ML20038A988

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Responds to 810902 Request for Addl Info Re Environ Qualification of TMI-related Equipment.Detailed Info Encl
ML20038A988
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 11/16/1981
From: Rich Smith
VERMONT YANKEE NUCLEAR POWER CORP.
To: Rooney V
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.D.3, TASK-2.E.4.2, TASK-2.F.1, TASK-TM FVY-81-61, NUDOCS 8111240563
Download: ML20038A988 (61)
v • d • e


Text

.

VERMONT YAN KEE NUCLEAR POWER CORPORATION 3

SEVENTY SEVEN GROVE STREET 2.C.2.1 RuTt tso, VEMMONT 05701 FVY 81-161 REPLY TO:

ENGINEERING OFFICE 1671 WORCESTER ROAD FR AMING H A M. M ASS ACH USETTS 01701 TELEPHONE 817+872 8100 November 15, 1981 Y

United States Nuclear Regulatory Commission Washington, D. C. 20555 k g[([ /./ i Atten tion : Office of Nuclear Reactor Regulation y 4'op8g f'b J M 'r 11 Mr. V. L. Rooney, Project Manager ,

7887 i Operating Reactor Branch #2 y k?l4,k%g 8, '

Division of Licensing

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References:

(a) License No. DPR-28 (Docket No. 50-271) xkJ '

(b) Letter, USNRC to VYNPC, dated September 2,1981

Subject:

Environmental Qualification of THI-Related Equipment 3 ear Sir:

Reference (b) documented a telephone conversation in which Vermont Yankee was requested to supply additional info rma tion regarding the environmental qualification of TMI-rela ted equi pmen t . The reque s ted informa tion is con-tained in the attachments to this letter.

We trus t this informa tion is sa tisf actory; however, should you have fur-ther questions, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

./Y - A R. L. Smith Licensing Engineer

[db Ii 3 RLS: dad f

Attachmen ts

' DESIGNATED ORIGINED N Certified By ,

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8111240563 811116 '

PDR ADOCK 05000'g P

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ATTACHMENT A

Reference:

Franklin Research Center Telephone Memorandum, dated August 20, 1981.

1) The following listing identifies the NUREG-0737 items involving instrumentation required to be installed by January 1, 1981. Other instrumentation not required by January 1,1981 but presently installed is also listed. This informa tion responds to Items 1, 2 and 3 of the referenced telephone memorandum.

Item II.B.3 Post-Accident Sampling (Attachment A-1)

PAS-1,2 -

Cable as described in Attachment A-1.

- Penetr-tion es described in Attachment A-3 (Elec-5).

- Installed during November, 1980.

Item II.D.3 Valve Position Indication (Attachment A-2)

PAM-2,3 - Cable f rom sensor to transmitter supplied with equipment.

- Cable from transmitter to penetration is Firewall III (fully qualified).

- Test reports not yet received.

- Installed during February, 19P0.

NBVI-5,6,7 -

Cable used for this installation is Firewall III (fully qualified).

- These instruments are being tested or replaced as necessary. No test reports are available for the existing switches at this time.

- Installed during November,1979.

Item II.E.4.2 Containment Isolation This modification consists of changes to the existing Primary Containment Isolation System logic circuitry in the main control room. The material used meets the requirements for equipment This modification was completed in located in mild environments.

February, 1980.

Item II.F.1.3 Containment High Range Monitor (Attachment A-3)

PAM-4 - Cable supplied with equipment.

Penetration as described in Attachment A-3.

- Installed during November, 1980.

Item II.F.1.4 Containment Pressure ( Attachment A-4)

PAM-11 -

Cable used for this installation is Firewall III (fully qualified).

- Installed during November, 1980.

Item II.F.1.5 Torus Water Level (Attachment A-5)

PAM-9,16 - Cable used for this installation ie Firewall III (fully qualified).

- Installed during November, 1980.

Item II.F.1.6 Containment Hydrogen Monitor Existing equipment is used to meet this requirement. NRC approval was received in an NRC letter, dated November 3,1980.

2) Item 4 of the referenced memorandum requested copy of a Vermont Yankee letter, dated February 2,1981 if the content of that letter is relevant to the FRC review effort. The February 2,1981 letter contains no informa tion not already presented above or in Attachments A-1 through A-5, and is therefore not being resubmitted.
3) Item 5 of the referenced memorandum requested that Vermont Yankee supply copies of the applicable qualification documentation for the equipment listed in Item 1 of this attachment. The necessary documentation not already in FRC's possession is listed below and included as Attachment A-6.

a) " Qualification Report for Fressure Transmitters," Rosemount Model 1153, Series B, Rosemount Report #108025.

b) Letter, Rosemount to Vermont Yankee Nuclear Power Station, dated August 12, 1981, "Model 1153, Series B, Pressure Transmitter Qualified Life."

c) RMT Report No. 117415, Revision B, " Qualification Tests for Rosemount Pressure Transmitter Model 1152."

d) Acton Test Report 15566-12, Revision 1, 11/11/80, " Thermal Aging Analysis of Rosemount Transmitters for Vermont Yankee Nuclear Power S ta ti on . "

e) Telecon Note, C. Voskamp with Dan Whalen of Rosemount on 7/28/81.

f) General Electric, " Qualification Test for F01 Electrical Penetration Assembly," by R. M. Shuster, 4/30/71.

g) Letter, September 6,1978, f rom R. F. Thibault of General Electric Company to W. F. Conway, Vermont Yankee Nuclear Power Corporation,

Subject:

" Electrical Penetration Qualification Test Report."

h) Acton Report No. 15566-13, Report of "Thernal Aging Analysis for Vermont Yankee Nuclear Power Station."

i) " Qualification Type Test Data Report for Class lE Victoreen High Range Containment Radiation Area Monitor System," #950.301.

4) Item 6 of the referenced memorandum requested Vermont Yankee to provide the methodology used in developing the environmental service conditions for the equipment in question. This methodology is described in Attachment A-7.
5) Item 7 of the referenced memorandum requested Vert.ont Yankee to supply the normal enviror. mental se rvice conditions. These conditions are given below.

~

., W J " W Equipment Loca ti on Normal Temperature Normal Humidity _

PAS-1 primary containment 135-1500F 70-99%

._ l PAS-2 reactor building 1040F max. 70-99%

PAM-2,3 primary containment 135-1500F 70-99%

NBVI-5,6,7 reactor building 1040F max. 70-99%

PAM-4 primary containment 135-1500F 70-99%

PAM-11 reactor building 1040F max. 70-99%

PAM-9,16 reactor building 1040F max. 70-99%

J

ATTACHMENT A-1 D

5 FACILITT: VERMONT YAhME t'I'N ' DOCKET No.: 50-271 AFFENDIN 11 e FAS-1 gy*

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=~" ?s ENVIRONMENTAL QUALIFICATION WORKSKEET r

g ENVIRONMENT DOCUMENTATION RITERINCE QUALIFICATION OUTSTANDING FARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS 51oul. Test Ope ra ting Note 1 1 year 004 006 and --

Time Eng. Analysis Temperature Fig. 111.1-1. Fig.Ik-11 001 006 S trut t ane ou s --

Test Pressure Fig. 111.1-2 Fig. IV-11 001 006 Simul t a ne ou s --

Test Relative 2001 100% Note 2 006 $1mul t a ne ou s --

Humidity Test Ctemical N/A -- -- -- -- --

Spray Radiation 6.3 x 10 7R 1.5 x 10 0R 002 006 Sequential --

Test Seq. Test Aging 40 years 10 years Note 3 '006 and --

Eng. Analysis Submergence N/A - - - * -- --

Component: System:

Solenoid Oper. Valve Post-Accident Sampling System Manufacturers Function:

. ASCO Filot Valve

, Model or Typet Service:

206-832-3 FCV-2-39 Accuracy: Associated Electrical Equipment:

Specified: N/A ELEC-5 Fenetration Demonstrated: N/A ELEC-11 Control Cable E LEC-12 Control Cable Location: ELEC-14 Terminal Block Areat Frieary Contaimment ELEC-28 Terminal Block Elevation: 297'-0"

_F_lood Levels t Elevation: 239'-8" -

l Above Flood Level: Tes .

