ML20072R547

Forwards Revised Justification for Continued Operation for Environ Qualification of safety-related Electrical Equipment,Per 830125 Response to NRC 821220 Request.Barton Differential Pressure Switch Component Matls Identified

ML20072R547
Person / Time
Site:	Brunswick
Issue date:	04/01/1983
From:	Utley E CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
References
LAP-83-76, NUDOCS 8304060076
Download: ML20072R547 (8)

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• Caronna Power & Light E ; c,-

P. O. Box 1551

• Raleigh, N. C. 27002 APR 011983 SERIAL: LAP-83-76 E.E.UTLEY Executive Vice President Power Supply and Engineering & Construction Director of Nuclear Reactor Regulation Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT REVISED JUSTIFICATIONS FOR CONTINUED OPERATION

Dear Mr. Vassallo:

By letter dated January 25, 1983, Carolina Power & Light Company (CP&L) submitte.d a 30-day response to the NRC Staff's December 20, 1982 request for justifications for continued operation (JCOs) for the Brunswick Steam Electric Plant, Unit Nos. I and 2. The information provided a technical basis for the continued operation of the Brunswick Plant for that equipment which has been determined by the Staff to be either (1) unqualified, or (2) as not having qualification established and for which JCOs have not been previously submitted.

It has been determined, following further CP&L review, that revisions are needed to clarify certain JCOs provided in our January 25, 1983 submittal. Enclosed are revised JCOs that supersede certain of those provided by the January 25, 1983 response. Carolina Power & Light Company continues to believe that there are no known concerns relating to the environmental qualification of safety-related electrical equipment which would interfere with safe, continued operation of the Brunswick Plant.

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8304060076 830401 l PDR ADOCK 05000324 l P PDR 1

D. B. Vassallo  ;

If you have any questions concerning thic . response, please contact our staff.

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Yours very truly, '

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Utley WRM/kjr (6454WRM)

Enclosures-

! cc: Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII) l Mr. S. D. MacKay (NRC) i 4

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> TER ITEM NUMBER 56  :

l l-BARTON PRESSURE SWITCH MODEL 288 Plant ID Numbers:

B21-PS-N021B B21-PS-N021D l-E41-P DS-N004 l-E41-PDS-N005 1-E51-PDS-N017 j 1-E51-PDS-N018 i

These pressure switches have been replaced with Rosemount Pressure Transmitters '(Part Numbers ll52GP and 1152DP Series). The Rosemount pressure transmitters are qualified for use at BSEP (

Reference:

United Engineers Report Number UC-33229, dated August 20, 1982).

Therefore, continued operation is justified.

NOTE: New plant ID numbers were assigned to the replacement pressure transmitters as follows (respectively):

B21-PT-N021B B21-PT-N021D l-E41-PDI-N004 1-E41-PDT-N005 1-E51-PDT-N017 1-E51-P DT-N018 l-l l

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TER ITEM NUMBERS 56, 57, AND 59 '

i' BARTON DIFFERENTIAL PRESSURE. INDICATING SWITCH MODELS 288/288A/289A' Plant ID Numbers:

4 CAC-P DS-4222 E41-PS-N00 LA 2-E41-P DG-N004 CAC-PDS-4223 E41-PS-N001B 2-E41-PDS-N005 -

a E41-PS-N001C 2-E51-PDS-N017' E41-PS-N001D 2-E51-PDS-N018 I

Component materials of the Barton differential pressure switches.

have been identified. These materials have been evaluated per D0R guidelines and by applying Arrhenius techniques. Results of this analysis indicate that 4

the non-metallic componeats have greater than 1.5 x 10 years of expected life at the maximum . reactor building temperature of 104*F. _ The pressure switch non-metallic waterials are exposed to the ~ plant postulated accident

] temperature peak of 180*F 'for thirty-five (35) minutes. The accident temperature then decreases to 125'F within three (3) . hours of event initiation. With an expected life of 96 years at 180*F, the pressure ' switch -

non-metallic materials are insensitive to thermal degradation for the required 1

operating period.

Additionally, similar switches have been successfully tested for six (6) hours at 100% RH, 7 inches W.G. with tempergtures from 40*F. to 212*F.

Also, the radiation testing performed (3.6 g 10 rads gamma) on similar switches exceeds the postulated TID (1 x 10 rads gamma) for these switches 4 (

Reference:

Patel Report Number PEI-TR-83-4-22) .

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Therefore, continued operation is justified.

