ML20040H410

Submits Addl Info Re Environ Qualification of safety-related Electrical Equipment,In Response to NRC

ML20040H410
Person / Time
Site:	Maine Yankee
Issue date:	02/11/1982
From:	Garrity J Maine Yankee
To:	Clark R Office of Nuclear Reactor Regulation
References
IEB-79-01B, IEB-79-1B, MN-82-25, NUDOCS 8202180222
Download: ML20040H410 (25)

Text

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EDISON DRIVE AUGUSTA, MAINE 04336 ce (207) 623-3521 February 11, 1982

• O MN-82-25 bl, Y

United States Nuclear Regulatory Commission Washington, D. C. 20555 3

Division of Licensing

(

- / ;ggg["g~S Attention:

Office of tbclear Reactor Regulation

{U n.'

,,# g Mr. Robert A. Clark, Chief

,e a

n-Operating Reactors, Branch No. 3

References:

(a) License No. DPR-36 (Docket No. 50-309)

(b) USNRC Letter to MYAPCo dated October 24, 1980, Order for Modification of License (c) MYAPCo Letter to USNRC, dated October 31, 1980 (WMY 80-145)

(d) MYAPCo Letter to USNRC, dated September 2, 1981 (WMY 81-133)

(e) USNRC Letter to MYAPCo, dated January 8,1982

Subject:

Environmental Qualification of Safety-Related Electrical Equipment - Additional Information.

Dear Sir:

In response to your letter, Reference (e), we are providing the following information to facilitate completion of the preliminary review by Franklin Research Center.

Request #1:

In reference to the Licensee's 90-day response to the tRC SER, a legible single copy of each of the following qualification documents is requested in order that the FRC evaluation may proceed.

Response #1:

In the cover letter to Reference (e), the NRC proposed that we remove this information from our EQ central filo and provide it to the NRC, to be returned to us upnn completion of review.

We appreciate the effort to reduce the amount of duplication associated with this request. However, after reviewing Maine Yankee Technical Specification 5.13.2 and the associated

[gp Commission's order, Reference (b), we are reluctant to risk the

/i

• loss of the single copies of these documents in our possession.

Therefore, we will duplicate and transmit this information as soon as possible (including partial transmittals) with completion

/[

by March 8,1982.

8202180222 820211 PDR ADOCK 05000309 P

PDR

i MAINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission February 11, 1982 Attention: Office of Nuclear Reactor Regulation Page 2 Request #2:

Environmental service condition temperature / pressure profile Figure III-4.2 is missing from Reference (d), Appendix 3.

FRC requests this information.

Pasponse #2:

The temperature / pressure profile, Figure III-4.2, has been deleted and is no longer referenced on any worksheets.

It was included in the intitial submittal of YAEC-1229 and was referenced on Page III.4-1.

This reference should be deleted.

Request #3:

Numerous SCEWs in Reference (d) do not contain specific information with respect to the specified operating time. FRC requests this information.

Response #3:

Each worksheet contains a table which provides the evaluated operating time under DBE and HELB conditions for that equipment.

Several of the ELEC worksheets do not have operating times listed, such as limit switches end terminal blocks, which have the same operating time as that. listed on the worksheets of the equipment with which they are associated.

Specific operating times have been listed for equipment operation up to 30 days. Beyond 30 days, the time to achieve cold shutdown and mitigate _ the consequences of an accident is very difficult to predict, depending on the scenario used, accessibility for repairs, etc. Therefore, the non-specific designation "Long Term" was used. A period of one year was used as a basis for calculating radiation doses to equipment in this category.

Request #4:

Reference (d) (Appendix I and E) provides details for replacement equipment; however, the currently installed equipment (manufacturer and model number) is not clearly identified. SCEW sheets for-installed equipment are requested where only the replacement component is identified.

M AINE YANKEE ATOMIC POWER COM,PANY United States Nuclear Regulatory Commission February _ 11, 1982 Attention: Office of Nuclear Reactor Regulation Page 3 Response #4:

Worksheets are attached for equipment which is being replaced -

with the exception of AFW-5 and HPSI-3.

It should be noted that SOVs-314, 324, and 334 on Worksheet HPSI-3 have been removed from service. A worksheet for the existing SOV-1106Y was not prepared because it was added to the worksheet list very' late in the preparation of the SER response, and it was decided that it should be replaced at that time.

Justification for this approach, based on almost immediate access for repair after HELB isolation, was provided on the first page of Attachment B of Reference (d) under discussion of EXN items.

Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY ff l

V

%8h N

John H. Garrity, Senio:.' Director Nuclear Engineering & Licensing JHG/at Attachment cc: Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103

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FACILITY:

MAINE YAhTIE DOCKET NO.* 50-309 APPENDIX II CS-3 ENVIRONMENTAL QUALIFICATION WORKSHEET i

. ENVIRONMENT DOCUMENTATION EIFERENCE 4

QUALIFICATION OUTSTANDING 4

PARAMETER SPECIFIED QUALIFIED SPECDIED QUALIFIED-METHOD ITEMS

- Ope ra t ing 30 Note 1 Note &

Time days JZZ'. 7-t Temperature Fig. tyv4-t 010 Note 4 Pressure Atmos.

Note 2 Note &

Relative Ambient Note 2

' Note &

Humidity Chemical N/A Spray -

t 7

Note 4 Radiation 2 x 10 R

' Note 5 oo9 Aging.

40 years Note 3 008 Note 4

~.

S ub:se rge nce N/A j

1 Component:

System:

Pressure Transmitter Contalment Spray i

Manufacturer:

Function JE :

-?'

!" 2 '3)

Fischer & Porter Containrient Spray Pump Discharge Pressure Transmitter Model or Type:

Service:

50EP1070 PT-352K, PT"353K s,

Associated Electrical Equipment:

i Accurar_f:

~

Specified: N/A ELEC-4 Instrument Cable Demonstrated: N/A r

Location:

Area: Containment Spray Pump Area j

Elevation: 12 '-6" Flood Level:

J Elevation: N/A Above Flood Level Yes k

a Page 11.4-5

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FACILITY: MAINE YANKEE CS-3' DOCKET NO. :

50-309 APPENDIX II NOTES:

A long-term operating requirement of 30 days has been established.

(1)

(2)- Since there are no HELB's postulated in these areas, relative humidity and pressure remain at ambient conditions.

has been assumed unless otherwise (3)' A 40 year qualified life requirement noted.

Because of preliminary results from recent HELB and Heat-Up studies, (4) many areas previously believed to be non-harsh have now been determined to be harsh. The impact on equipment qualification has yet to be fully analyzed and resolved; a'nd therefore..the conclusions reached herein are to be considered preliminary.

(5)

Dosage assumed same as HCV 322,332.(iyr Ja se)

DOCUMENTATION

REFERENCES:

008 Ac to n Re po r t No. 15564-8, Report of " Thermal Aging Analysis of'Fischer

& Porter Transmitters for Class 1E Service at Maine Yankee Nuclear U,

Power Generating Station".

02-0570-1065, " Environmental Qualification of Class 'lE 009 EDS Report Electrical Equipment", September 1980, Revision 0.

02-0570-1069, Revision 0, " Pressure and Temperature 010 EDS Report Conditions at Maine Yankee Due to High Energy Line Break (HELB) Outside Containment and Heat-Up Caused by Recirculation Fluids Duc - to Loss-of-Coolant Accident (LOCA) Inside Containment".

Pa ge 11.4-6

' FACILITY:

PAINE YANKEE DOCKET No.: 50-309 APPENDIX 11

.FW-1 ENVIRONNENTAL QUALIFICATION WORKSHEET

/'

ENVIR0hMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Ope ra ting Long Long Note 1 Note 4 Engineering Time Te m Tern Analysis Tempe ra ture Fig. 111.1-1 Fig. IV.3-4 001 024 Simultaneous Test Pressure Fig. 111.1-2 Fig. IV.3-9 Col 024 Simultaneous Test Relative 100%

100%

Note 2 024 Simultaneous Humidity Test Chemical N/A Spray 6

6 Radiation 3.5 x 10 R 3.5 x 10 R 007 025 Sequential

. Test A61ng 40 years 40 years Note 3 008 Engineering Analysis i

Submergence N/A

/

Compor.ent:

System:

Pressure Trnesit:ters, Feedwater Systes Level Transvitter.

Function 'f--

'.;;;;di; '" 2 0),

hanufacturer:

Steam Generator Level Information Fischer & Porter Service:

l.

Model or Type:

Lt-1213A, LT-1213B, LT-1213C, LT-1213D, 50EP1000 (Pressure),

LT-1223A.. LT-12238, LT-1223C, LT-1223D, 1302495 (Level)

LT-1233A, LT-12338, LT-1233C,

LT-1233C Accuracy:

Associated Electrical Equipment:

Specified: 5%

ELEC-4 Instrument Cable Demonstrated:

3.5%

-ELEC-5 Terminal Block ELEC-6 Penetration Assembly Location:

Area: Reactor Containment Elevation: 20'-0" Flood Level:

l Elevatton 1.7*

Above Flood Level: Yes e

i l

/

Pare !!.6-1 i

FACILITY: KAINE YANKEE Fw-1 DOCKET NO. :

50-309 APPENDIX II NOTES:

A long-term operating requirement of 30 days has been established.