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FACILITY: VEPliONT YANKEE s, DOCKET NO. : 50-271 PAS-1 APPENDIX II

  • ]

ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES (1) The following table' provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment 1 Hour MSLB Steam Tunnel B RPCI Reac. Bldg. (Torus Area) B 3*

Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) B Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') B A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

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

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

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  1. I FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 ,

PAS-1 APPENDIX II ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES

. 001 Memo,. B.C. Slifer to S.F. Urbanowski, " Post-Accident Containment .

Pressure / Temperatures, Vermont Yankee", NED 80-341, dated April 18, 1980.

002 Calculation IVY-ADH-80-2, " Primary Containment Post-LOCA Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

006 NUS Qualification Document Review Package #QDR-5429-006-0401, which includes the following documents:

a) Test Report No. AQS21678/TR, " Qualification Tests of Solenoid Valves by Environmental Exposure to Elevated Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance,

. Accident Radiation and Loss-of-Coolant Accident (LOCA) Simulation",

dated March 1978.

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  • C # DOCNIT NO. 50-271 APPENDIX 11 e PAS-2

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ENVIRONMENTAL QUALIFICATION WORKSHIET ENVIRONMZWT DOCUMINTATION RIFERINCE QUALIFICAI2ON OUTSTANDINO FAKAMETER SPECIFIED QUALIFIED SPECIFIED QUALITIED MITHOD. ITEMS

, Simul. Test ope rating Note 1 Lons 004 006 and --

Time Tern Eng. Analysis Tes pe ra tur e 104*F (Max.) Fig. IV-11 005 00( Simultaneous --

Note 4 Test Fressure Atmos. Fig. IV-11 005 006 Simultaneous --

Note 4 Test Relative Ambient 1 00% Note 2 006 Simultaneous --

Humidity Test Chemical N/A --

Spr ay Radiation 3.2 x 10 5R 2 x 10 8R 003 006 Sequential --

Test Seq. Test Aging 40 years 20 years Note 006 and --

Erg. Analysis g

1. -- -- --

Sub2ergence N/A -- --

1 Ce=ponent,: System:

Solenoid Valve Fost-Accident Sarpling da+.uf ac t ur er s Functiont ASCO Containment Isolation Model or Type: Service:

KP-1 Series (Note 5) FCV-2-40 Accuracy: Associated Electrical Eqairment Specified: N/A ELEC-12 Control Cable Demo n s t r a t ed : N/A ELEC-2 3 Control Cable E'.iC-2 8 Terminal Block locatfon:

Area: Reactor Building - Vol. 23

, Elesation: 280' Flood Level -

Elevation: N/A ,

Above Flood Levelt N/A .,e

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3 FACILITY: VERMONT YANKEE

\ DOCKET No.: 50-271 ,.

PAS-2 l , APPENDIX II l

l ENVIRONMENTAL QUALIFICATION WC RKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basic Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME

~

LOCA Primary Containment Long Term MSLB Steam Tunnel B ,

HPCI Reae. Bldg. (Torus Area) B Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) B Steam Tunnel RCIC Room

. RWCU Reac. Bldg. (Elev. 280') B A: Required to function under non-ha rsh environmental conditions.

B: Not required to function for this DBE.

(2) Ambient relative humidity has been assumed for non-HELB (heat-up)

, , conditions.

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) The Post-LOCA heat-up temperature profile in Documentation Reference

  1. 005 has been revised as a result of refinements in the calculations and proposed plant modifications. The resultant Post-LOCA heat up temperature will not exceed 104 F in areas above elevation 252'.

There is no pressure change associated with Post-LOCA heat-up of the reactor building. ..

(5) The existing solenoid operated pilot valve is being replaced with an equivalent ASCO Type NP-1. Qualification information is provided for the replacement NP-1.

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FACILITY: VERMONT YANKEE I DOCKET No.: 50-271 PAS-2

, APPE l} II -

ENVIRONMENTAL QUALIFICATION WOR' SHEET: DOCUMENTATION REFERENCES 003 Calculation fVY-ADH-80-6, " Reactor Building Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Repor't #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont i

Yankee Nuclear Power Station".

006 NUS Qualification Document Review Package #QDR-5429-006-0401, which includes the following documents:

a) Test Report No. AQS21678/TR, " Qualification Tests of Solenoid Valves by Environmental Exposure to Elevated Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance, Accident Radiation and Loss-of-Coolant Accident (LOCA) Simulation",

dat'ed March 1978.

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FACILITY: VER.CNT YANKEE

, DOCKIT NO.: 50-271 AFFENDIX II ELEC-11 ENVIR0hMNTAL QUALIFICATION WORKSEEET ENVIROMENT DOCLHENTATION RITERINCE QUALIFICATION CUTSTANDINC FARAETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Opera ting Note 1 Long 004 006 E ngineering --

Time Tern Analysis Temperature ' Fig. III.1-1; Fig. IV-3 001 006 Simultaneous --

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Test -

Fressure Fig. III.1-2 Fig. IV.3 001 006 Simult ane ou s --

Test Relative i 1001 100: Note 2 006 Simul t a ne ou s --

. Humidity Test i

Chemical N/A -- -- -- -- --

Spray Radiation ! 6.3 x 10 7R 100R 002 006 Engineering --

Analysis Aging 40 years 40 years Note 3 006 Er.gineering --

Analysis Sutme rge nc e N/A -- -- -- -- --

Ccapenent: System:

Centrol Cable Residual Heat Removal System High Pressure Coola.t Injection System Manuf act urer: Reactor Core Isolation Cooling System Rc=e Cable (Cyprus) Auto =atic Derressurization System Reactor Vater Cleanup System Model or Type Main Steam System XLP/FVC/PVC Reactor Recirculation System Fost-Accident Sampling Syst em Accuracy: Function:

Specified: N/A Electrical Control

  • Demonstrated: N/A Se rvi c e:

Location: MOV-23-15, NOV-2-74 HOV-13-15, Mov-2-53A Area: Frizary Containment Mov-2-53B, HOV-2-54A, MOV-2-545, NOV-12-15

. Elevation: 240'-0* and above MOV-10-18, RV-2-71A, RV-2-71%, RV-2-71C RV-2-71D, FCV-2-39, A0v-2-80D J

- Flood Level: A0V-2-80A, ADV-2-808 A0V-2-80C Elevation: 239'-8* ,

Above Flood Level: Yes -

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4 FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ELEC-11 APPENDIX II ,

ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment 1 Hour MSLB Steam Tunnel A HPCI Reae. Bldg. (Torus Ar.ea) A 4 Steam Tunnel

  • HPCI Room RCIC Reae. Bldg. (Torus Area) A Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 260') A

. A: Required to function under r.on-harsh environmental conditions.

