIENCY The deficiency involves the omission of conduit on electrical wiring to the HPCX inboard steam isolation valve E41-F002 and RCIC inboard steam isolation valve E51-F007.The installation of this condui.t is required to meet a specific requirement of the General Electric specification for electrical separation, applicable to Susquehanna 1 6 2.This deficiency relates to both the GE scope of supply (i.e.the Power Generation Control Complex)and the Bechtel Corp.scope of supply (i.e.Balance of Plant)for these circuits.Note: Although GE's Part 21 report (ref.TRR-26-81/MFN-065-81 dated 4/8/81)included ADS circuits in the scope of the reported deficiency, as did their generic response to NRC Z&E Information Notice 79-32, ADS has not been included in the scope of thi.s report because the Susquehanna ADS design, unlike earlier vintage plants, has two redundant power and logic trains and is capable of operation with a failure in either division.CAUSE The General Electric specification for electrical separation applicable to Susquehanna SES, requires that conduit be installed to provide special separation of the HPCZ and RCXC inboard steam line isolation valve circuits from other circuits assigned to the same division (see attached diagram of Fig.5 of G.E.Doc.22A3052).The intent, of this special separation require-ment is to provide conduit separation of the"Division I-X" circuit from other Division X circuits and conduits separation of the"Division ZZ-X" circuits from other Division ZI circuits thereby preventing a postulated single electrical failure from disabling both the HPCX and RCXC systems.GE and Bechtel Corp., for their respective scopes of supply, failed to incorporate this special electrical separation requirement into the design output documents they prepared and issued for the manufacture and construction of the Susquehanna HPCZ and RCZC systems.ANALYSIS OF SAFETY IMPLICATIONS The intent of the GE requirement for special separation using conduit on the subject HPCX and RCIC circuits was to prevent a postulated single electrical failure from disabling both the HPCX and RCIC systems.There is a possibility that a fire could cause a hot-short circuit in the cable to the HPCX inboard isolation valve (Division I)resulting in the closure of this valve and at the same time, disabling the RCZC system which is essentially a Division X system.This scenario could'result in a loss of capability in both the HPCX and RCIC'Page 1 of 2 Attachment to PLA-827 systems.The RCIC system is designed to provide Reactor Makeup Water during a loss of offsite power and to establish and maintain reactor water level during shutdown conditions.
This      letter serves to provide the Commission with an interim report of a deficiency involving the lack of required special conduit separation for certain safety-related electrical circuits. The deficiency was originally reported to the NRC iTL General Electric letter TRR-26-81/MPN-065-91, dated April 8, 1981 under the provisions of 10 CFR 21. Recognizing its to review the condition for reportability under 10 CFR 50.55(e),         'esponsibility PP&L determined this deficiency to be potentially reportable.                             Consequently, Mr. C. Z. McVicker of PPaL so advised NRC Region I Inspector Mr. L. Narrow by telephone on             April 14, 1981.
Although the ADS would still be available in the event of RCIC'system failure, it is not the intended function of the ADS to be used as a backup to RCIC during a reactor shutdown.At Susquehanna, the ADS is provided with two redundant power and logic trains and would always be available for a loss of a single division.Therefore, no deficiency exists in the ADS design.This has been confirmed through discussions with GE in May, 1981.PPGL has determined, however, that the lack of installed conduit to provide separation for the electrical circuits to the HPCI and RCIC inboard isolation valves does represent a significant.
The     attachment to this letter contains                 a desription of the deficiency, its cause,       safety implications, and the corrective action taken and planned.
deficiency in final design as released for construction and is therefore reportable under 10 CFR 50.55(e).CORRECTIVE ACTION G.E.site personnel have written Field Deviation Disposition Requests (FDDR-522-12 and FDDR-KRX-542-9) to enclose the circuits for valve E41-F002 from panel H12P617 to the PGCC termination cabinet and the circuits for valve E51-F007 from panel H12P617 to the termination cabinet in flexible conduit.Bechtel has issued Design Change Package (DCP)308.1 to the field for the rework required to enclose the remainder of the HPCI and RCXC inboard valve control circuits in conduit.The Bechtel and GE design documents identified above will provide the direction to install the conduit necessary to achieve compliance with the cited special separation recpxirement for'he HPCX and RCIC systems.Page 2 of 2 Isolntion Inputs Temp 6 Flow Div I Mireu~y RCIC Logic Cabinet lncl.Timer)Isolation Inputs Temp 6 Flo" Div II Mir awny Lnclai"urc Isol valves Logic Cabinet I>>cl.Timur I RIG I RL~r-L Durrier+Isolation Inputs Temp 6 Flow I D~BIIS\~Barrier.nr nclosurc Isol Valves Logic Cabinet Incl.Tlcccr Isolation Inputs Temp S Flow IIPC'ogic Chb inc: t (I>>cl.Timer)P z Div I DC Poucr DC>ICC Div I Mireuay Div"II-X" Conduit AC HCC RCIC Otlicr Isol I laol Valve Valve I tarte c Stnrtci Div II Mireway Div II AC Power Div I Mirew~y p iv"I-X" Conduit Div I AC Poucr Div II DC Pow AC YACC Other~lll'CI Isol IIsol Valve l Valve itrta'sP tnrtcrs DC lICC Div II Mircway~rrc r-I n N)V To RCIC Turb F gp P Div"II-X" Conduit To/ther Div II Isol Valvec DRIMELI, F-007 To Othe:i Div I Iscl Valves Div"I-X" Co>>duit'C F+~+'RVIy.LL.
The     information is submitted               as a final report pursuant to the provisions of   10 CFR       50.55(e).
DC To IIPCI F-003 Turb 0 o n h x 0 ri Z x 0 h)I CO M PEGNIB 5 IIPCJ:/RCIC Sl;PAIIATIOH SCIIEME r~l a n eg C}}
We   trust the       Commission         will find the information forwarded by this         letter to   be   satisfactory.
Very     truly yours, N. W.     Curtis                                                                               yoi~
Vice President-Engineering                   6 Construction-Nuclear                                       5 FLW/WHG/vs'.
PENNSYLVANIA POWER       iL LIGHT COMPANY
 
