ML19310A289

Environ Qualification of Safety-Related Electrical Equipment at VT Yankee Nuclear Power Station

ML19310A289
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	06/02/1980
From:	Baxter F, Tsouderos G, Urbanowski S YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19310A282	List: ML19310A281 ML19310A289
References
IEB-79-01B, IEB-79-1B, YAEC-1216, NUDOCS 8006110029
Download: ML19310A289 (184)

Text

{{#Wiki_filter:. r 1 4 O 3 1 0 I' u a t~ k EhTIRONMENTAL QUALIFICATION OF SAFEIY-RELATED ELECTRICAL EQUIPFZNT ~ i-l AT VERMONT YANKEE NUCLEAR POWER STATION I O 9 Yan<ee Atomic E ectric Company w exes w goobitoot?

e C 'du ENVIRON! ENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPPENT AT VERMONT YANKEE NUCLEAR PORIR STATION By S. F. Urbanowski, Senior Ingineer May, 1980 l PREPARED BY: M44 6 Ek 0 S. F. Urbanowski, Senior E:.gineer (Date) A REVIEWED BY h6 - -12e C - Z -%O C Tsouderos, Senior Electrical Engineer (Date) Av b APPROVED BY: Z. S0 F. D. Baxter, Manage r '(Late) Electrical Engineering Group Yankee Atomic Electric Company Nuclear Services Division 25 Research Drive Westborough, Massachusetts 01581

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i DISCLAIMER OF RESPONSIBILITY This document was prepared by Yankee Atomic Electric Company on behalf of Vermont Yankee Nuclear Power Corporation. This document is believed to be completely true and accurate to the best of o6r knowledge and information. It is authorized for use specifically by Yankee Atocic Electric Company, Vermont Yankee Nuclear Power Corporation and/or the appropriate subdivisions within the Nuclear Regulatory Commission only. With regard to any unauthorized use whatsoever, Yankee Atomic Electric Company, Vermont Yankee Nuclear Power Corporation and their of ficers, directors, agents and employees assume no liability nor make any warranty or representation with respect to the contents of this document or to its accuracy or completeness. 11

l ABSTRACT General Design Criterion 4 states in part that " structures, systems and components important to safety shall be designed to accommodate the i effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss of coolant accidents". This report provides the necessary documentation to ensure that certain safety-related electrical equipment at Vermont Yankee is environmentally qualified. G ( 9 O ) iii

ACKNOWLEDGEMEhTS In addition to all the departments and groups that assisted us in this effort, we would in particular like to thank John F. O'Connot and William G. Alcusky of the Instrumentation and Contrpi Engineering Group for this close liaison and significant contributions. iv

TABLE OF CONTENTS Page D{SCLAIMER OF RESPONS IB ILITY..................................... "- ii ABSTRACT......................................................... iii ACKN 0WLE DGEME hT S................................................. iv TAB LE OF CO NTE NT S................................................ v LIST OF FIGURES.................................................. vi

1.0 INTRODUCTION

I 2.0 ANALYSIS OF POSTULATED SCENARIOS........................... 3 2.1 LOCA/HELB Inside Containment......................... 3 2.2 HEL3 Ou t sid e Containmen t............................. 3 2.3 Recirculation of Radioactive Fluids from InSide Containment................................... 3 3.0 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDE NT CONDITIONS.............................. 4 4.0 ELECTRICAL COMP 0NENTS...................................... 5 ~ 5.0 S ERVIC E REQUIR EKE NTS....................................... 6 5.1 Operating Time....................................... 6 5.2 Te m pe r a t u r e.......................................... 6 5.3 Pressure............................................. 7 5.4 Relative Humidity.................................... 7 5.5 Chemical Spray....................................... 8 5.6 Ra d i a t i o n............................................ 6 5.7 Aging................................................ 8 5.8 Submergence.......................................... 9 6.0 ENVIRONME NTAL QUALIFIC ATIONS............................... 12 REFERENCES....................................................... 13 ENCLOSURE 1: EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS..................... ENCLOSURE 2: ELECTRICAL COMP 0NENTS.............................. ENCLOSURE 3: ENVIRONMEh'IAL QUALIFICATION WORKSHEETS............. V r

LIST OF FIGURES Number Ti tle Page

,5.1 Design Basis Accident Containment Temperature Profile Maine Yankee..........................................

10 5.2 Design Basis Accident t Containment Pressure Profile Maine Yankee.......................................... 11 I l ) e i f s' vi

1

1.0 INTRODUCTION

IE Bulletin 79-01 required licensees to perform a detailed review of Class 1E electrical equipment environmental qualifications to ensure that the equipment will function under postulated accident conditions. This review was conducted for Vermont Yankee with particular emphasis placed on electrical equipment located in the primary containment and steam tunnel. The results of this review were consolidated into Reference (a), YAEC Report

1. 1179, " Environmental Qualification of Electrical Equipment Within the Primary Containment and Steam Tunnel at Vermont Yankee Nuclear Power S t a tio n". A summary of this report, #1179A, was submitted to the Nuclear Regulatory Commission on June 15, 1979, in response to IE Bulletin 79-01.