(1)

-(Scc %c..d i n'. 2 ^. )-

100% relative humidity has been assumed due to saturated steam (2) conditions.

(3)

A 40-year qualified life requirement has been assumed.

Qualification of this component for the required operating time has (4) been determined to be adequate based on an evaluation of the qualification data used to-qualify it for all applicable environmental parameters indicated on this worksheet DOCUMENTATION

REFERENCES:

Letter, Combustion Engineering, Inc., to Maine Yankee Atomic Power f'

001 Company, HYC-4169, dated January 25, 1978.

(This letter-contains

. revised containment pressure and temperature tables for Maine Yankee.)

L.

Engineering Analysis _#MY-105, " Radiation Dose Calculation".

007 No. 15564-8, Report of " Thermal Aging Analysis of Fischer Acton Report 008

& Porter Transmitters for Reactor Containment Use at Maine Yankee".

1. 2204-51-B-006, " Maximum Credible Accident Test on 024 Test Report:

Electronic Transmitters".

s=

Qualification Tests of Dif ferential Transmitters Under Nuclear 025 Radiation.

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Page 11.6-2

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' FACILITY:

HPSI-22dLn4j~

f!

DOCKET NO.: 50-309 APPENDIX II',

ENVIRONMENTAL QUALIFICATION WRKSHEET

..w, 1

ENVIRONMENT DOCUMENTATION REFERENCE

- ' '}Z

- t QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD' ITEMS Operating 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 6 days Note 1 Note &

Engineering Note 4 Analysis Time Tempe rature Fig. 111.2-4 Fig. IV.3-1 010 019 Test and III.2-8 Pressure

~ Fig. 111.2-4 Fig. IV.3-1 010

-019 Test Relative 100%

100:

Note 2 019 Test Humidity (Max.)

Chemical N/A Spray Radiation Note 5 10 R 009 048 Sequential Note 6

}

8 Test Note 7 Aging 40 years 40 years Note 3 008 Engineering Analysis

)

Submergence N/A Component:

System:

High Pressure Safety Injection System Motor Operator Function (See Appendix IV.2-33):

j Manufacturer Limitorque (Reliance)

Valve Operation Service:

Model or Type:

HCV-300, HCV-301, HCV-302, HCV-303 SMB-O HCV-311, HCV-313 HCV-321, HCV-323 SMB-1 H CV-3 31, HCV-333 Accuracy:

Speciffed: N/A Associated Electrical Equipment:

Demonstrated: N/A ELEC-10 Control Cable ELEC-12 Power Cable Location:

Area: Primary Auxiliary Building Elevation 21' Flood Level Elevatior.: N/A

-~Above Flood Level: N/A

--+e----.-

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Page 11.8-3

s FACILITY: MAINE YANKEE HPSI-2 a.d 7 DOCKET No.:

50-309 APPENDIX II NOTES:

(1)

An ' operating requirement of one hour has been assumed for post llELB operation.

(2) 100% relative humidity is assumed as a conservatism.

(3)

A 40 year qualified life requirement has been assumed unless otherwise no ted.

(4)

Qualification of this component fo. the required operating time has been determined to be adequate based on an evaluation of the qualification data used to qualify it for all applicable environmental parameters indicated on this worksheet (5)

The specified radiation environment is as follows:

Component Radiation 6

IICV-300 4.37 x 10 Rads 6

IICV-301 3.77 x 10 Rads 6

HCV-302 4.35 x 10 Rads 6

9-IICV-303 3.73 x 10 Rads IICV-311 9.74 x 105 Rads 6

- IICV-321 4.26 x 10 Rads 6

IICV-331 3.70 x 10 Rads 6

IICV-313 8.96 x 10 Rads 6

itCV-323 4.19 x 10 Rads

/

6 Rads

!!CV-333 3.61 x 10 (6)

The qualified radiation data provided is for the actuator excluding the mo to r. We are presently working with Limitorque Corp. to obtain radiation tolerance data for these motors. This information will be available for review on completion.

(7)

Because of preliminary results from recent ilELB and lleat-Up studies, many areas previously believed to be non-harsh have now been determined i

to be harsh. The impact on eculpment qualification has yet to be fully analyzed and renolved; and therefore, the conclusions reached herein are to be considered preliminary.