B: Not required to function for this DBE.

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

(3) A specified value of 40 years has been assumed for the qualified If fe of equipment.

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FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ELEC-11 APPENDIX II .

ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES 001 Memo, B.C. Slifer ,to S.F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee", NED 80-341, dated April 18,

  • 1980.

002 Calculation #VY-ADH-80-2, " Primary Containment Post-LOCA Radiation Doses".

004 Vermont Yankee Equipment Operating Time Fbtrix.

006 YAEC Qualification Document Review Package #QDR-5429-006-0839, which includes the fellowing documents:

a) Acton Eeport No.15566 , Report of " Thermal Aging Analysis for Class lE Service at Vermont Yankee Nuclear Power Generating Station".

b) Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company Transmitting Environmental Certification.

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e T ACILITY: %ILMONT LL'32E .

. DOCKET NO. 50-271 AFPICi1X !! JLEC-12 ENVIRONMENTAL QUALIFICATION WORKSREET, ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTtNDING PARAMETER SPECIFIED QUALIFIED SPECIFLED QUALIFIED METHOD INS Operating Note 1 Long 004 006 Engineering --

Time Tern Analysis Temperature Fig. 111.4-10 Fig. IV-3 005 006 Simultaneous --

Fig. 111.5-24, Note 4 Test  ;

Pressure Fig. 111.4-10 Fig. IV-3 005 006 Simultaneous --

Fig. 111.5-24 Note 4 Test pela:ive 2002 100% Note 2 006 Simultaneous --

Humidity (Max.) Test Chemical N/A -- -- -- -- --

Spray Radiation 2.1 x 10 7 R 1 x 10 8R 003 006 Engineering --

(Max.) Analysis Aging 40 years 40 years Note 3 006 Engineering --

Analysis Submergence N/A -- -- -- -- --

Co ponent Function:

Control Cable Electrical Control Manufacturer Services Ro=e Cable (Cyprus) Mov-10-13A, NOV-10-13B, MOV-10-13C, MOV-10-13D MOV-10-17 Nov-10-15A, NOV-10-155, MOV-10-15C Model or Type: MOV-10-15D, MOV-10-27A, MOV 2 78, P10-1A XLP/PVC/Pvc P10-15, P10-1C, r10-1D. F8-1A P8-18, P8-1C, P8-1D, RRU-5 Accuracy: RRU-6, RRU-7, RRU-8, V-SB6 Specified: N/A V-557 V16-19-7A, V16-19-23, F S0-109-7 5A2 Demonstrated: N/A FSO-109-75B2, TSO-109-75D2, VC-95, VC-12A VC-128 VC-13A, VC-138, V16-19-6A Location: V16-19-65, RV-2-71A, RV-2-715 RV-2-71C

  • Areat Reactor Building RV-2-71D, MOV-70-20, F-46-1A, P-4 6-18 Elevation: Various NCC-89A, MCC-898, LT-2-3-72A, LT-2-3-72B LITS-2-3-73A, LITS-2-3-735, MOV-10-34A, MOV-10-34B Flood Level: MOV-10-183, MOV-10-18V, NOV-2-74, MOV-2-53A

. Elevation: N/A MOV-2-538, NOV-2-54A, M0V-2-548, Rov-20-34A Above Flood Level N/A MOV-10-34 5 MOV-10-18, NOV-10-65A, MOV-10-658 NOV-12-15 MOV-13-16 MOV-13-15, MOV-23-15 System SB-1A, 55-18, SB-2A, - - SB-28 Various $5-3A, $3-3B, SB-4A, , . SB-48 55-5, REF-2A, REF-28. 16-19-11A 16-19-118 TS-2 3-101 A, TS-2 3-10'2 A, TS-23-103A TS-23-104A, TS-13-79A, TS-13-80A, TS-13-81A TS-13-82A, A0V-2-86A, ADV-2-865, A0V-2-E6C A0V-2-86D, A0V-2-80A, A0V-2-805, A0V-2-80C A0V-2-803, FCV-2-39, FCV-2-40 S

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s FACILITY: VERMONT YANKEE DOCKET No.: .30-271 ELEC-12 APPENDIX II ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/RELE LOCATION EQUIPMENT OPERATING TIME LOCA Pricary Containment Long Term MSLB Steam Tunnel 10 Seconds HPCI Reae. Bldg. (Torus Area) A Steam Tunnel HPCI Room

  • RCIC Reac. Bldg. (Torus Area) A Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') A A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) A specified value of 100% relative humidity has been assumed due to saturated steam conditions. Ambient relative humidity has been assumed for non-HELB (heat-up) conditions.

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) The HELB temperature and pressure profiles in Documentation Reference

  1. 005 have been revised as a result of refinements in the calculations, and proposed plant modifications. Any profiles no longer required due to elimination of harsh environments have been deleted from Documentation Reference #005.

. The Post-LOCA heat-up temperature profile in Documentation Reference

  1. 005 has been revised as a result of refinements in the ca'1cu19tions ~

and proposed plant modifications. The resultant Post-L0CA[ heat-up temperature will not exceed 104 Finareasaboveelevat[fon252'.

There is no pressure change associated with Post-LOCA N'dat up of the i reactor building.

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d FACILITY: VERMONT YANFEE DOCKET No.: 50-271 ELEC-12 APPENDIX II .t .

ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES 003 Calculation #VY-ADH-80-6, " Reactor Building Radiation Doses". ,

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside contaiheent, Vermont Yankee Nuclear Power Station".

006 YAEC Qualification Document Review Package fQDR-5429-006-0839, which includes the following documents:

a) Acton Report No.15566, Report of " Thermal Aging Analysis for Class 1E Service at Vermont Yankee Nuclear Power Generating Station".

b) Letter dated August 17, 197F, Cyprus Wire and Cable Company to Yankee Atomic Electric Company Transmitting Environmental Certification. ,

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s ATTACHMENT A-2 i

FACILITY: VERMONT YAhTEE

. DOCKET Wo.: 50-271 APPENDIX 11 PAM-2 ENVIROhv;NTAL QUALIFICATION WORTSMEET ENVIRONMENT DOCL*1ENTAT10N REFERENCE

- QUALIFICATION OUTSTASDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Ope rating Note 1 004 -

Time Tempera ture Fig. 11I.1-1 001 -

Pressure Fig. III.1-2 001 -

Relative 100% Note 2 --

Humidity Chemical N/A - - - -- --

Spray Radiation 1.0 x 10 8 R 002 -

Aging 40 years Note 3 -

Submergence N/A - -- -- - --

Cocponent: System:

Acoustic Transmitter Post-Accident Monitoring Manufacturer _Tunction Babcock & Wilcox (Note 4) SV Position Indication Hodel or Typer Service:

N/A Plant IDF not assigned yet I .

Accuracy: Associated Electrical Equipment Specified: Note Qualified cable supplied by Demonstrated: Note BW (Note 4)

Location:

Areas Primary Containment Elevation: Approximately 300'

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~ Flood Level: .

i Elevation: 239'-8*

Above Flood Level Yes i

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FACILITY: Vr.RMONT YANKEE DOCKET NO.: 50-271 PAM-2 APPENDIX 11 ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES i .)