Subsequently, the NRC issued IE Bulletin 79-01B as a result of their initial review of licensees' responses to IE Bulletin 79-01. In addition to requesting'more detailed information, the scope of IE Bulletin 79-01B includes the investigation of high energy line breaks (HELB) inside and outside primary containment, aging, submergence, and radiation exposure due to recirculating fluids for long-term core cooling. YAEC Report #1216 1 (this report) was issued to provide the additional information required by IE Bulletin 79-01B. YAEC Report #1216 may be considered to supersede Reports #1179 and

1. 1179A because its scope is broader and its contents include the information previously submitted.

YAEC Report #1216 presents the results of an exhaustive evaluation of environmental qualifications for certain safety-related electrical equipment at Vermont Yankee. 1

The scope has been limited to equipment affected by the following scenarios * (a) LOCA/High Energy Line Break (HELB) inside containme'nt, (b) HELB outside containment, (c) recirculation of radioactive fluids from inside containment for long-term post-accident core cooling. In order to evaluate the adequacy of safety-related electrical equipment environmental qualifications, the following information was determined: (a) plant equipment required to function under postulated accident conditions, (b) electrical components used for each piece of equipment identified

above, (c) environmental qualification requirements for each electrical component, (d) environmental qualification of each component based upon design data, test reports and/or engineering analyses.

2

2.0 ANALYSIS OF POSTULATED SCENARIOS Analysis of postulated scenarios is based on the following assumptions: 2.1 LOCA/HELB Inside Containment l The environmental effects due to tne LOCA/HELB inside primary containment affect only equipment located inside the primary containment. No hostile environments are experienced by electrical equipment located outside the primary containment. Radiation levels outside the primary containment are generally well below the threshold values for most materials. As a conservative assumption, no credit is taken for operation of the containment spray. The operation of containment spray is a manually initiated function approximately 1/2 hour af ter a LOCA/EELB. The effect of containment spray is to immediately reduce post-accident temperature j and pressure on the drywell, as indicated in Figure 1. A further discussion of environmental conditions in the primary containment is contained in Reference (b). 2.2 HELB Outside Containment The environmental effects of postulated high energy line breaks outside primary containment were addressed by Reference (c), " Supplemental Report on Ef fects of Postulated Break in a High Energy Piping System Outside the Containment". In all cases analyzed, the environmental conditions had no adverse ef fect on safe shutdown of the plant. 3

2.3 Recirculation of Radioactive Fluids from Inside Containment The primary environmental effect of this scenario is due to radiation exposure from recirculation of radioactive fluids from inside the primary containment. As directed by lE Bulletin 79-OlB, other service conditions st.ch as temperature and relative humidity are also included on the environmental qualification worksheets (Enclosure 3). The values used for temperature, pressure, and relative humidity in Section 5 of this report for areas outside the primary containment were taken from the Vermont Yankee FSAR. However, the basis for this information appears questionable and these valueo are being verified. The values have been entered on the environmental qualification worksheets and will be corrected if necessery. 4

3.0 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTUIATED ACCIDENT COhTITIONS A determination of equipment required to function under postulated accident conditions was made using the Vermont Yankeo FSAR ahd emergency procedures. Enclosure 1 is a tabulation of the required equipment, by system, and contains the following information': (a) equipment identification number, (b) description, (c) location (inside or outside prinary containment), (d) reference to associated electrical component environmental qualification worksheet (Enclosure 3). 9 ) \\ l 1 1 1 1 h 1 5 1 4 l

4.0 ELECTRICAL COMPONENTS For each piece of equipment required to remain operable, a list of associated electrical components such as motor operators, cables, terminal blocks, etc., was developed by reviewing installation drawings. Whenever possible, a physical verification was made to tonfirm that the information was accurate. is a tabulation of electrical component used in each system and contains the following information: (a) component (generic name), (b) canufacturer, (c) model # or type, (d) location (inside or outside primary containment), (e) reference to applicable environmental qualification worksheet (Enclosure 3). l 6 1 M r

5.0 SERVICE CONDITIONS l The following service conditions have been used to evaluate each electrical component. 5.1 Operating Time l Operating time is defined as the length of time a component must remain operable following a design basis accident. As a conservative measure, a long-term operating requirement of one year has been assumed except where a shorter period may be justified. 5.2 Temperature Normal operating and design basis accident temperatures are defined as follows for each area under investigation: Normal Accident Primary Containment 135-1500F (Avg.) Figure 1 Steam Tunnel 130 F (Avg.) 300 F (Max.) Reactor Building (General) 1000F (Max.) 150 F 0 Reactor Building (Specific 1480F (Max.) (under Compar tments) investigation) The primary containment temper sture profile shown in Figure 1 is the result of a recent in-house review [ Reference (b)] which envelopes the loss-of-coolant accident, main steam line break, and small break accident temperature ef fects., 7 -e t