DOCUMEffrATION

REFERENCES:

- - +

~~~

.Acton Report No. 15564-20, Report of " Thermal Aging Analysis of 008 Limitorque Valve Actuators for Class 1E Service at Maine Yankee Nuc1 car Power Cencrating Station".

Page II.8-4

-T 4

=

i ;.

s T

HPSI-2 anw(9 (Co n t ' d ) '

APPENDIX II 009 EDS Report 02-0570-1065, " Environmental Qualification of Class 1E Electrical Equipment", September 1980, Revision O.

010 EDS Re po r t 02-0570-1069, Revision 0, " Pressure and Temperature Conditions at Maine Yankee Due to High Energy Line Break (HELB) Outside Containment and Heat-Up Caused by Recirculation Fluids. Due to Loss-of-Coolant Accident (LOCA) Inside Containment".

019 Test Report #600198, " Test of Limitorque Valve Operator to Meet General Requirements of an Electric Valve Actuator in Nuclear Reactor Containment Environment".

• 020 Letter, Radiation International, Inc. to Franklin Institute Research Laboratory, dated May 23, 1972.

• 021 Letter with Enclosure, Limitorque Corporation to Yankee Atomic Electric Company, dated May 4, 1979.

048 Test Report #600376A, " Nuclear Power Sta. ion Qualification Type Test Report, Limitorque Valve Actuators for the BWR Service", dated May 13, 1976.

• 049 Letter, Limitorque to Acton Testing Corp. - dated October 3,1980.

• This Docu' mentation Reference contains supplemental information.

Page II.8-4A

FACILITY:

MAINE YANKEE HPSI-5 ArrENDrx tr DOCrET NO.* 50-309 ENVIRONMENTAL QUALIFICATION UORKSHEET DOCUMENTATION REFERENCE ENVIRONMENT QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Operating Long Long Note 1 Note 4 Engineering Note 6 Analysis Timr Tern Tern Tem pe ra tu r e Fig. III.2-5 212*F 010 044 Ve nd o r Note 6 Data and 111.2-6 6

010 045 AE Note 6 Pressure Fig. III.2-/

Atmos, Spec Relative 100Z 95%

Note 2 045 AE Note 6 Spec Humidity e

Chemical N/A Spray Radiation 3.6 x 10 R 3.5 x 10 R 009 045 AE Note 6 5

5 Spec Note 5 Note 3 Aging 40 years Note 6

/

t Submergence N/A System:

C_omponent:

High Pressure Safety injection System Flow Transmitter Function:

Manuf acturer:

HPSI Pump Discharge Flow Indication Fischer & Porter Service:

Model or Type:

FT-331 FT-321, FT-311 Flow Indication Associated Electrical Equipment:

Accuracy:

Specified: N/A ELEC-4 Instrument Cable Demonstrated:

Locatlon:

Area: Primary Auxiliary Building Elevation:

11'-0" Flood Level:

Elevation: N/A Above Flood Level: Yes Page 11.8-9

_._s n

a

FACILITY: MAINE YANKEE HPSI-5 DOCKET No.:

50-309 APPENDlX 11 NOTES:

This A l'ong-term operating requirement of 30 days has been assumed.to a cold shutdown (1) is the time required to bring the plant following the accident.

100% relative humidity is assumed as a conservatism.

(2)

A 40 year qualified life requirement has been as umed unless otherwise (3) noted.

HP31 to verify -oentuii,;ca m pump (4)

The components listed are usedOnce verified <30 days, pressure measurement discharge pressure.

Therefore, we feel the units will be available need not be available.

for the time required.

Aging qualification is under investigation and will be provided when (5) completed.

Because of preliminary results from recent HELB and Heat-Up studies,i d many areas previously believed to be non-harsh have now been determ ne (6)

The impact on equipment qualification has yet to be to be harsh-fully analyzed and resolved; and therefore, the conclusions reached i

herein are to be considered preliminary.

DOCUMENTATION

REFERENCES:

04-0570-1065, " Environmental Qualification of Class 1E 009 EDS Report Electrical Equipment", September 1980, Revision O.

Revision 0, " Pressure and Temperature 010 EDS Report 02-0570-1069, to High Energy Line Break (HELB) Outside Conditions at Main 2 Yankee Due Containment and Heat-Up Caused by Recirculation Fluids Due to Loss-of-Coolant Accident (LOCA) Inside Containment".

Fischer & Porter Specification for Model 10B2496.

044 4467-488-903 045 Combustion Engineering Specification o

Page II.8-10

YACILIT :