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l TER ITEM NUMBERS 60, 61, AND 63 STATIC-0-RING PRESSURE SWITCH MODEL SN-AA3--X9-STT AND 12NAA4-X10TT Plant ID Numbers: E21-PS-N008A E21-PS-N009A Ell-PS-N010A Ell-PS-N019A E21-PS-N008B .E21-PS-N0098- Ell-PS-N0108 Ell-PS-N019B Ell-PS-N010C Ell-PS-N019C Ell-PS-N010D E11-PS-N019D Ell-PS-N011A C71, C72-PS-N002A Ell-PS-N011B C71, C72-PS-N002B Ell-PS-N011C C71, C72-PS-N002C E11-PS-N0llD C71, C72-PS-N002D Component materials of the Static-0-Ring - Pressure' Switches _ have been identified. These materials have been evaluated per D0R guidelines and by-applying Arrhenius techniques. Results-of this analysis indicate that each of the non-metallic materials (Viton A, Neoprene, General Purpose Phenolic and Ethylene Propylene rubber) has an expected life in excess of 261 years at the a maximum reactor building temperature c f 104*F. The switch non-metallic -

materials are exposed to the plant postulated accident temperature peak of 192*F for a maximum of 10 minutes. The accident temperature then decreases to 125*F within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of event initation. With an expected life of 564 days ~at 192*F, the switch non-metallic materials are insensitive to thermal degradation for the required operating period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Also, similar switches were tested at high humidity for 100 days at 150*F with no f ailures observed. Prior to the accident testing these' switches had been thermally-aged for 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> at 80*C.

Additionally, at the highest dose rate during the initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident, the total accumulated dose of the non-metallies will be significantly less than the lowest radiation damage threshold. (

Reference:

Patel Report: PEl-TR-83-4-18).

Therefore, continued operation is justified.

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TER ITEM NUMBER 62 STATIC-O-RING PRESSURE SWITCH MODEL 6N-AA21-X9-SVTI Plant ID Numbers: E41-PS-N010 Component, materials of the Static-O-Ring Pressure Switches have been identified. These materials have been evaluated per DOR guidelines and by applying Arrhenius techniques. Results of this analysis indicate that each of the non-metallic materials (Viton A, Ne' oprene, General Purpose Phenolic and Ethylene Propylene rubber) has a expected life in excess of 261 years at the maximum reactor building temperature of 104*F. The switch non-metallic materials are exposed to the plant postulated accident temperature peak of 293*F for a maximum of 2 minutes. The accident temperature then_ decreases to 125'F within 30 minutes of event initiation. With an. expected life of 164 '

hours at 293*F, the switch non-metallic materials are insensitive to thermal degradation for the required operating period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Also, similar 1 switches were tested at high humidity for 100 days at 150*F with no -failures ,

observed. Prior to the accident testing these switches had been thermally aged for 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> at 80*C.

Additionally, at the highest dose rate during the initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident, the total accumulated dose of the non-metallies will be significantly less than the lowest radiation damage threshold. (

Reference:

Patel Report: PEI-TR-83-4-18) .

Therefore, continued operation is justified.

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TER ITEM NUMBER 70 i BARKSDALE PRESSURE SWITCM MODEL B2T-M12SS.  !

l Plant ID Numbers: B21-PS-N021A I B21-PS-N021C B21-PS-N023A ~ '

B21-PS-N023E

'B21-PS-N023C

(- B21-PS-N023D l

These pressure switches have been replaced with Rosemount Pressure Transmitters (Part Numbers 1152GP' Series). The Rosemount pressure transmitters are qualified for use at BSEP (

Reference:

Un ited Engineers Report Number UC-33229, dated August 20, 1982).

Therefore, continued operation is justified.

i NOTE: New plant .ID numbers were assigned to the replacement pressure i transmitters as follows (respectively)* i l

B21-PT-N021A B21-PT-N021C B21-PT-N023A B21-PT-N023B B21-PT-N023C B21-PT-N023D .

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TER ITEM NUMBERS 84, 86, AND 87 l.

YARWAY LEVEL SWITCH MODEL 4418C/4418EC-Plant ID Numbers: ,

• B21-LS-N021A B21-LS-NO31A-l *B21-LS-N021C B21-LS-N031B B21-LS-N024A 'B21-LS-NO31C B21-LS-N024B B21-LS-NO31D B21-LS-N025A B21-LS-N042A B21-LS-N025B B21 -LS-N042B B21-LITS-N036 B21-LITS-NO37

• Items deleted from the list of safety-related equipment These level switches have been replaced with Rosemount Pressure Transmitters (Part Numbers 1152DP Series and 1152GP Series). ' The Rosemount pressureftransmitters are qualified for use at BSEP'(

Reference:

Un ited Engineers Report Number UC-33229, dated August 20, 1982).

Th'erefore, continued operation is justified.

NOTE: New plant ID numbers were assigned to th2 replacement pressure transmitters as follows (respectively):

B21-LT-N024A1, A2 B21-LT-N024B1, B2 B21-LT-N025A1, A2 B21-LT-N025B1, B2 B21-LT-N031A B21-LT-N031B B21-LT-N031C B21-LT-N031D B21-LT-N042A B21-LT-N042B B21-LT-N036 B21-LT-N037 I

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