5.3 Pressure Normal operating and design basis accident pressures are defined as follows for each area under investigation: No rmal Accident Primary Containment Atmospheric Figure 2 Steam Tunnel Atmospheric 4 psig (Max.) Reactor Building Slightly Negative 0.25 psig (Max.) The pressure profile shown in Figure 2 is the result of a recent in-house review [ Reference (b)] which envelopes the loss-of-coolant accident, main steam line break, and small break accident pressure effects. 5.4 Relative Humidity The plant ventilation and air-conditioning systems maintain the j relative humidity in a normal range. However, during and after a design 1 c basis accident, the required equipment and 'its associated electrical i components inside the primary containment and steam tunnel may be subjected to a steam environment. Consequently, the maximum expected relative humidity for this equipment is assumed to be 100%. The overall design limit for post-accident relative humidity in the reactor building is specified to be 90%. 8

l i^ 5.5 Chemical Spray Since Vermont Yankee does not use a chemical spray, this service requirement is not applicable. 5.6 Radiation a f The primary containment radiological doses for the required equipment have been re-evaluated for this report. The specified exposures consist of the dose received during normal operation in addition to the dose received during the course of an accident. Furthermore, due to the significant effect of equipment arrangement in the primary containment, the dose to each piece of required equipment was evaluated on a case-by-case basis. Radiological doses to the required equipment in the steam tunnel and reactor building are presently being evaluated by EDS Nuclear, Inc. 5.7 Aging Aging refers to che effects of operational, environmental, and system conditions on equipment during a period of time up to, but not including, design basis and post-accident basis events. Aging is included in the qualification requirements to determine if aging has any effect on operability. As a conservative measure, a 40 year qualified life requirement has been assumed in most cases. 5.8 Submergence Sufficient water is provided in the suppression pool to accommodate the initial energy which can transiently be released into the drywell from a postulated pipe failure. The suppression chamber is sized to contain 9 l l

this water, plus the water displaced from the reactor primary system together I with the free air initially contained in the drywell. Therefore, the primary ~ containment is designed and constructed to rule out any flooding in all { but the lowest elevation. The maximum postulated flood leve inside the primary containment is specified to be elevation 239'-8". Since none of the components in the primary containment are located below this elevation, submergence is not applicable. [ 10

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REFERENCES (a) YAEC Report #1179, " Environmental Qaalification of Electrical Equipment 'i Within the Primary Containment and Steam Tunnel at Vermont Yankee Nuclear Power Station". (YAEC-1179A is e summary of YAEC-1179.) (b) Memo, B. C. Slifer to S. F. Urbanowski, NED 80-341, dated April 18, 1980, " Post-Accident Containment Pressure / Temperature, Vermont Yankee". (c) " Supplemental Report on Ef fects of Postulate'd Break in a High Energy Piping System Outside the Containment", dated April, 1974. (d) " Report on Effects of a Postulated Break in a High Energy Piping System Outside the Containment", dated July, 1973.. (e) Vermont Yankee Nuclear Power Station, " Final Safety Analysis Report". l l 14-l i

I q ENCLOSURE 1 \\ contains the following inf,ormation according to systen affiliation: (a) equipment identification number, (b) description, (c) location (inside or outside primary containment), (d) references to associated electrical component environmental qualification worksheet (Enclosure 3). S e d t I f

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FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET No.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: High Pressure Coolant Injection System Equipment Location Enclosure (.') Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items MO-V-23-15 Supply Line Isolation valve X A,B,C,1,J,K MO-V-23-16 Supply Line Isolation Valve X N,0,Q 99 1-2

FACILITY: VERMONT YANKEE ENCOOSURE 1 DOCKET No.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Core Spray System Equipment Location Enclosure (3) ' Identification Inside Outside Worksheet Number Desc ri ption Pri. Cont. Pri. Cont. Items P46-1A Core Spray Pump X KK,JJ P46-1B Core Spray Pump X KK,JJ MO-V-14-11A Core Spray Discharge Valve X DD,LL,MM MO-V-14-11B Core Spray Discharge Valve X DD,LL,MM MO-V-14-12A Core Spray Discharge Valve X DD,LL,MM MO-V-14-12B Core Spray Discharge Valve X DD,LL,MM MO-V-14-26A Core Spray Test Valve X DD,LL MM MO-V-14-268 Core Spray Test Valve X DD,LL,MM S 1-3

i FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 ENCLOSURE 1 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEF.. Main Steam System Equipment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items A0-V-2-80A Inboard Isolation Valve X C,E,C,1,J M A0-V-2-80B Inboard Isolation Valve X C,E,C,1,J,M A0-V-2-80G Inboard Isolation Valve X C E.C,1,J,M A0-V-2-80D Inboard Isolation Valve X C,E,C,1,J,M A0-V-2-86 A Dutboard Isolation Valve X A0-V-2-86B Outboard Isolation Valve Q,S,R,T,U X A0-V-2-86C Outboard Isolation Valve Q,S,R,T,U X A0-V-2-86D outboard Isolation Valve Q,S,R,T,U X Q,S,R,T,U MO-V-2-74 Main Steam Drain Isolation Valve X A,B,C,1,J K 1-4

FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET NO.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Core Isolation Cooling System Equipment Location Enclosure (3) Identification Ins.de Outside Worksheet Number Description Pri. :ont. Pri. Cont. Items MO-V-13-15 , Steam Supply Line Isolation Valve X A, B, C,1, J, K MO-V-13-16 Steam Supply Line Isolation Valve X 0,P,Q