MAINE YANKEE DOCKET NO.: 30-309 APPENDIX II LPSI-4 ENVIRONMENTAL QUALIFICATION WORKSHEET ENVIRONMENT DOCUMENTATION PJJERENCE QUALIFICATION OUTSTAND 1NC PARA 1ETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS ope rating 30 days 6 days Note 1 019 Simultaneous Note 5 Time Test Tempe ra tur e ' Fig. III.1-1 Fig. IV.3-1 001 019 Simultaneous Test Pressure Fig. III.1-2 Fig. IV.3-1 001 019 Simultaneous Test Relative 100%

100 Note 2 019 Simult a neou s Humidity Test Chemical 1,720 ppm 1.5 wt/Z 002 019 Simultaneous Spray Boron Boron Test pH=9.5 pH-7.67 7

8 Radiation 2.0 x 10 R 10 R 007 048 Sequential Note 4 Test Aging 40 years 40 years Note 3 008 Engineering Analysis Submergence N/A Component:

System:

Moter Operator Low Pressure Safety Injection System Manufacturer:

Function (See Appendix IV.2.3):

Limitorque Corporation Low Pressure Safety Injection Isolation Valves Model or Type:

Service:

f SMB-1 HCV-327 HCV-328 l

(

Associated Electrical Equipment:

ELEC-6 Penetration Assembly Location:

ELEC-7 Terminal Blocks Area: Reactor Containment ELEC-8 Control Cable Elevation:

l'-5" and above ELEC-9 Power Cable Flood Level:

Elevation:

1.7' Above Flood Level: Yes (Note 6)

~

i 4

page 11.9-5

-'[

FACILITY: MAINE YANKEE LPSI-4

\\

DOCKET NO.:

50-309 APPENDIX II NOTES:

(1)

An operating time of 30 days is specified based on the requirements for this equipaent needed prior to long-term cooling.

(2) 100% relative humidity has been assumed to saturated steam conditions.

(3)

A 40-year qualified life requirement has been assumed.

(4)

The qualified radiation data provided is for the actuator excluding the motor. We are presently working with Limitorque Corp. to obtcin radiation tolerance data for these motors. This information will bel availabic for review on completion.

(5)

Qualification of this component for the required operating time has been determined to be adequate based on an evaluation of the qualification data used to qualify it for all applicable environmental parameters indicated on this worksheet (6)

Valve actuator is located above flood level. Valve body is below.

DOCUMENTATION

REFERENCES:

001 Letter, Combustion Engineering, Inc., to Maine Yankee Atomic Power Company, MYC-4169, dated January 25, 1978.

(This letter contains revised containment pressure and temperature tables for Maine Yankee.)

002 Maine Yankee Atomic Power Station Technical Specification 3.7 (pages 3.7-1 and 3.7-2) and FSAR Section 6.2.

005 Maine Yankee Atomic Power Station FSAR Question / Answer 6.11.

• 006 Maine Yankee Emergency Procedure 2-14, "Long-Term Core Cooling Realig nmen t".

007 Engineering Analysis #MY-125, " Radiation Dose Calculation".

008 Ac ton Repo r t No. 15564-20 Report of " Thermal Aging Analysis of Limitorque Valve Actuators for Class lE Service at Maine Yankee Nuclear Power Generating Station".

• 012 Letter with Enclosures, Reliance Electric Company to Stone and Webster, dated April 8, 1971.

019 Test Report #600198, " Test of Limitorque Valve Operator to Meet Ccnceal Requirements of an Electric Valve Actuator in Nuclear Reactor Containment Environment".

Page 11.9-6

}

1 s

LPSI (Co n t' d)

APPENDIX II

• 020 ' Letter, Radiation International, Inc. to Franklin Institute Research Labbrato ry, ' d a ted May 23, 1972.

'021 ' Letter with Enclosure, Limitorque Corporation to Yankee Atomic Electric Company, dated May 4, 1979.

. f 048 Test Report #600376A, " Nuclear Power Station Qualification Type Test Report, Limitorque Valve Actuators for B'JR Service", dated May 13, i

1976.

i

• 049 Letter, Limitorque to Acton Testing Corp., dated October' 3, 1978.

s

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- s I.

I.

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• This Documentation Reference contains suppicmental information.

Page II.9-6A

FACILITY:

MAINE YANKEE LPSI-5 APPENDIX II DOCKET NO.: 50-309

, ENVIRONMENTAL QUALIFICATION WORKSHEET DOCUMENTATION REFERENCE ENVIROINENT QUALIFICATION

