ML20058N607

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Environ Qualification Rept for Class 1E Equipment for Shoreham Nuclear Power Station Unit 1 Lilco
ML20058N607
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/30/1983
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20058N600 List:
References
SE-90-023, SE-90-023-R01, SE-90-23, SE-90-23-R1, NUDOCS 9008140240
Download: ML20058N607 (11)
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r-SE-90-023, Rev. 1-Attacinant B

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Revision 1 - January 1982 Revision 2 - May 1982 Revision 3 - August:1982 Revision 4 - October 1982-6 Revision 5 - June 1983 4

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', EVIPCtNENTAL CGLTFICATION REFORT -

FOR CIASS'IE EQUIPMENT

- i. g-SHORDIAM NUCLEAR POLER STATION - LHIT lt 14NG ISLAND LIGHTING COMPANY s.

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SE-90-023,.Revo :1-

- Attachment B.

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7JST OF APFETED PAGES

. REVISION.

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SE-90-023,:Rev. 1-n ;- ' Attachment B.

Page 4 of 12-SNPS-1 EQR. -

SGNUE

.'Ihis report is produced. for NFC review of the modified Enviseddal Qualification Program which is applicable to the Shoreham Nuclear Power Station-

, (STS)' defueled condition.

-;Should the plant status change in the future, a reconsideration of this report

, will precede this. change.

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1. 0 -- MJDITIED ENVIRJtNENTAL QUALIFICATIm PHOGRAM Based on the plant defueled condition, the possibility.of producing a'-

- harsh environnent is eliminated (Safety Evaluation 90-023)'. 'Iherefore ,-

all electrical equipnent (Safety Related Class 1E equipnent and equipment required by Regulatory Guide 1.97) are located in a mild envirorsnent and the environmental qualification of such equipnent isi not included within the scope of 10 CFR 50.49.

Should the plant status change in the future, a reconsideration of the basis for qulification must precede the plant's upgrade to operable :

status.

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.SE-90-023, Rev. 1' l a" '

Attachment B '! '

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, SNPS-1,.EQR .

s SECTION 2

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t c2.0~ }ODIFIED DEFINITION OF SAFTTY-PETATED ELTTRICAL

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.j The definition of " Electrical equipment important to safety," as.

defined-in 10 CPR 50.49- (b) (1) through (3), does apply to safety related equipaent at SNPS . However, the plant will not rely upon any' ,

electrical epipnent to remain functional during- and following design  !

basis events to'perfom functions I(i) through (iii) of Section (1)'of

10 CPR 50.49 due to the SNPS present defueled condition.-

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.Page 7 of 12-SNPS-1 EQR ,

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3.0. EDITIED DNIRONMENTAL 00NDfrICNS With the plant in its defueled condition the only applicable postulated accidents fran Chapter 15.of the USAR are:

Tuel Handling Accident IMIM Radwaste Tank Rupture The results of analysis determined chat the Total Integrated Dose (TID) on the refueling level for six fronth post accident duration is 32 rads, Gartra and Beta.

.The temperature and pressure conditions in the' plant are at ambient and'

- will not change due to any one of the accidents-postulated above.:

Therefore, the envirorrnents where safety related equipment is installed-will not be> significantly rnore-severe than normal envirorsnents- and can be considered a mild envirornnent.

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SE-90-023,Rev.ll-Attaclitent B -

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4.0- MODIFIED QUALIFICATIN STAMIS With the plant in the defueled condition, there is no EQ equiptent that :  ;

is relied upon to remain functional during and following design basis

. events. Therefore, operab'.lity codes' assigned to EQ equipnent par.

NUR E 0588 Appendix E ar< not applicable.

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SE-90-023, Rev. 1

- Attachment B Page 9 of 12

,V SNPS-1 EQR ,

SECTION 5 SURVEIMANCE AND MAINTDENCE The Shorehan surveillance and maintenance progrm will continue as is. However,

- the Environmental Qualification related maintenance, to maintain the equiptent

_ qualification status, will be inactivated as follows:

Engineering will halt the transnitting of the EQ related maintenance requirements to plant maintenance.

  • - Installation of non-qualified replacement parts will be allowed in qualified equipment.

' - No EQ related surveillances will be performed.

  • - All normal maintenarce required to maintain the equipment or systen functional will be performed.

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Page 10 of 12 SNPS-1-ECR' .

'"3 APPDOIX D -

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}ODIFIED RADIATION, Tl!2tPERA'IURE AND PRESSURE EATA Based on the plant present defueled condition the plant normal and-accident

' conditions are:

RE2ATIVE Temperature (F) Radiation (RADS) PRESSURE;  !!LMIDITE Normal- 79 III Insignificant (2) Atmospheric Not-Controlled 3

Accident 79 32(3) Atmospheric L Not-Controlled

.(1)~ LIIf0 Calculation No. CCI-036590 Revision O.

-(21 -The estimated 2 days full power operation in ecnparison to 40 years-operation results in insignificant backgrcund radiation.

~-(311 Calculation No. C-RPD-529 Revision O.

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SNPS-1 EQR ,

APPDOIX E

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E.0 , The analyses foming the basis for the Envirornental Qualification

+ ' Program;(EQP) modification are:

1. NED 4170024 Revision 0 " Radiological Safety Analysis"
1. Calculation No. C-RPD-529 Revision 0 "Offsite and Onsite Reactor

+> Building. Dose Rates Due.to FHA with Core Inventories as of June 15,.1989" t

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SE-90-023, Rev. 1

-!!l Attachment B-Page 12 of 12 i/

SNPS-1 EQR ,

.. i APPENDIX F ENVIRONMENTAL QUALIFICATION STATUS REPORP  !

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I w  :-'!his caponent of the EnvircrYnental Qualification Progran (EOP) will be

' deactivated as the result of EQP nodification. Should the plant status change ]

in the future, a reconsideration of the EQP nodification will pid this change.. l 1

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