== 9 e 1-5

i FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 ENCLOSURE 1 i { as. EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS 1 l SYSTEM: llenting and Ventilation System Equipment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items RRU-5 Reactor Rectre Unit X DD,II,HM (RHR Service Water Pump Area) RRU-6 Reactor Recirc Unit X DD, Hil, MM (RHR Service Water Pump Area) RRU-7 Reactor Recirc Unit X (RHR & Core Spray Pump Area) DD,II,HM RRU-8 Reactor Recirc Unit X DD,II,HM (RHR & Core Spray Pump Area) d' 1-6

1 FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET No.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Recirculation System Equi pment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items MO-V-2-53A Recirculation Pump Discharge Valve X A,B,C,1,J,K MO-V-2-53B Recirculation Pump Discharge Valve X A,B,C,I,J,K MO-V 54 A Recirculation Pump Discharge Bypass Valve X A,B,C,I,J,K HO-V-2-54B Recirculation Pump Discharge Bypass Valve X A,B,C,1,J,K FCV-2-39 Recirculation Loop Sample Valve X C,1,J,L h 1-7

FACILITY: VERMONT YANKEE A 'URE 1 DOCKET No.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Containment Atmosphere Dilution System Equipment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items VG-23 Rad. Monitor Sample Isolation Valve X PP,(LATER) VG-26 Rad. Monitor Sample Isolation Valve X PP,(LATER) VG-24 Torus Sample Isolation Valve X PP,(LATER) VG-25 Torus Sample Isolation Valve X PP,(LATER) VC-33 Torus Sample Isolation Valve X PP,(LATER) VC-34 Torus Sample Isolation Valve X PP,(LATER) VG-9A Drywell Vent Inboard Isolation Valve X PP,(LATER) VG-9B Torus Vent Inboard Isolation Valve X PP,(LATER) VG-22A Drywell Vent Outboard Isolation Valve X (LATER) VG-22B Torus Vent Outboard Isolation Valve X (LATER) NC-11A Torus and Drywell Air Dilution X PP,(LATER) Isolation Valve NC-11B Torus and Drywell Air Dilution X PP,(LATER) Isolation Valve NC-12A Torus Air Dilution Isolation Valve X PP,(LATER) NC-12B Torus Air Dilution Isolation Valve X PP,(LATER) NC-13A Drywell Air Dilution Isolation Valve X PP,(LATER) NG-13B Drywell Air Dilution Isolation Valve X PP,(LATER) 1-8

FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET No.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Containment Atmosphere Dilution System (Continued) Equipment Location Enclosure (3) Identification Inside outside Worksheet Number. Description Pri. Cont. Pri. Cont. Items VG-75A3 Torus Sample Inboard Isolation Valve X PP,(LATER) VG-75A4 Torus Sample Outboard Isolation Valve X PP,(LATER) FS0-109-75A1 Containment Air Sampling Valve X 00,DD FS0-109-75A2 Containment Air Sampling valve X 00,DD FS0-109-75B1 Containment Air Sampling Valve X 00,DD FS0-109-75B2 Containment Air Sampling Valve X 00,DD FS0-109-75C1 Containment Air Sampling Valve X 00,DD FS0-109-75C2 Containment Air Sampling Valve X 00,DD FS0-109-75D1 Containment Air Sampling Valve X 00,DD FS0-109-75D2 Containment Air Sampling Valve X 00,DD FS0-109-76A Containment Air Sampling Valve X EE,DD FS0-109-76B Containment Air Sampling Valve X EE,DD 1-9

FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET NO.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Water Cleanup System Equipment Location Enclosure (3) Identification Insido Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items MO-V-12-15 Isolation Valve X A,B,C,1,J,K O O 8 1-10

) 3 1 ( te E ees R rh m U use S skt 1, O orI H, L l o C cW D N n E n. E t en d o iC s t. ui or n P o i t m a e c S t o N s L t O y n N I S eo O T dC I I g i X T D n s. C N i ni N O r I r U C o P F t T i O N n T E o D M D I E C t R C n 1 I A e 1 U d Q D i 1 E E c R T c A A T L N U t E T s M S o P O P I P n U o Q R i E E M t D E p e N T i r U S r u Y c t S s a e r D ep m e T l l e E w E y K r N D AY 1 T7 N2 O - M0 R5 n E o V i t t 0 na 3 o ecr YN mie 9 T pfb 1 I T iim L F. ut u 6 I K qnN 1 CC E e AO d E I T FD O

4 FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET NO.: 50-271 . ~.* EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Residual IIeat Removal System Equipment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Prf. Cont. Items MO-V-10-18 Shutdown Cooling Isolation Valve X A,B,C,1,J.K MO-V-10-32 Ilead Spray Isolation Valve X A,B,C,I,J,K MO-V-10-13A Torus to Pump Suction X DD,LL.MM Valve MO-V-10-13B Torus to Pump Suction X DD,LL,MM Valve MO-V-10-13C Torus to Pump Suction X DD.LL,MM Valve MO-V-10-13D Torus to Pump Suctio'n X DD.LL,MM Valve MO-V-10-17 Shutdown Cooling Isolation Valve X DD,LL,MM MO-V-10-15A Recirc Supply to Pump Suction Valve X DD LL,MM MO-V-10-15B Rectre Supply to Pump Suction Valve X DD,LL,MM MO-V-10-15C Rectre Supply to Pump Suction Valve X DD,LL,HM MO-V-10-15D Rectre Supply to Pump Suction Valve X DD,LL,HM MO-V-10-27A RIIR Outboard Injection Valve X DD LL,HM HO-V-10-27B RIIR Outboard Injection Valve X DD,LL,HM MO-V-10-25A RIIR Inboard Injection Valve X DD.LL.MM MO-V-10-25B RiiR Inboard Injection Valve X DD,LL.MM 1-12 1 l