.0UTSTANDING PA?./c2TER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Note 1 Engineering Note 4 Operating Long Analysis Note 6 Time Tern Temperature Fig. III.3-1 212*F 010 044 Vendor Note 4 Data Note 6 Note 4 010 045 Vendor Pressure Atmos.

Atmos.

Date Note 6 Relative Ambient Ambient Note 2 045 Vendor Note 4 Data Note 6 Humidity Chemical N/A

ipray 5

Note 4 Radiation 3.0 x 10 R 3.5 x 10 R 009 045 Note 6 (Note 5)

Note 7 Note 4 Note 3 Aging 40 years Note 6

~~

Submergence N/A System:

Component:

Low Pressure Safety Injection Syst.a-Flow Transmitter Function (See Appendix IV.2-38):

Manufacturer:

LPSI Pump Discharge Flow Indication Fischer & Porter Service:

Model or Type FT-312, FT-322, FT-332 1082496 Associated Elect rical Equipment:

s Accuracy:

Specified: 0.5% of Span ELEC-4 Instrument Cable s

Demonstrated N/A Location:

Area: Containment Spray Pump Area Elevation:

15'-6" Flood Levels Elevation: N/A Above F1'ood Level Yes Page 11.9-7

st.

3 FACILITY: MAINE YANKEE-LPSI-5 DOCKET NO. : 50-309 APPENDIX II NOTES:

(1)

A 16ng-term operating requirement of one year has been assumed.

(2) 100% relative humidity is assumed as a conservatism.

(3)

A 40 year qualified life requirement has been assumed unless otherwise noted.

(4)

Units were purchased to referenced specification and we feel that operation of these units can be assumed.

(5)

Doses for HCV-312, 322 and 332 motors used for these transmitters.

(6)

Because of preliminary results from recent HELS and Heat-Up studies,-

many areas previously believed to be non-harsh have now been determined to be harsh. The impact on equipment qualification has yet to be fully analyzed and resolved; and therefore, the conclusions reached j

herein are to be considered preli.minary.

(-

(7)'

Aging qualification is under investigation and will be provided when available.

DOCUMENTATION

REFERENCES:

009 EDS Report 02-0570-1065, " Environmental Qualification of Class lE Electrical Equipment", September 1980, Revision 0.

010 EDS Report 02-0570-1069, Revision 0, " Pressure and Temperature Conditions at Maine Yankee Due to High Energy Line Break (HELS) Outside Containment and Heat-Up caused by Recirculation Fluids Due to Lo s s-of-Coolant. Accident (LOCA) Inside Containment".

044 Fischer & Porter Specification for Model 1032496.

045 Combustion Engineering Specification 4467-488-903.

i h

Page II.9-8 IL

'FACIL1TY:

MAINE YANKEE

~ PAM-5 DOCKET No.: $0-309 APPENDIX 11 ENVIRONMENTAL QUALIFICAT10N WORKSHEET e

ENVIRONMENT DOCUMENTATIV.6 REFERENCE QUALIFICAT!0tl OUTSTANDING PARAMETER SPECIFIED.

QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Operating.

Long Long Note 1 Note &

Engineering Time Term Tetu Analysis Tempe ra ture Fig. III.1-1 Fig. IV.3-2 001 024 Simultaneous Test i

I Pressure Fig. 111.1-2 Fig. 'V.3-2 001 024 Simultaneous Test Relative 100%

100Z Note 2 024 Simultaneous Test Huaidity Chemical Note 5 h

Spray 6

6 Radiation 3.5 x 10 R 3.5 x 10 R 007 02$

Sequential Test Aging 40 years 40 years Note 3 008 Engineering Analysis Sutrw egence N/A Component:

System:

Pressure Transmitter Post-Accident Monitoring (TMI)

Manufacturer:

Function:

Fischer & Porter Prisary Component Saturation Monitor Model or Type:

-Se rvi c e:

50EP1041 rr -102 X.

PT-102Y.

Associated Elect rical Equipment:

Accuraev:

Specified:

.25% FS Accuracy E LEC-4 Instrumentation Cable Demonstrated: N/A ELEC-5 Terminal Block Etic-6 Penetration Assembly Location:

Area: Reactor Containment Elevation:

20'-0" Flood Level:

Elevation: N/A

=

Above Flood Level: N/A e

Page !!.10-5

.l.-

FACILITY: HAINE YANKEE PAH-5 DOCKET No. :

50-309

'*PPENDIX II NOTES:

(1)

A l'ong-term operation of one year has been assumed.

1007. relative humidity has been assumed due to saturated steam (2) conditions.

A 40 year qualified life requirement has been assumed.

(3) for the required operating time has Qualification of this component (4) been determined to be adequate based on an evaluation of the.

qualification data used to qualify it for all applicable environmental parameters indicated. on this worksheet Transmitters are located in instrumentation cabinets protected from (5) chemical spray.