(1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Frieary Containment Long Term MSLB Steam Tunnel A HPCI Reae. Bldg. (Torus Area) A Steam Tunnel HPCI Room RCIC Reac. Bldg. (Torus Area) A Steam Tunnel RCIC Room -

RWCU Reae. Bldg. (Elev. 280') A A: Required' tc function under non-harsh environmental conditions.

B: Not required to function for this DBE.

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

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) Testing of this equipment by the manufacturer is currently in progress.

  • Test results will be reviewed upon receipt of reports.

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FACILITY: VERMONT YANKEE '

p DOCKET NO.: 50-271  ; PAM-2 g APPENDIX II

. ENVIROINENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES 001 Memo, B.C. Slifer "ot S.F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee", NED 80-341, dated April 18, 1980.

002 Calculation #VY-ADH-80-2, " Primary Containment Post-LOCA Radiation doses".

004 Vermont Yankee Equipment Operating Time Matrix.

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e FACILITY: VERMONT YANKIE DOCEIT NO.: 50-271 APPENDIX II PAM-3 E IR0h4 NTAL QUALIFICATION WORKSHEET

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EWIR0hMENT DOClHENTATION REFERINCE QUALIFICATION OUTSTA'; DING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITT>ts Operating Note 1 004 -

Time -

Tempe ra ture Fig. 111.1-1 001 -

Pressure Fig. III.1-2 001 -

Relative 1001 Note 2 --

Humidity Chemical ,

N/A - -- - -- --

Spray Radiation 1.0 x 10 8 R 002 -

Aging 40 years Note 3 -

Submergence N/A - - - --

Component System:

Acoustic Accelerometer Post-Accident Monitoring Manufacturers Tunction:

Babcock & Wilcox (Note 4) SV Position Indication Model or Type Service:

N/A Plant IDI not assigned yet ,

Accuracy: Associst.ed Electrical Equp ment:

Specified: Note Qualified cable supplied by B&W (Note 4)

Demonstrated: Note Locations

. Area: Primary Containment Elevation: Approximately 300' -!:

Flood Levels Elevation: 239'-8" -

Above Flood Level Yes

FACILITY: VERMONT YANKEE e DOCKET NO.: 50-271 . PAM-3 t

J #

APPENDIX II ,

.. ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment Long Term MSLB Steam Tunnel A HPCI Reac. Bldg. (Torus Area) A Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) A Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') A A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

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

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) Testing of this equipment by the manufacturer is currently in progress.

Test results will be reviewed upon receipt of reports.

~

_q 4

O

4 FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 PAM-3

\ F .-

p APPENDIX II ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES

^

001 Memo, B.C. Slifer to S.F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee", NED 80-341, dated April 18, 1980.

002 Calculation #VY-ADH-80-2, " Primary Containment Post-LOCA Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

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./

4 TACILITY: VERMONI YAME DOCKET NO.: 50-271 ArrENDix 11 ,

Nav1-5 ENVIRONVENTAL Qt'ALIFICATION WORKSMEET ENVIR0hMENT DOCLMENTATION REFERENCE

, QUALIFICATION OUTSTANDING 7ARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS

' Operating Note 1 004 -

Time Tempe ra ture 104*F (Max.), 005 -

Note 4 Pressure Atmos. 005 --

Note 4 Relative Ambient Note 2 -

llumidity Chemical N/A - - - -- -

Spray Radiation 5 x 10'R 003 -

Aging 40 years Note 3 --

Subsergence N/A e- - - -- --

Cosoonent: Systems Sa'ety Relief Valve Pos. Mon. Nuclear Bo!!er Vessel Instrumentation System Manufacturers Function:

Ceneral Elect ric (Note 5) Safety Relief Valve Position Indication 3 Model or Type Service:

N/A CE Dsg. #112D1943C005 Accuracy:

Spe ci f ied : Note 4 Associated Electrical Equipment s .

Demonstrated: Note 4 Note 4 Location:

Areat Reactor Building - Vol. 34 .

Elevation: 252'

~~

Flood Level

  • Elevation: N/A ,.

Above Flood Level: N/A .

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O FACILITY: VERMONT YANKEE DOCKET No.: 50-271 NBVI-5 -

e

'}g APPENDIX II

.r

! ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES ,

s (1) The following table'provides the operating time of this item for e'ach Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME -

LOCA Primary Containment Long Term MSLB Steam Tunnel A HPCI Reae. Bldg. (Torus Area) A Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) A Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') A

~

A: Required to function under non-harsh environmental conditions.

3 B: Not required to function for this DBE.

(2) Ambient relative humidity has been assumed for non-HELB (heat-up) conditions.

(3) A specified value of 40 years has been assumed for the qn '.ified life of equipment.

(4) The HELB temperature and pressure profiles in Documentation Reference

  1. 005 have been revised as a result of refinements in the calculations
  • and proposed plant modifications. Any profiles no longer required due to climination of harsh environments have been deleted fiam Documentation Reference #005.

- The Post-LOCA heat-up remperature profile in Documentation Reference

  1. 005 has been revised as a result of refinements in the~ calculations and proposed plant modifications. The resultant Post-LOCA heat-up temperature will not exceed 1040F in areas above elevation 252'.

There is no pressure change associated with Post-LOCA heat-up of the reactor building.

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4 FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 NBVI-5 I NOTES (Cont'd) e T f (5)' Testing of this equipment is currently in progress. Test reports will be reviewed when available.

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.. FACILITY: YERMONT YANKEE ,

DOCKET No.: 50-271 NBVI-5 k, +

g APPENDIX II t~'

ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES t

4 003 Calculation #VY-ADHw80-6, " Reactor Building Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EIS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont Yankee Nuclear Power Station".

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. FACILITY: TIRMONT YANKIE DOCKET NO.: 50-271 APPENDIX 11 pBVI-6

, INVIRCST NTAL QUALIFICATION WOPXSREET ENVIRohM NT DOCLMENTAT10N REFERENCE ,

QUAL FICATION OUTSTANDING

,FARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS i

ti Operating Note 1 004 -

Time Tem pe r a ture 1040F 005 -

Note A Pressure Atmos. 005 -

Ncte 4 Relative Ambient Note 2 -

Hut:idi ty Chemical N/A - - - --

Spr.y Radiation 5 x 10'R 003 --

Aging 40 years Note 3 -

Submergence N/A ,- -- -

Component: System:

Pressure switch Nuclear Boiler Vessel Instrumentation System Manufacturer; kunction:

Static-0 41ng (Note 5) Safety Relief Valve Position Indication Model or Typet -Cervice:

6N-E 3-CI A-GC.tRTTX10 PS-2-71-1C, PS-2-71-1D, PS-2-71-2C, PS-2-71-2D PS-2-71-3C, PS-2-71-3D Accuracy:

Specified: Associated Electrical Equipment: ,

Demonstrated: Note 4 pcation:

Area: Reactor Building - Vol. 34 "levation: 252'

- Flood Level: ~,

Elevation: N/A  ;

i Above Flood Level: N/A -f

4 d

\

,.- FACILITY: VERMONT YANKEE t

'l DOCKET NO.: 50-271' .f' NBVI-6

  • ?