FACILITY: VERMONT YANKEE ENCLOSURE 1 DOCKET NO.: 50-271 EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Residual lleat Removal System (Continued) Equipment Location Enclosure (3) Identification Inside Outside Worksheet Number Description Pri. Cont. Pri. Cont. Items MO-V-10-26A Cont. Spray Outboard Injection Valve X DD,LL,MM MO-V-10-26B cont. Spray Outboard Injection Valve X DD,LL MH MO-V-10-31A Cont. Spray Inboard Injection Valve X DD,LL.MM MO-V-10-31B Cont. Spray Inboard Injection Valve X DD,LL,HM h0-V-10-38A Suppression Chamber Spray Valve X DD,LL,HM MO-V-10-38B Suppression Chamber Spray Valve X DD,LL,MM P10-1A RIIR Pump X DD FF,MM P10-1B RilR Pump X DD,FF,MM P10-1C RilR Pump X DD,FF,HM P10-1D RilR Pump X DD,FF,MM P8-1A RHR Service Water Pump X DD,GG,HM P8-1B RilR Service Water Pump X DD,GG,MM P8-1C RilR Service Water Pump X DD,CC,HM P8-1D RilR Service Water Pump X DD,GG,MM 1-13

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ENCLOSURE 2 I ' contains the following information according to system affiliation: e f (a) component (generic name), (b) manufacturer, (c) model # or type, (d) location (inside or outside primary containment), (e) references to applicable environmental qualification worksheets (Enclosure 3). 1 l

l l g ) 3( te ees rh m use skt orI 1 J C F l o cW n E 2 E" 9 R-U- S t C en L d o C i C N s X E t. ui Or n P o i taco L tn eo dC i X X X X s. ni m I r e P tsy S no S i e T t p 4 N a y O E z T S N i N O r r P u o C M s 3 V F O s 0 P 6 C e S / 1 r ,l N C 1 L p e V 8 A e d P 3 2 C D o 2 / I M 0 P 6 R c S T L 0 T i N N X 2 C t E a L m E o t u A r c e i M r r E u t T t c S c e Y a l e S f E l u b n l a a a s C M r e e t e O n a m C e t o S G S R A E E KN AY y e 1 l v T7 b l N2 m a O - t e V M0 n s R5 e s k E n A c e r V o o l e p n l b p m o B a O

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'i ~ FACILITY: VERMONT YANKEE ENCLOSURE 2 DOCKET Nn.: 50-271 ELECTRICAL COMPONENTS SYSTEM: liigh Pressure Coolant Injection System Location Enclosure (3) Inside Outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items Penetration Assembly General Electric NS02, NS03, NSO4 X X 1 Terminal Block Buchanan 0222 X K T;rminal Block States NT X J Ccntrol Cable Rome Cable XLP/PVC/PVC X X C,Q P wer Cable Rome Cable XLP/PVC X B Motor Operator Limitorque SMR-1 X X A,0 P wer Cable Kerite HTK/FR ,X N s 2-2

) 3 ( te ees rh m T. Q U, R, S, us e sk t orI 1 J C M C E K B A l o cW n E 2 E R U S t O L en d o C i C N s X X X X X X E t. ui Or n P o i tac o L tn eo dC i X X X X X X X X X s. ni I rP me t S s e T y p 4 N S y O E T S D N m N O a r 0 P e o C R 0 M t 3 V S 7 O S 0 P 6 6 C S / l 3 8 3 n l N C l A C 0 L i e V a 3 0 V 0 2 A a 'd P w 2 4 P 0 C M o 2 / e 3 7 2 / I H O P r 8 2 P B R S T L i P A 2 L M T N N X F N E 0 X S C M E E L T E SYS r c i e i r r u t t c c e a l e s e e f E l o l u u b t n b q n l a s a a r, a a s C e n C o M r e b O a t e t e k O C h e i n a m c C M c m m e t o o S A u o i G S R R A N B R L E EKNAY y e 1 l v T7 b l N2 m a O - t e V M0 n s R5 e s k k d E n A c e e r c e V o o l l e h o t p n l b b p c l e a m o B a a O t B l r

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FACILITY: VERMOprr YANKEE DOCKET No.: 50-271 ENCLOSURE 2 ELECTRICAL COMPONENTS SYSTEM: Containment Atmosphere Dilution System Location Enclosure (3) Inside Outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items Solenoid Oper. Valve Target Rock 75E-002 X PP Control Cable Rome Cable XLP/PVC/PVC X D3 Solenoid Oper. Valve Atkomatic 15840-VPI-MOD K 00 Solenoid Oper. Valve Atkomatic 31840-VPI-MOD X EE 0 2-6