Mr. Boyce H. Grier cc: Mr. Victor Stello (15)
Director-Office of inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. McDonald, Director (1)
Office of Management Znformation & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P. O. Box 52 Shickshinny, PA 18655
 
                      . ~
Attachment to PLA-827 SUB JECT Special electrical separation for the   G.E. supplied Power Generation Control Complex   involving the High Pressure Coolant Injection (HPCX), Reactor Core Isolation Cooling (RCIC), and Automatic Depressurization Systems (ADS) as identified in NRC ZGE Information Notice 79>>32.
DESCRIPTION OF DEFICIENCY The deficiency involves the omission of conduit   on electrical wiring to the HPCX inboard steam isolation valve E41-F002 and   RCIC inboard steam isolation valve E51-F007. The installation of this condui.t is required to meet a specific requirement of the General Electric specification for electrical separation, applicable to Susquehanna 1 6 2. This deficiency relates to both the GE scope of supply (i.e. the Power Generation Control Complex) and the Bechtel Corp. scope of supply (i.e. Balance of Plant) for these circuits.
Note:   Although GE's Part 21 report (ref. TRR-26-81/MFN-065-81 dated 4/8/81) included ADS circuits in the scope of the reported deficiency, as did their generic response to NRC Z&E Information Notice 79-32, ADS has not been included in the scope of thi.s report because the Susquehanna ADS design, unlike earlier vintage plants, has two redundant power and logic trains and is capable of operation with a failure in either division.
CAUSE The General Electric specification for electrical separation applicable to Susquehanna SES, requires that conduit be installed to provide special separation of the HPCZ and RCXC inboard steam line isolation valve circuits from other   circuits assigned to the same division (see attached diagram of Fig. 5 of   G.E. Doc. 22A3052). The intent, of this special separation require-ment is to provide conduit separation of the "Division I-X" circuit from other Division X circuits and conduits separation of the "Division ZZ-X" circuits from other Division ZI circuits thereby preventing a postulated single electrical failure from disabling both the HPCX and RCXC systems. GE and Bechtel Corp.,
for their respective scopes of supply, failed to incorporate this special electrical separation requirement into the design output documents they prepared and issued for the manufacture and construction of the Susquehanna HPCZ and RCZC systems.
ANALYSIS OF SAFETY IMPLICATIONS The intent of the   GE requirement for special separation using conduit on the subject   HPCX and RCIC   circuits was to prevent a postulated single electrical failure   from disabling both the HPCX and RCIC systems. There is a possibility that a fire could cause a hot-short circuit in the cable to the HPCX inboard isolation valve (Division I) resulting in the closure of this valve and at the same time, disabling the RCZC system which is essentially a Division X system.
This scenario could'result in a loss of capability in both the HPCX and RCIC Page 1 of 2
 