N: '

[ APPENDIX II ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment Long Term MSL3 Steam Tunnel A 4 i

HPCI Reac. Bldg. (Torus Area) A Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) A Steam Tunnel .

RCIC Room RWCU Reac. Bldg. (Elev. 280') A A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) Ambient relative humidity has been assumed for non-HELB (heat-up) conditions.

(3)) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) The HELB temperature and pressure profiles in Documentation Reference *

  1. 005 have been revised as a result of refinements in the calculations and proposed plant modifications. Any profiles no longer required due to elimination of harsh environments have been deleted from Documentation Referance #005.

The Post-LOCA heat-up temperature profile in Documentation Reference

  1. 005 has been revised as a result of refinements in the- calculations and proposed plant modifications. The resultant Post-LOCA heat-up temperature will not exceed 104 F in areas above elevation 252'.

There is no pressure change associated with Post-LOCA heat-up of the reactor building.

9 d

FACILITY: VERMONT YANKEE -

50-271 -;

.NBVI-6 S.,DOCKETNO.:

),

. - F.

4

.[j NOTES (Cont'd) , )

(5)' These switches are being replaced with " Pressure Controls" pressure j switches. The replacement switches are currently being tested.

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J FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ,; NBVI-6

(

t APPENDIX II i

2 ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES 003 Calculation IVY-ads-80-6, " Reactor Building Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont Yankee Nuclear Power Station".

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FACILITY: VERMONT TANKEE DOCKET NO. 50-271 APPEND 1% 11 NBVI-7 ENVIRONMENTAL QUALIFICA.'10N WORKSHEET' ENVIRONMENT DOCUMENTATION REFERENCE l QUAL 1r1 CAT 10N OUTSTANDING 3 ITEMS g fPARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD, 5 .

' Operating _ Note 1 004 -

Time

?

Temperature 104*F (Max.) Note 5 005 Note 5 Note 5 -

Note 4 Pressure Atmos. Note 5 005 Note 5 Note 5 --

Note 4 Relative Ambient Note 5 Note 2 Note 5 Note 5 --

Humidity CheJ1 cal N/A - -

Spray Radiation 2 x 10 5R 003 --

Aging 40 yeara Note 3 --

Submergence N/A -- -

Component: System:

' Pressure Switch Nuclear Boiler Vessel Instrumentation System Manufacturer: Function:

Static-O-Ring (Note 6) Safety Relief Valve Position Indication Madel or Type: Service:

6N-E3-CIA-CCMMRTTX10 PS-2-71-1A PS-2-71-18 Accuracy: PS-2-71-2A Specified: PS-2-71-28 Demonstrated: PS-2-71-3A .

PS-2-71-38 Location:

Area: Reactor Bo!1 ding - Vol. 37 Associat ed Electrical Equipment:

Elevation: 252' Note 4 -

Flood Level

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

N

FACILITY: VERMONT YANKEE DOCKET NO.: 50-271  ! NBVI-7 s  :

APPENDIX II 1 i3 ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES k

(1) The following table provides the operating time of this item for each Design Basis Event _ (DBE) and High Energy Line Break (HELB) evaluated:

).

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment Long Term MSLB Steam Tunnel A HPCI Reac. Bldg. (Torus Area) A Steam Tunnel HPCI Room l

RCIC Reac. Bldg. (Torus Area) A Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') A A: Required'to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

t (2) Ambient relative humidity has been assumed for non-HELB (heat-up) conditions.

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) The HELB temperature and pressure profiles in Documentation Reference ,

  1. 005 have been revised as a result of reff nements in the calculations and proposed plant modifications. Any profiles no longer required due to elimination of harsh environments have been deleted from Documentation Reference #005.

The Post-LOCA heat-up temperature profile in Documentation Reference

  1. 005 has been revised as a result of refinements in the- calculations and proposed plant modifications. The resultant Post-LOCA heat-up temperature will not exceed 104 F in areas above elevation 252'.

There is no pressure change associated with Post-LOCA heat-up of the reactor building.

6

M FACILITY: VERMONT YANKEE DOCKET No. : 50-271 NBVI-7

\

NOTES (Cont'd)

(5) The maximum postulated DBE level for this environmental parameter is within normal operating limits. Equipment has been specified and designed in accordance with industry standards to cperate continuously in this environmen'.t (6) Switches are being replaced with qualified switches which are currently being tested. Documentation references will be added when completed test results are received and reviewed.

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O s FACILITY: VERMONT YANKEE h DOCKET No.: 50-271 NBVI-7

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$ APPENDIX II '

h' ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES N

003 Calculation #VY-ADH-80-6, " Reactor Building Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions D_e to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont Yankee Nuclear Power Station".

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1

o ATTACHMENT A-3

/

, FACILITf VERMONT YANKEE

  • DOCKET No.: 50-271 APPENDIX II PAM-4

~

ENVIRONMENTAL QUALIFICATION WORKSEEET h i

. .> . . ~ .

  • ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTA!Q1NG ARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITLMS Simul. Test Operating Note 1 Long 004 006 and --

Time Tern Eng. Analysis Temperature Fig. 111.1-1 Tig. IV-25 001 006 Simultaneous -

Test Pressure Fig. 111.1-2 Fig . IV-2 5 001 006 Simultaneous -

Test Relative 100Z 100% Note 2 006 $1multaneous --

Humidity . Test Chemical N/A - - - -- --

Spray Radiation 1.0 x 10 0R 1.5 x 10 8R 002 006 Sequential --

Test Seq. Test Aging 40 years 40 years Note 3 006 and --

, Eng. Analysis Submergence N/A - -- -- - --

Component: System:

Radiation Detector Post-Accident Monitoring <

Manufacturer Tunction:

Victoreen High Range Radiation Monitor Model or Type Se rvi c e .

877 RD-16-19-1A, RD-16-19-1 B 4

! Accuracy: Associated Electrical Equipment:

Specified: Note Qualified cables supplied by B&W (Note 4)

Demonstrated
Note

~ locations i Areat Primary Containment - [-

Elevation: 257' /

. (

Flood Levels I f Elevation: 239'-8*

Above Flood Level Yes i-

d FACILITY: VERMONT YANKEE PAM-4 DOCKET NO.: 50-271 7 APPENDIX II .in

'g -

T*

Wi

- t .

~

T ENVIRONMENTAL QUALIFICATION WORKSHEET: NOTES

. y (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment MSLB Steam Tunnel HPCI Reac. Bldg. (Torus Area)

  • Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area)

Steam Tunnel RCIC Room .

RWCU Reae. Bldg. (Elev. 280')

A: Required'to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

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

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

(4) This equipment is required under NUREG-0578 (TMI). .

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d FACILITY: VERMONT YANKEE DOCKET No. : 50-271 $k' PAM-4

(.  ; - 2 1 6~ APPENDIX II *ih ENVIRONMEh'TAL QUALIFICAT ON WORKSHEET: DOCUMENTATION REFERENCES ~

>[

001 Memo, B.C. Slifer to S.F. Urbaaowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee", NED 80-341, dated April 18, 1980.