FAgILITY: VERMONT YANKEE ENCLOSURE 2 -DOCKET No.: 50-271 ELECTRICAL COMPONENTS SYSTEM: Reactor Water Cleanup System Location Enclosure (3) Inside Outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items P;netration Asseably General Electric NS02, NS03, NSO4 X X 1 Tarminal Block Buchanan 0222 X K TIrminal Block States NT X J Control Cable Rome Cable XLP/PVC/PVC X X C.DD P2wer Cable Rome Cable XLP/PVC X X B,MM Motor Operator Limitorque SMB-000, SMR-00 X X A.LL 'e ) I 2-7

FACILITY: VERMONT YANKEE ENCLOSURE 2 DOCKET NO.: 50-271 ELECTRICAL COMPONENTS SYSTEM: Post Accident Monitoring System Location Enclosure (3) Inside Outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items P:netration Assembly General Electric N302, NS03, NSO4 X 1 Thermocouple Extension Lewis Engineering SR/SR X D Cable Thsrmocouple Assembly PYC0 02-3171-08 X H 9 2-8

FACILITY: VERh0NT YANFEE ENCLOSURE 2 DOCKET No.: 50-271 ELECTRICAL COMPONENTS SYSTEM: Residual lleat Removal System Location Enclosure (3) Inside Outside Worksheet Componen t Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items P;netration Assembly General Electric NS02, NS03, NSO4 X X I Tzrainal Block Buchanan 0222 X K T;rminal Block States NT X J C:ntrol Cable Rome Cable XLP/PVC/PVC X X C DD Prwer Cable Rome Cable XLP/PVC X X B,MM Motor Operator Limitorque SMB-2, SMB-000, SMB-1 X A,LL a SMB-4, SMB-4T, SMB-3 SMB-0, SMB-00 Motor General Electric BEJ 2120J3 X FF BEJ 219002 BEJ 219003 BEJ 205002 Motor Westinghouse So f69F46553 X CC 2-9 l

FACILITY: VERMONT YANKEE ENCLOSURE 2 DOCKET NO.: 50-271 ELECTRICAL COMPONENTS SYSTEM: Core Spray System Location Enclosure (3) Inside Outside Workeheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items Motor General Electric FEJ 604010 X JJ FEJ 604011 Power Cable Collyer Buty1/ Neoprene X KK Motor Operator Lim 1 torque SMB-1, SMB-2 X LL Power Cable Rome XLP/PVC X MM Control Cable Rome XLP/PVC/PVC X DD S i 2-10 4

FACILITY: VERM0fft YANKEE ENCLOSURE 2 DOCKET NO.: 50-271 ELECTRICAL COMPONENTS SYSTEM: lleating and Ventilation System Location Enclosure (3) Inside Outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items Motor Allis-Chalmers 1-5101-39529-2-2 X II 1-5101-39529-3-1 1-5101-39529-3-2 Motor Allis-Chalmers Dwg #51-308-578 X HH P4wer Cable Rome Cable XLP/PVC X MM Control Cable Rome Cable XLP/PVC/PVC X DD 9 2-11 g

FACILITY: VERMONT YANKEE ENCLOSURE 2 DOCKET No.: 50-271 - n. ELECTRICAL COMPONENTS SYSTEM: Primary Containment and Atmospheric Control System Location Enclosure (3) Inside outside Worksheet Component Manufacturer Model # or Type Pri. Cont. Pri. Cont. Items Solenoid Operated Valve ASCO 8316B15 K AA Solenoid Operated Valve ASCO 8302C29RF X RR Solenoid Operated Valve ASCO 8321A6 X CC Control Cable Rome XLP/PVC/PVC X DD Solenoid Operated Valve ASCO 8317A29 X NN 1 2-12

1 ENCLOSURE 3 l f contains the following information for sich component referenced in Enclosures 1 and 2: t i (a) a qualification worksheet, i (b) a set of notes and documentation references for the applicable qualification worksheet, (c) a service condition test profile (if available). ) 'I i I

FACILITY: VERM0h7 YANKEE DOCKET No. : 50-271 ENCLOSLTE 3 TABLE OF CONTENTS - ENCLOSURE 3 ITEM COMPONENT MANlTFACTURER LOCATION A Motor Operator Limitorque Pri. Cont. B Power Cable Rome Pri. Cont. C Control Cable Rome Pri. Cont. D Thermocouple Cable Lewis Eng. Pri. Snt. E Limit Switch NAMCO Pri. Cont. F Solenoid Oper. Valve ASCO Pri. Cont. G Solenoid Oper. Valve ASCO Pri. Cont. H Thermocouple Assembly PYC0 Pri. Cont. I Penetration Assembly CE Pri. Cont. J Terminal Block States Pri. Cont. K Terminal Block Buchanan Pri. Cont. L Solenoid Oper. Valve ASCO Pri. Cont. M Control Cable Rockbestos Pri. Cont. N Power Cable Kerite Steam Tunnel 0 Motor Operator Limitorque Steam Tunnel P Power Cable Rome Steam Tunnel Q Control Cable Rome Steam Tunnel R Solenoid Oper. Valve ASCO Steam Tunnel S Limit Switch NAMCO Steam Tunnel T Terminal Block States Steam Tunnel U Control Cable Rockbestos Steam Tunnel AA Solenoid Oper. Valve ASCO tteactor Building BB Solenoid Oper. Valve ASCO Reactor Building CC Solenoid Oper. Valve ASCO Reactor Building DD Control Cable Rome Reactor Building EE Solenoid Oper. Valve Atkomatic Reactor Building FF Motor GE Reactor Building GG Motor Westinghouse Reactor Building HH Motor Allis-Chalmers Reactor Building 11 Motor Allis-Chalmers Reactor Building JJ Motor GE Reactor building KK Power Cable Collyer Reactor building LL Motor Operator Limito rque Reactor Building MM Power Cable Rome Reactor Building NN Solenoid Oper. Valve ASCO Reactor Building 00 Solenoid Oper. Valve Atkomatic Reactor Building PP Solenoid Oper. Valve Target Rock Reactor Building