Attachment to PLA-827 systems. The RCIC system is designed to provide Reactor Makeup Water during a loss of offsite power and to establish and maintain reactor water level during shutdown conditions. Although the ADS would still be available in the event of RCIC 'system failure, it is not the intended function of the ADS to be used as a backup to RCIC during a reactor shutdown. At Susquehanna, the ADS is provided with two redundant power and logic trains and would always be available for a loss of a single division. Therefore, no deficiency exists in the ADS design. This has been confirmed through discussions with GE in May, 1981. PPGL has determined, however, that the lack of installed conduit to provide separation for the electrical circuits to the HPCI and RCIC inboard isolation valves does represent a significant. deficiency in final design as released for construction and is therefore reportable under 10 CFR 50.55(e) .
CORRECTIVE ACTION G.E. site personnel have written Field Deviation Disposition Requests (FDDR-522-12 and FDDR-KRX-542-9) to enclose the circuits for valve E41-F002 from panel H12P617 to the PGCC termination cabinet and the circuits for valve E51-F007 from panel H12P617 to the termination cabinet in flexible conduit.
Bechtel has issued Design Change Package (DCP) 308.1 to the field for the rework required to enclose the remainder of the HPCI and RCXC inboard valve control circuits in conduit.
The Bechtel and GE design documents identified above will provide the direction to install the conduit necessary to achieve compliance with the cited special separation recpxirement   for'he HPCX and RCIC systems.
Page 2 of 2
 
P Isolntion                       Isolation                                  Isolation                        Isolation Inputs                          Inputs                                      Inputs                          Inputs                        z Temp 6   Flow                   Temp 6     Flo"                           Temp 6    Flow                  Temp S    Flow Div I RIG I
I   RL~ r             Div II                                    I D~         BIIS Mireu~y                                            Mirawny                                    \
L Durrier  +                                                          ~Barrier
                                                                                                        .nr RCIC  Logic      Lnclai"urc    Isol valves                                Isol Valves       nclosurc      IIPC'ogic Cabinet                        Logic Cabinet                              Logic Cabinet                    Chb inc: t lncl. Timer)                                                                                                  (I>>cl.
I>>cl. Timur                                Incl. Tlcccr                      Timer    )
                                                                                                                                                        ~ rrc Div I                                                                                                                               r Mireuay                                   Div  II          Div I          p  iv "I-X"                     Div  II Div "II-X"              Mireway         Mirew~y               Conduit                        Mircway                -I Div I                             Conduit DC  Poucr AC HCC Div   II                                   n DC     Pow RCIC      Otlicr                          Other~ lll'CI DC
          >ICC Isol     I  laol        Div II    Div I  Isol IIsol                            DC lICC Valve I
Valve      AC Power AC Poucr Valve l Valve        AC tarte  c  Stnrtci                        itrta'sP tnrtcrs YACC Div "II-X" Div "I-X" Conduit           To /ther                                   Co>>duit Div II                       To Othe:i Div   I Isol  Valvec Iscl                     'C Valves                                                            0 o
N)V                                                                                                                              h n DC x
0 ri To                                                                                                                                                Z To IIPCI RCIC Turb F    gp P          DRIMELI,    F  -007                                F +~+'RVIy.LL.                     F-003           Turb         x 0
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Latest revision as of 16:28, 3 February 2020

Interim Deficiency Rept Re Lack of Required Special Conduit Separation for Certain safety-related Electrical Circuits, Initially Reported on 810408.Safety-related Electrical Circuits Will Be Correctly Separated
ML18030A048
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 06/05/1981
From: Curtis N
PENNSYLVANIA POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, PLA-827, NUDOCS 8106090406
Download: ML18030A048 (6)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM. (RIDS)