002 Calculation #VY-ADH-80-2, " Primary Containment Post-LOCA Radiation Doses".

004 Vermont Yankee Equipment Operating Time tbtrix.

006 NUS Qualification Document Review Package #QDR-5429-006-2450, which includes the following documents:

a) " Qualification Type Test Data Report for Class 1E \.tctoreen High Range Containment Radiation Area Monitor System", #950.301.

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o

, FACILIITs VERMONT YANKEE DOCKET do.: 50-271 APPENDIX II ELEC-5 e

ENVIRONMENTAL QUALIFICATION WORKSHEET ENVIRONMENT DOCUMENTATION REFERENCE ,

h e QUALIFIC ION OUTSTANDINO

N .7IARAMETER SPECIFIED QC" IFT ED SPECIFiED QUALIFIED METH0 ITEMS o.'

Simul. Te,st f0perating Note 1 100 days . 004 006 and -

Eng. Analysis

    • fTime Simul. Test Te=perature Fig. 111.1-1, Fig. IV-6 001 006 and --

- Eng. Analysis Simul. Test Pressure Fig. 111.1-2 Fig. IV-6 001 006 and -

Eng. Analysis Simul. Test Relative 100% 100% Note 2 006 and --

Humidity Eng. Analysis i

Chemical N/A - -- -

Spray Prototype Test Radiation 6.8 x 10 7R 108R 002 006 and --

Eng. Analysis Type Test Aging 40 years 40 years Note 3 006 Eng. Analysis --

Note 5 .

Sutnergence N/A ,-

1 Component: System:

Penetration Assembly All Systems Inside the Primary Containment Manufacturer: Function:

General Electric Electrical Penetration Model or Type: Service NSO2, Ns03, NSO4 RV-2-71A, RV-2-71B, RV-2-716, RC-2-71D MOV-2 3-15, MOV-2-74, RP .o-19-1 A, RD-16-19-18 Accuracy: A0V-2-80A, ADV-2-80B. A0V-2-80C, ADV-2-00D Specified: N/A FCV-2-39, MOV-l' 13, MOV-2-53A, MOV-2-53B Demonstrated: N/A mV-2-54A, mv-2-548, MOV-12-15, MOV-10-18 ,

TE-16-19-30, TE-1-149-1 TE-1-149-2 TE-1-149-3, location: TE-1 -149 -4 , TE-1-149-5, TE-1-149-6, TE-1-149-7 Area: Primary Containment TE-1-149-8 TE-1-149-9 TE-1-149-10 TE-1-149-11 Elevation: 252'-0" and above TE-1-149-12

,. Flood Level:

Elevation: 239'-8" Above Flood Level: Yes ..

i

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.o FACILITY: VERMONT YANKEE DDCKET No.: 50-271 ELEC-5 i

APPENDIX II e -

(- f':  :.

~

n ENVIRONMENTAL QUALIFICAT' ION WORKSHEET: NOTES i

)

Lp (1) The following table provides the operatir.g time of this item for each Design Basis Event.(DBE) and High Energy Line Break (HELB) evaluatec:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment MSLB Steam Tunnel HPCI Reae. Bldg. (Torus Area)

Steam Tunnel HPCI Room RCIC Reac. Bldg. (Torus Area)

Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') .

A: Required.fo function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) A specified value of 100% relative humidity has been assumed due to saturated steam conditions. Ambient relative humidity has.bcen assuced for non-HELB (heat-up) conditions.

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

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FACILITY: VERMONT YANKEE ik ELEC-5 DOCKET NO.: 50-271 xL 1 k* .

4, " '

  • APPENDIX II  ?

I R; -

ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES I .

001 Memo, B.C. Slifer t'o S.F. Urbanowski, " Post-Accident Containment Pressure /Temperatu'es, r Vermont Yankee", NED 80-341, dated April 18, 1980.

002 Calculation IVY-ADH-80-2, " Primary Containment Post-LOCA Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

006 NUS Qualification Document heview Package #QDR-5429-006-1025, which includes the following documents:

a) General Electric, Qualification Test for F01 Electrical Penetratioa Assembly, by R.M. Shuster, 4/30/71.

b) Letter, September 6,1978, from R.F. Thibault of General Electric Compdny to W.F. Conway, Vermont Yankee Nuclear Power Corp.,

Subject:

Electrical Penetration Qualification Test Report. ,

c) Acton Report No. 15566-13, Report of " Thermal Aging Analysis for Vermont Yankee Nuclear Power Station.

d) Electric Penetration Assembly, Prototype Testing Qualification Report, 3/16/70, Ceneral Electric Company, 175 Curtner Ave., San Jose, California 95125.

e

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9

ATTACHMENT A-4 I' Fac!LI TY: VEPX N' YANKEE DOCKET h0.: 50-271 ArrENDIX II PAM-Il e,y ,'- ENVIRON'Eh7AL QUALIFICATION WORKSHEET

, e, f~

ENVIRONMENT DOCUMENTATION REFERENCE '[

QUALIF1( T10N OUTSTANDING

, PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED MITB01 ITEMS e{

^

Ope ra ting Note 1 Long 004 005 Segrential --

,[ Time , Tern Test Temperature 104 F (Max.) Fig. IV-1 005 006 Simultaneoue --

Note 4 Test Pressure Atmos. Fig. IV-1 005 006 Simultaneous --

Note 4 Test Relative 100% 100% Note 2 006 S imul t ane ou s --

Humidity Ambient Test Chemical N/A - -- - -- --

Spray l Radiation 5 x 10'R 5 x 10 6R 003 006 Sequential --

Test Aging 40 years 40 years Note 3 006 Engineering --

Analysis Submergence N/A - - -- -- --

Comronent: System:

Pressure Transmitter Post-Accident Monitoring System Manufacturer Furetion:

, Rosemount Dryvell Pressure Model or Type: Se rvi c e :

_1152 PT-16-19-2 9 A , PT-16-19-2 98 Accuracy:

Associated Electrical Ecuirment:

i Specified: +0.5% ELEC-23 Control Cable DemonstratedT _+0.5%

Location:

Area: Reactor Building - Vol. 21 Elevation: 280'

_; Qood Level Elevation: N/A Above Flood Level: N/A -:

P-

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u?%

i' FACILITY: VERMONT YANKEE 50-271 , PAM-11 DOCKET NO. : 7 APPENDIX II $

j

~

ENVIRONMENTAL ' QUALIFICATION WORKSHEET: NOTES (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment Long Term MSLB ' Steam Tunnel B RPCI Reac. Bldg. (Torus Area) B Steam Tunnel HPCI Room RCIC Reac. Bldg. (Torus Area) B Steam Tunnel RCIC Room RWCU Reac. Bldg. (Elev. 280') B A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) Ambient relative humidity has been assumed for non-llELB (heat-up) conditions.

(3) A specified value of 40 years,has been assumed for the qualified life of equipment.

(4) The Post-LOCA heat-up temperature profile in Documentation Reference ,

  1. 005 has been revised as a result of refinements in the calculations and proposed plant modifications. The resultant Post-LOCA heat-up temperature will not exceed 104 F in areas above elevation 252'.

There is no pressure change associated with Post-LOCA heat-up of the

- reactor building.

h.

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? .

FACILITY: VERMONT YAhKEE PAM-11 DOCKET NO.: 50-271 ,

    • APPENDIX II r ENVIRONMENTAL QUALIFkCkTIbN WORKSHEET: DOCUMENTATION REFP. NCES u

it -

Calculation #VY-ADlJ-80-6, " Reactor Buildi'ng Radiation Doses".