DOCUMENTATION

REFERENCES:

('~

001 Le tter, Combustion Engineering, Inc. to Maine Yankee Atomic Power 25, 1978.

(This letter contains Company, NYC-4169, dated January pressure and-temperature ' tables for Maine Yankee.)

revised containment

-I t

Engineering Analysis #HY-105, " Radiation Dose Calculation".

I 007 l

008 Acton Repo r t No. 15564-8, Report of " Thermal Aging Analysis of Fischer Use at Kaine Yankee".

and Porter Transmitter for Reactor Containment Test on

1. 2204-51-B-006, " Maximum credible Accident 024 Test Report:

Electronic Transmitters".

Qualification Tests of Differential Transmitters Under Nuclear 025 Radiation.

(

Page II.IO-6

[

FACILITY:

MAINE YANKEE PAM-7 DOCKET NO.: 50-309' APPENDIX !!

ENVIRONMENTAL QUALIFICATION WORKSHEET-DOCUMENTATION REFERENCE ENVIRONMENT QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Cote 4 Operating

• Long N/A Note 1 Time Tern Tempetature 150*F 212*F 010 044 Vendor Note 4 Data

+

Pressure Atmos.

Atmos.

010 045 AE Note 4' I

Spec Relative 100:

95%

Note 2 045t AE -

Note 4 e

Spec Humidity Chemical N/A Spray Radiation 2.8 x 10 R N/A Note 5 Note 4 6

Note 4

-Aging 40 years N/A Note 3

(

Submergence N/A Component:

System:

Post-Accident Monitoring (TMI)

Pressure Transmitter Function (See Appendix IV.2-30):

Manufacturer:

Containment Pressure -

Fischer & Porter Se rvic e:

Model or Type:

50EP1070 PT-2013 Associated Electrical Equipment Accuracy:

Specified: 1%

ELEC-4 Instrument Cable Demonstrated: N/A ELEC-5 Terminal Block Location:

Area: Primary Auxiliary Building Elevation:

21'

• Flood Level:

Elevation: N/A Above Flood Level: N/A e

i

\\

P3Re !!.10-9

n FACILITY: MAINE YANKEE PAM-7

{

DOCKET No.: 50-309 APPENDIX II NOTES:

A long-term requirement of one year has been -assumed for post-LOCA (1) use.

100% relative humidity has been assumed due to saturatedisteam (2) conditions.

(3)

A 40-year qualified life requirement has been assumed.

Because of preliminary results from recent HELB and Heat-Up studies, (4) many areas previously believed to be non-harsh have now been determined to be The impact on equipment qualification has yet to be har.*

fully analyzed and resolved; and therefore, ~ the conclusions reached herein are to be considered preliminary.

this location is taken from charging pump cubicle (target (5)

Dose at 012), Reference 009.

DOCUMENTATION

REFERENCES:

009 EDS Report ~ 02-0570-1065, " Environmental Qualification of Class lE.

(

Electrical Equipment", September 1980, Revision O.

02-0570-1069, Revision 0, " Pressure and Temperature EDS Report 010 Conditions at Maine Yankee Due to High Energy Line Break (HELB) Outside Containment and Heat-Up Caused by Recirculation Fluids Due to Loss-of-Coolant Accident (LOCA) Inside Containment".

044 Fischer & Porter Specification for Model 50EP1000.

045 Combustion Engineering Specification 4467-488-903.

Page 11.10-10

FACILITY:

HAINE YANKEE DOCKET NO.

50-309 APPENDIX II RC-1 ENVIRONMENTAL QUALIFICATION WORKSHEET 1

ENVIRONMENT DOCUMENTATION REFERENCE

{

QUALIFICATION OUTSTANDINC PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS J

l Operating I hour 1 hout Note 1 Note 4 Engineering Time Analysis 1

l Temperature Fig. 111.1-1 Fig. iv.3-2 001 024 Simultan ous l

Tet

• l

+

Pressure Fig. 111.1-2 Fig. IV.3-3 001 024 Simultaneous Test Relative 1001 100%

Note 2 024 Simultaneous Humidity Test Checical N/A Spray Note 5 6

6 Radiation 3.5 x 10 R 3.5 x 10 R 007 025 Sequential Test Aging 40 years 40 years Note 3 008 Engineering Analysis i

Submergence N/A Component:

System:

Pressure Transmitters Reactor Coolant System Manufacturer:

Function (See Appendix IV.2-4):

Fischer 4 Porter Pressurizer Pressure Model or Type:

Service:

50EP1000 (Pressure)

PT-102A, PT-1025, PT-102C, PT-102D Accuracy:

Associated Electrical Equipment:

Specified: 5%

ELEC-4 Instrument Cable Demonstrated:

3.5%

ELEC-5 Terminal Block ELEC -6 Penetration Assembly l