ACCESSION NBR:8106090406 DOC ~ DATE! 81/06/05 NOTARIZED: NO DOCKE.T' FACIL:50 387 Susquehanna Steam Electrf c Stations Unf t 1 > Pennsyl va 0500~087 50 388 Susquehanna Steam Electr f c Statf one Unf t 2'P Pennsyl va 05 'I)038 AUTH',NAME AUTHOR AFFILIATTON CURTIS N ~ W ~

E Pennsyl vanf a Power L Lf ght Co ~

RECIP ~ NAMEl RECIPIENT AFFILIATION GRIERiB ~ H ~ Region ii Phfladelphfar Office'f the Director (81/03/01)

SUBJECT:

Interim deficiency rept re lack of required special conduit separation for certain- safety>>rel'ated electrical cfrcuftsr fnftfally r epor'ted on 810408 Safety related electrical circuits will be correctly separated, DISTRIBUTION CODE':: BOI9S'OPIES RECEIVEDiLTR ~NCI./ SIZE TITLE,: Construction Deficiency Report (10CFR50 55K) ~

NOTES!Send IEE 3 copfes FSAR 5 al 1 amends,1 cytBWR>>LRG PM(L RIB') 05000387 Send IEE 3 copies FSAR 8 all amends,i cy:BWR~LRG PM(L ~ RIB) 05000388 RECIPIENT COPIES' RECIPIENT'D COPIES ID'ODE/NAMEI TTR'NCL CODE/NAME" LTTR'NCI.

ACTION: A/D LICENSNG 04 1 1 LIC BR ¹2'C 05 1 1 LIC BR ¹2 LA 06 1 1 STARKERS 07 1 1 INTERNAL'SLBP/J',HARD 1 D/DIR HUM 1 1 f

FAC15'QUIP EDO 8 STAFF 19 1 1 QUAL BR1 1 1 HYD/GEO BR 1 1 ILE Oo 1 1 22'E/EES 1 1 LIC QUAL'R 1 1 02' 12'RC MPA 20 1 1 PDR i. 1 OELD 21 1 1 REV 13 1 1 QA BR 14 1 1 ,EG FILE 01 1 1 STANDRDS DEY 21 1 1 EXTERNAL: ACRS 1 6. 16 16 LPDR 03 1 1 NSIC 08 1 1 gag 10 1981 TOTAL NUMBER. OF COPIES REQUIRED: LTTR ~$ v'g ENCL

TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE~ (215) 7/0-5151 NORMAN W. CURTIS Vice pfesidenl-Engineeting d Construction-Nuclear 770 5381 June 5, 1981 r Mr. Boyce H. Grier Director, Region U. S.

I Nuclear Regulatory Commission

-'(gyes, ',

631 Park Avenue King of Prussia, PA 19406 0r S 1aI C0 SUSQUEHANNA STEAM ELECTRIC STATION FINAL REPORT OF A DEFICIENCY RELATING TO ELECTRICAL SEPARATION ER's 100450/100508 FILES 840-4/900-10 PLA-827

Dear Mr. Grier:

This letter serves to provide the Commission with an interim report of a deficiency involving the lack of required special conduit separation for certain safety-related electrical circuits. The deficiency was originally reported to the NRC iTL General Electric letter TRR-26-81/MPN-065-91, dated April 8, 1981 under the provisions of 10 CFR 21. Recognizing its to review the condition for reportability under 10 CFR 50.55(e), 'esponsibility PP&L determined this deficiency to be potentially reportable. Consequently, Mr. C. Z. McVicker of PPaL so advised NRC Region I Inspector Mr. L. Narrow by telephone on April 14, 1981.

The attachment to this letter contains a desription of the deficiency, its cause, safety implications, and the corrective action taken and planned.

The information is submitted as a final report pursuant to the provisions of 10 CFR 50.55(e).

We trust the Commission will find the information forwarded by this letter to be satisfactory.

Very truly yours, N. W. Curtis yoi~

Vice President-Engineering 6 Construction-Nuclear 5 FLW/WHG/vs'.