003 .

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont Yankee Nuclear Power Station".

006 NUS Qualification Document Review Package #QDR-5429-006-0138, which includes the following documents:

o a) RMT Report No. 117415, Revision B, Qualification Tests for Rosemount Pressure Transmitter Model 1152.

b) Acton Rest Report 15566-12, Revision 1, 11/11/80, Thermal Aging

- Analysis of Rosemount Transmitters for Vermont Yankee Nuclear Power Station.

c) Telecon Note, C. Voskamp with Dan Whalen of Rosemount on 7/28/81.

1 i

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ATTACHMENT A-5 Ft.CILITY: VEMONT YAh72E DOCKET No.: 50-271 APPECIK 11 _PAM-9 g ENVIRONMENTAL QUALIFICATION VCRKS}iEET SC.

.m .

n-ENVIRONMENT DOCUMEh7AT10N REFERENCE QUALIFICATION OUTSTAh' DING SPECIFIED SPECIFIED QUALIFIED METHOD ITEMS PARAMETER QUALIFIED y byetating Note 1 Long 004 006 Engineering 4 -

,. , Time Ters Analysis Tearerature Fig. 111.4-9 Fig . IV-2 7 005 006 Simultaneous -

Test Fressure Atmos. Fig. IV-27 005 006 Simultaneous -

Test Relative Ambient 1001 Note 2 006 Simultaneous -

llumidity Test Chemical N/A - -

Spray ,

Radiation 2.1 x 10 R 7

2.21 x 10 7R 003 006 Sequential --

Test Aging 40 years 10 years Note 3 006 Engineering -

Analysis Subsergence N/A - -

Component: System:

Level Transmitter Post-Accident Monitoring Manufacturer: Fune*fon:

Rosecount (Note 4) Torus Water level Model or Type Servleet 1152 LT-16-19-10A Accuracy: Associated Electrical Equipment:

Spec 111ed: +

_0.5%

Demonstrated: 4

_0.5%

Location:

Area: Reactor Building - Vol. 48 Elevation: 213'

-t

  • Flood Level

_I Elevation: N/A

.l Above Flood level N/A

  • t

.I n,

3 . _. '

ggs .

FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 PAM-9 TN APPENDIX II i -

l *. is

,h ENVIRONMENTAL' QUALIFICATION WORKSHEET: NOTES (1) The tollowing table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/HELB DBE/HELB LOCATION EQUIPMENT OPERATING TIME LOCA Primary Containment Long Term MSLB Steam Tunnel B HPCI Reae. Bldg. (Torus Area) B Steam Tunnel HPCI Room RCIC Reac. Bldg. (Torus Area) B

. Steam Tunnel l RCIC Room ,

RWCU Reac. Bldg. (Elev. 280') B A: Required to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) A specified value of 100% relative humidity has been assumed due to saturated steam conditions. Ambient relative humidity has been assumed for non-HELB (heat-up) conditions.

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

t (4) The existing Rosemount 1152 level transmitters will be replaced with Rosecount 1153 Series B transmitters. The qualification information

-o provided is for the replacement transmitters.

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FACILITY: VERMONT YANKEE PAM-9 DOCKET NO. : 50-271

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APPENDIX II' $

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ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATION REFERENCES

,i 003 Calculation fVY .ADHl-80-6, " Reactor Building Radiation Doses".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont Yankee Nuclear Power Station".

006 NUS Qualification Document Review Package #QDR-5429-006-0138-2, which includes the following documents:

a) " Qualification Report for Pressure Transmitters", Rosemount Model 1153 Series B, Rosemount Report #108025.

b) Letter, Rosemount to Vermont Yankee Nuclear Power Station, dated

' August 12, 1981, "Model 1153 Series B Pressure Transmitter Qualified Life".

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FACILITY: VER.ONT YANKIE APPENDIX 11 PAM-16

-- DOCKET NO. 50-2 71 F,.."*

TN ENVIRONMENTAL QUALIFICATION WORFSHEET

~

EWIRONMENT DOCUMENTATION REFERENCE QUALYFIC/J10N OUTSTANDING SPECIFIED SPECIFIED QUALIFIED METBdl' ITDtS

N

- - ARAMETER QUALITIED r , ,

F Sinal . T1 st Note 1 Long 004 006 and -

  • Operating Eng. Analysis

., Time Teca Temperature Fig. 111.4-9 Fig. IV-26 005 006 Simultaneous --

Test t.

I Pressure Atmos. Fig . IV-26 005 006 St=ul;aneous -

Test Note 2 006 Simul t a n e ou s Relative Ambient 100%

Test 9

Hosidity Chemical N/A

  • Spray R6diation 2.1 x 10 R 2.2 x 10 R 003 006 Sequential --

Test 40 years 10 years Note 3 006 Engineering Aging Analysis Submergence N/A --

Component: System:

Level Transmitter Post-Accident Monitoring Manufacturer: u nc t i on:

F_u Rosemount Torus Water Level Model or Tyn : Service:

1153B (Note 5) LT-16-19 -10 B Accuracy: Associated Elect rical Equipment:

Specified: +

_0.5% .

Deconstrated: _40 . 5 %

Location:

., Area: Reactor Building - Vol. 42 Elevation: 213' l.

Flood 1.evel:

-] Elevation: N/A -'

Above Flood Level: N/A .

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FACILITY: VERMONT YANKEE 50-271 PAM-16 DOCKET NO.: r; L r

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APPENDIX II *

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ENVIRON >iENTAL QUALIFICATION WORKSHEET: NOTES, (1) The following table provides the operating time of this item for each Design Basis Event (DBE) and High Energy Line Break (HELB) evaluated:

DBE/RELB DBE/HELB LOCATION EQUIPMENT GPERATING TIME LOCA Primary Containment Long Term MSLB Steam Tunnel B HPCI Reac. Bldg. (Torus Area) B Steam Tunnel HPCI Room RCIC Reae. Bldg. (Torus Area) B Steam Tunnel RCIC Room RWCU Reae. Bldg. (Elev. 280') B A: Required'to function under non-harsh environmental conditions.

B: Not required to function for this DBE.

(2) Ambient relative humidity has been assumed for non-HELB (heat-up)

. conditions.

~

(3) A specified value of 40 years has been assumed for the qualified life of equipment.

l l (4) The HELB temperature and pressure profiles in Documentation Reference *

  1. 005 have been revised as a result of refinements in the calculations and proposed plant modifications. Any profiles no longer required due to elimination of harsh environments have been deleted from

, Documentation Reference #005.

(5) The existing Rosemount 1152 transmitter will be replaced with a Rosecount Model 1153, Series B, transmitter. Qualification information is included for the replacement transmitter. I.I er

I FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 PAM-16 1

i' APPENDIX II }s }

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I.j ENVIRONMENTAL QUALIFICATION WORKSHEET: DOCUMENTATIONREFh.RENCES 003 Calculation #VY-ADH-80-6, " Reactor Building Radiation Dosec".

004 Vermont Yankee Equipment Operating Time Matrix.

005 EDS Report #02-0570-1068, " Pressure and Temperature Conditions Due to High Energy Line Breaks Outside Containment and Heat-Up Caused by Recirculating Fluids Following a LOCA Inside Containment, Vermont ~

Yankee Nuclear Pcwer Station".