~~ i ITEM A E ) I 1 i

0 FACILITY: TERMONT TAMKEE ECKET NO.: 50-271 ENCMSURE 3 ENVIRONMENTAL QUALIFICATION WORJt3 HEFT - ITEM A ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS I Opeisting Long Fate 1 Engineering Note 6 Time Te rs Analysis Temperature Fig. 5.1 Fig. A-1 901 013 ' Simultaneous Test Pressure Fig. 5.2 Fig. A-1 901 013 ' Simultaneous Test ' Relative 100% 100% Note 2 013 Simultaneous Humidity Test Chemical N/A Spray 7 8 Radiation 6.0 x 10 R 2.04 x 10 R 011 013 Sequential Test Aging 40 Tears Note 3 Engineering Note 5 Analysis Submergence N/A Component: System: Motor Operator Residual Heat Removal System Bigh Pressure Coolant Injection System Manufacturer Reactor Core Isolation Cooling Systea Limitorque Reactor Water Cleanup Systes Main Steam Systen Model or Type Reactor Recirculation Systen SMB-000, SMB-00 SMB-1, SMB-2 Service: MOV-23-15 Mov-2-74, Mov-13-15 Mov-2-53A Funetton: M0v-2-535, Mov-2-54A, MOV-2-545, Mov-12-15 Valee Operation MOV-10-18 MOV-10-32 Aceuracy: Specified: N/A Desonstrated: N/A Location: Area: Primary Containment Elevation: 240'-0 and above Flood Level Elevation: 239'-6* Above Flood Level Tes ( (A-1) l

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM A NOTES: i (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Docum,entation Reference (s): (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. DOCUMENTATION

REFERENCES:

011 Engineering Analysis #VY-101, " Radiological Dose Calculation". 013 Nuclear Power Station Qualification Type Test Report, Limitorque Valve ~ Actuators for BWR Service, Limitorque Project No. 600376A, reissued May 13, 1976. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. ~ i (A-2) J l L I .-~

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FACILITTs VERMONT TANKEE DOCKET No.: 50-271 INCIASURE 3 INVIRONMENTAL QUALIFICATION IdORKS1tEET - ITEM 8 ENVIRONMENT DOCL9fENTAT10N REFERENCE QUALIFICATION OUTSTANDING FAAAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED KETHOD 7 ITEMS Operating Long Note 1 Engineering Note 6 Time Te rn Analysis Tempe ra ture Fig. 5.1 Fig. B-1 901 023 Simultaneous Test Pressure Fig. 5.2 Fig. B-1 901 023 $1sultaneous Test Re? -1.; 100% 1 00% Note 2 023 Simultaneous E.dity Test Chemical N/A Spray 7 8 Radiation 6.3 x 10 R 10 R 021 024 Engineering Analysis Aging 40 years Note 3 Engineering Note 5 Analysis Submergence N/A Component: System: Power Cable Residual Best Reecial Systes High Pressure Coolant Injection Systes Reactor Core Isolation Cooling Systra Manufacturer Reactor Water Cleanup Systen Rose Cable Main Stesa Systes Reactor Recirculation Systen Model or Type KLP/FVC Se rvice: MOV-23-15, MOV-2-74, NOV-13-15, MOV-2-53A Function: MOV-2-535, MOV-2-54A, MOV-2-548, MOV-12-15 Electrical Power MOV-10-18, MOV-10-32 Accuracy: Specified: N/A Demonstrated: N/A Location: Areas Primary Containment Elevation: 240'-0* and above Flood Levels Elevation: 239'-8* Above Flood Level: Yes (3-1) l

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM B NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam 4 conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Paference(s): 025, 026. (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined ~ for all environmental parameters. DOCUMENTATION

REFERENCES:

021 Engineering Analysis #VY-102, " Radiological Dose Calculation". 023 Correspondence between Rome Cable and Vermont Yankee Nuclear Power Station documenting environmental testice. 024 Engineering Analysis #VY-302, "Qualiff e : ;en for Radiation Environment." 025 Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company transmitting Environmental Certification. 026 Ebasco Specification, VYNP-IV-C-2B, "600V Auxiliary Power Cable" - Revision 5. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. 1 (B-2)