PENNSYLVANIA POWER iL LIGHT COMPANY

Mr. Boyce H. Grier cc: Mr. Victor Stello (15)

Director-Office of inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. McDonald, Director (1)

Office of Management Znformation & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P. O. Box 52 Shickshinny, PA 18655

. ~

Attachment to PLA-827 SUB JECT Special electrical separation for the G.E. supplied Power Generation Control Complex involving the High Pressure Coolant Injection (HPCX), Reactor Core Isolation Cooling (RCIC), and Automatic Depressurization Systems (ADS) as identified in NRC ZGE Information Notice 79>>32.

DESCRIPTION OF DEFICIENCY The deficiency involves the omission of conduit on electrical wiring to the HPCX inboard steam isolation valve E41-F002 and RCIC inboard steam isolation valve E51-F007. The installation of this condui.t is required to meet a specific requirement of the General Electric specification for electrical separation, applicable to Susquehanna 1 6 2. This deficiency relates to both the GE scope of supply (i.e. the Power Generation Control Complex) and the Bechtel Corp. scope of supply (i.e. Balance of Plant) for these circuits.

Note: Although GE's Part 21 report (ref. TRR-26-81/MFN-065-81 dated 4/8/81) included ADS circuits in the scope of the reported deficiency, as did their generic response to NRC Z&E Information Notice 79-32, ADS has not been included in the scope of thi.s report because the Susquehanna ADS design, unlike earlier vintage plants, has two redundant power and logic trains and is capable of operation with a failure in either division.

CAUSE The General Electric specification for electrical separation applicable to Susquehanna SES, requires that conduit be installed to provide special separation of the HPCZ and RCXC inboard steam line isolation valve circuits from other circuits assigned to the same division (see attached diagram of Fig. 5 of G.E. Doc. 22A3052). The intent, of this special separation require-ment is to provide conduit separation of the "Division I-X" circuit from other Division X circuits and conduits separation of the "Division ZZ-X" circuits from other Division ZI circuits thereby preventing a postulated single electrical failure from disabling both the HPCX and RCXC systems. GE and Bechtel Corp.,

for their respective scopes of supply, failed to incorporate this special electrical separation requirement into the design output documents they prepared and issued for the manufacture and construction of the Susquehanna HPCZ and RCZC systems.

ANALYSIS OF SAFETY IMPLICATIONS The intent of the GE requirement for special separation using conduit on the subject HPCX and RCIC circuits was to prevent a postulated single electrical failure from disabling both the HPCX and RCIC systems. There is a possibility that a fire could cause a hot-short circuit in the cable to the HPCX inboard isolation valve (Division I) resulting in the closure of this valve and at the same time, disabling the RCZC system which is essentially a Division X system.

This scenario could'result in a loss of capability in both the HPCX and RCIC Page 1 of 2

Attachment to PLA-827 systems. The RCIC system is designed to provide Reactor Makeup Water during a loss of offsite power and to establish and maintain reactor water level during shutdown conditions. Although the ADS would still be available in the event of RCIC 'system failure, it is not the intended function of the ADS to be used as a backup to RCIC during a reactor shutdown. At Susquehanna, the ADS is provided with two redundant power and logic trains and would always be available for a loss of a single division. Therefore, no deficiency exists in the ADS design. This has been confirmed through discussions with GE in May, 1981. PPGL has determined, however, that the lack of installed conduit to provide separation for the electrical circuits to the HPCI and RCIC inboard isolation valves does represent a significant. deficiency in final design as released for construction and is therefore reportable under 10 CFR 50.55(e) .

CORRECTIVE ACTION G.E. site personnel have written Field Deviation Disposition Requests (FDDR-522-12 and FDDR-KRX-542-9) to enclose the circuits for valve E41-F002 from panel H12P617 to the PGCC termination cabinet and the circuits for valve E51-F007 from panel H12P617 to the termination cabinet in flexible conduit.

Bechtel has issued Design Change Package (DCP) 308.1 to the field for the rework required to enclose the remainder of the HPCI and RCXC inboard valve control circuits in conduit.

The Bechtel and GE design documents identified above will provide the direction to install the conduit necessary to achieve compliance with the cited special separation recpxirement for'he HPCX and RCIC systems.

Page 2 of 2

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