006 NUS Qualification Document Review Package #QDR-5429-006-0138-2, which includes the following documents:

a) " Qualification Report for Pressure Transmitters", Rosemount Model 1153 Series B, Rosemount Report #108025.

b) Letter, Rosemount to Vermont Yankee Nuclear Power Station, dated August 12, 1981, "Model 1153 Series B Pressure Transmitter Qualified Life".

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ATTACHMENT A-7 EDS'NUCI. EAR INC. - --

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REPORT APPROVAL COVER SiiEET (I .

Client: Yankee Atomic Electric Comnany Project: Vermont Yankee Nuclear Power Station ' Job Number: 0570-010-681 Report

Title:

Pressure and Temperature Conditions at Vermont Yankee Due to llELB's Outside Con- "

tainment and Heatup Caused by Recirculating Fluids Following a LOCA 16. side Containment Report Number: 02-0570-1068- Rev. Preliminary The work described in this Report was performed in accordance with the EDS Nuclear Quality Assurance Program. The signatures below verify the accuracy of this Report and its compliance with applicable quality assurance requirements.

Prepared By: ,1 Date:

Reviewed By:

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Date:

T'w$,i-ye.

. %.9 Date

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aroved By- ft '

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'k~p Concurrence By:  % Date: _

Regional Quality Assurance Manager REVISION RECCRD Rev. Approval Nc. Prepared Reviewed Approved Concurrence Date Revision 4

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Report No. 02-0570-1069 Fevision 0 Page 1 1.0 EXECUTIVE SU?4fARY The Nuclear Regulatory Ccamission (NRC) has recently man-dated in letters to utilities that the environmental qualification of electrical equipment required to function subsequent to certain postulated accidents be reviewed.

The postulated accidents include a'LOCA inside containment

' and a High Energy Line Break (HELB) inside or outside of containment.

The qualification conditions to be considered include the f'ollowing:

1. Post accident pressure and temperature conditions
2. Heatup due to the recirculation of hot fluids from the suppression pool following a LOCA inside con-tainment k ),

The Yankee Atomic Electric Company (YAEC) requested EDS to execute the analyses necessary to adequately define the post accident service condition profiles for all areas outside containment which contain high energy lines or lines which recirculate torus fluid. The EDS scope of work included the following tasks:

1. Develop pressure and temperature time histories for plant areas outside of containment bated upon post-ulated line breaks in the fellowing 3 nt : ?s:

- Main Steam System (MS)

- Reactor Water Cleanup System (CU)

- High Pressure Core Injection System (itPCI)

- Reactor Core Isolatioc. Cooli..g System (RCIC)

2. Calculate the temperature rise in jo' apartments out-side containment which contain piping that recircu-lates suppr'ession pool water following a LOCA.

4 6# The thermal-hydraulic analysis to develop the pressure and temperature service co.idition profiles was performed utili -

. ing RELAP4/ MODS.

E DS Nuclear

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RADIATION EXPOSURE OF SAFETY RELATED EQUIPMENT AT VERMONT YANKEE FRUM RECJHCULATING FLUIUS Prepared For:

9 ~ ,

Yankee Atomic Electric Company Vermont Yankee Nuclear Power Station Prepared By: ~~

EDS Nuclear Inc.

.~

s November, 1980 '

Report No. 02-0570-1057 Revision 1

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EDS Noctear . _ _

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' (es), : JT Report No. 02-0570-1057

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Page 1 of 13 l,i e ' '

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1.0' EXECUTIVE

SUMMARY

The Nuclear Regulatory Commission (NRC) has recently

/ mandated in letters to utilities that the environ-

  • I

[ mental qualification of Class IE electrical equip-ment required to function subsequent to certain postulated accidents be reviewed. These accidents j^ include a Loss of

' ' containment with a; Coolant Accident (LOCA) inside I

ssociated recirculation of LOCA fluids outside of containment. Qualification con-

. ., 7,, ditions to be considered include the post accident

, -; integrated radiation exposure one could expect this 4 J, ,

electrical equipment _ta experience during a NUREG-

[~ 0578 type accidental core release.

  • n

" At a Marcn 7, 1980 meeting, the Yankee Atomic Electric Company (YAEC) requested EDS to execute the

' cnalyses necessary to adequately determine the post y3 )  ; accident integrated radiation exposures to electrical L,1f

' equipment outside' containment whose designation was specified by YAEC. 'In addition, YAEC provided marked up system piping drawings indicating potentially contaminated lines outside of containment following 7 the postulated accident.

4-

~, The EDS scope of work, as detailed in Section 2.0, in-
l. cluded the determination of NUREG-0578 accident type

! source terms through the use'of the computer code ORIGEN, and the calculation of radiation exposures utilizing the computer code QAD-PSA. In some cases, hand calculations were made. In addition, a man-ufacturer survey was conducted in order to determine

}

the radiation tolerance values for some of the specified electrical equipment and to ascertain what qualifications 2,.

had been performed by the manufacturer. This report. pro-vides the radiation tolerance for some of the Class 1E equipment and the total one year integrated radiation

'l s .

s exposure subsequent to a LOCA for these equipment targets. ,

,,p. '.

~'

These results provide YAEC with an accurate assessment of P post accident radiation environment fron-recirculating fluids "o

and available qualifications for the specified electrical l ' /. and mechanical equipment. .

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1. Figures 1(a) and 2(a) provide the envelopes for drywell pressures and temperatures, respectively, assuming no credit for drywell sprays.
2. Figures 1(b) and 2(b) provide the envelopes for drywell pressures and temperatures, respectively, assuming drywell sprays are activated in accordance with existing plant procedures. The temperature envelope of Figure 2(b) should only be applied to equipment located below the effective elevation of the drywell spray system.
3. The envelopes cover the entire range of single pipe breaks, in terms of size and type (i.e., steam or liquid), that can occur f.nside the primary con tainmen t.
4. The envelopes assume the minimum design complements of ECCS and RHR sys tems are available. In other words, system degradations beyond the original design basis are not considered.
5. No credit is taken for the drywell fan-coolers (RRU's), since they are assumed to be shed f rom the emergency bus on a high drywell pressure signal.
6. The longest times at high temperatures occur for small steam breaks. The assumptions rade for this event are that the reactor is cooled down at near normal rates (i.e.,1000F/hr) and cold shutdown conditions are tochieved about four hours af ter the beginning of the event. The time at temperature could be reduced with a faster cooldown rate. This could occur natur 11y in the course of the event with automatic actuation of ADS. However, since HPCI has enough capacity to keep up with the inventory loss from small steam breaks, the HDS probably would not automtically. actuate, and 'operator action would be required tc achieve the f as ter coo 1down.
7. Operator actions to restore the RRUs, or actuation of containment sprays, would also help to reduce the time at high temperatures. However, temperature reductions from spray actuation will be achieved immediately only in 'ie sprsy-affected zone. Local temperatures in regions not directly reached by the drywell spray 1 will still be at superheated steam temperatures as determined by the source (reactor) and sink (containment) pressures. These higher temperatures will fall off more slowly through natural heat transfer processes between the spray-affected and unaffected zones. For that reason, the higher temperature (i.e., no D spray) limit curves should be applied to equipment which is located above the elevation that is reached by the drywell sprays.

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