Location:

(

Area: Reactor Containment i

Elevation: 20'-0" l

Flood Level:

Elevation:

1.7' Above Flood Level: Yes IJ Rt=

ll,j4.j

cm.

g

.a-FACILITY: MAINE YANKEE RC-1 g

DOCKET No. :

50-309 APPENDIX 11 NOTES:

An -operating time of one hour c is'specified based on Supplement #2 (1) to IEB 79-01B.

100% relative-humidity-has been assumed due to saturated steam (2) conditions.

A 40-year qualified life requirement has been assumed.

(3) for the required operating time has Qualification of this. component been determined to be adequate based on an evaluation of thefor all applicable (4).

qualification _ data used to qualify it parameters indicated on this worksheet Transmitters are located in instrumentation cabinets protected from (5) chemical spray.

DOCUMENTATION

REFERENCES:

to Maine Yankee Atomic Power 001 Letter, Combustion Engineering, Inc.,

25,' 1978.

(This letter contains Company, NYC-4169, dated 'Januarypressure and temperature tables for Ma l-revised containment Engineering Analysis ' #MY-105, "Radia tion Dose Calculation".

.007 Ac ton Repo r t No. 15564-8, Report of " Thermal Aging Analysis of Fischer and Porter Transmitters for Reactor Containment Use at Maine Yankee 008

1. 2204-51-B-006, "tiaximum Credible Accident Test on 024 Test Report:

Electronic Transmitters".

l Qualification Tests of Dif ferential Transmitters Under Nuclear 025 Radiation.

'l i

Page 11.14-2

s

. i,

~

FACILITY:

HAINE YANKEE ELEC-13 ENCLOS"2E 3 DOCKET NO.: 50-309 ENVIRONMENTAL QUALIFICATION WORK $REET 3

1

. REFERENCE DOCUMENTATION ENVIRONMENT QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED KETHOD ITEMS

~

l Note 4 Note 1-OperatingL 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Note 5 4.

Time i

e' Note 4~

001 Temperature Pig. 111.1-1 Note 5 i

Note 4 l

001 Pressure Fig. 111.1-2 Note.5 e

f' i

Note 4 4

Relative 100%

Note 2 i

Note 5-Humidity

~

t Note 5 002 Chemical 1,720 ppm Spray Boron

' Note 5 pH=9.5 4

t Note 4 5

6 Radiation 1.2 x 10 R 007 Note 5 Aging 40 years 7.7 years Note 3 008 Engineering Note 5 Analysis l-

,- =

Submergence N/A' l

i System:

Component:

Primary Vent and Drain System Limit Switch Primary Component Cooling System 4

Manufacturer:

Function:

Primary Sampling System Valve Position Indication NAMCO Containment Air Activity Sampling System Valve t osition Indication Model or Type:

Fire Protection System Valve Position Indicar 2n EA740-80,000 Low Pressure Saf ety injection System Valve !;sition Indication.

j I

Service:

i Spectiied: N/A Tv-3303, TV-3410,'

TV-3414, TV-3416 Accuracy:.

I Demonstrated: N/A TV-3505, TV-2001, Tv-2906, HCV-35tK TCV-201K Location:

}

Area: Reactor Containment Elevation:

2'-O' and above e

Flood Level:

Elevation:

1.7' Above Flood Level: Yes i

L i

4 -

Page !!.16-25

. ~.., -,..

o

^'%'

o b

FACILITY:. MAINE YANKEE ELEC-13 DOCKET NO. :

50-309 APPENDIX II NOTES:

An operating _ time of one hour is specified based on Supplement #2 (1) to IEB 79-01B.

1007. relative humidity has been assumed for conservatism.

(2).

A 40 year qualified life requirement has been assumed.

_(3)

Operation of equipment utilizing _ this component occurs before the (4) abnormal environment associated with an accident has had an opportunity In addition, we to fully develop and af fect component integrity.

are planning to replace these.

ipment is included because of'NUREG-0578.

(5)

This e DOCBIENTATION

REFERENCES:

Le tter, Combustion Engineering, Inc., to Maine Yankee - Atomic Power -

-001 25, 1978.

(This letter contains Company, MYC-4169, dated January revised containment pressure and temperature tables for Maine Yankee.)

Maine Yankee Atomic Power Station Technical Specification 3.7.(pages 002 3.7-1 and 3.7-2) and FSAR Section 6.2.

Engineering Analysis #MY-115, " Radiation Dose Calculation".

007 No. 15564-4, Report of " Thermal Aging Analysis of Namco 008 Acton Report Switches for Class 1E Service at Maine Yankee Nuclear Power Limit Generating Station".

Page 11.16-26