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FACILITY: VERHOWT TANEZE 3OCKET so.: 50-271 ENesm 3 ENVIR0rMENTAL QUALIFICATION WORK $REET - ITTM C ENVIRONMENT DOCUMENTATION REFERZNCE QUALIFICATION, OUTSTANDINO ITEMS PARAMETER SFECIFIED QUALIFIED SFECIFIED QUALIFIED METHOD operating Long Note 1 Engineering Note 6 Time Terz Analysis Tempera ture Fig. 5.1 Fig. C-1 901 033 Simultaneous Test Pressure Fig. 5.2 Fig. C-1 901 033 Simultaneous Test Relative 1002 100% Note 2 033 Simultaneous Humidity Test Chealcal N/A Spray 7 8 Radiation 6.3 x 10 R 10 R 031 034 Engineering Analysia Aging 40 years Note 3 Engineering Note 5 Analysis Submergence N/A Component Systes Control Cable Residual Beat Removal Systes Righ Pressure Coolant Injection Systee Rasctor Core Isolation Cooling Systes Manufseturer: Autoestic Depressurization Systen Rome Cable Reactor Water Cleanup Systes Main Steam Systen Model or Type Reactor Recirculation Systee ILF/FVC/FVC Service Function: Mov-23-15, Mov-2-74, MOV-13-15 MOV-2-53A Electrical control MOV-2-535, MOV-2-54A, MOV-2-545, MOV-12-15 MOV-10-18, MOV-10-32, RV-2-71A, RV-2-71B Accuracy: RV-2-71C, RV-2-71D, FCV-2-39 Specified: N/A Demonstrated: N/A Location: Areat Prima *y Containment Elevation: 240'-0" and above Flood Level Elevation: 239'-8" Above Flood Level Tee (C-1)

3' FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM C NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. i (4) Additional information is contained in Documentation Reference (s): i 035, 036. (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. DOCUMENTATION

REFERENCES:

i 031 Engineering Analysis #VY-103, " Radiological Dose Calculation". 033 Correspondence between Rome Cable and Vermont Yankee Nuclear Power Station documenting environmental testing. 034 Engineering Analysis #VY-303, " Qualification for Radiation Enviro nmen t". 035 Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company transmitting Environmental Certification. 036 Ebasco Specification, VYNP-IV-C-2C, "600V Control Cable" - Revision 5. 901 Memo, B. C. Slifer to S. F. Urler.owski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, j i 1980. (C-2) i I

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e FACILITT VEllMONT TANKEE 30CEET,,No.: 50-271 ENCLOSURE 3 ENVIRO *fMENTAL QUALIFICATION /ORKSEET = ITEM D ^ ENVIRONMENT DOCLNENTATION REFERENCE QUALIFICATI0% QUTSTANDING FARANETER SPECIFIED QUALIFIED $7ECIFIED QUALIFIED METPCD ITEMS Operating Long Note 1 Engineering Note 6 Time Tara Analysis Temperature Fig. 5.1 Fig. D-1 901 043 Simultaneous Test Pressure Fig. 5.2 Fig. D-1 901 043 Simultaneous Test Relative 100: 100% Note 2 043 Simultaneous Humidity Test Chemical N/A Spray 7 8 Radiation 6.3 x 10 R 10 R 041 043 Sequential Test Aging 40 years Note 3 Engineering !!ote 5 Analysis Submergence N/A Coopenent: System Thermocouple Cable Foot-Accident Monitoring Systes Manufacturer Servlee Lewis Enginering TE-16-19-30 Model or Type SR/SR Function: Drywell Temperature Monitoring Accuracy: Spccified: N/A Demonstratada N/A ucation: Are F Frimary Containment Elevation: 265'-0* and above Flood Levels F'evation: 239'-8" Above Flood Level Tes i i l (D-1)

I FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM D NOTES: t (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 044, 045. (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. ~ DOCUMENTATION

REFERENCES:

041 Engineering Analysis fVY-104, " Radiological Dose Calculation". 043 FIRL Test Report #F-C2781, " Test of Electrical Cables Under Simulated Post-Accident Reactor Containment Service", prepared for Lewis Engineering Company, April 1970. 044 Ebasco Specification, VYNP-IV-C-2F, " Thermocouple Cable" - Revision 4. 045 Letter dated October 12, 1978, from Galite, Inc. to Franklin Institute Research Laboratories requesting FIRL Test Report #F-C2781. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. (D-2) i

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( FACILITY: TERMONT YANKEE . DOCEET No.: 50-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORKSHEET - ITEM E ENVIR0!NENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDINO FA M TER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Operating <10 sec. 30 days Note 1 052 Staultaneous Time Test Temperature Fig. 5.1 Fig. E-1 901 052 Simultaneous Test Fressure Fig. 5.2 Fig. E-1 901 052 Simultaneous Test Relative 100% 100% Note 2 052 Simultaneous Hualdity Test Chemical N/A Spray 7 8 Radiation 2.0 x 10 R 2.04 x 10 R 051 05 Sequential Test Aging 40 years Note 3 Engineering Note 5 Analysis Submergence N/A 1 Component: Systes: Limit Switches Main Steam System Manufacturer: Service: NAMCO A0V-2-80A, A0V-2-80s, A07-2-80C, A0V-2-80D Model or Type: EA 740-86700 Rev. D Functions Re, actor Protection System Input I Accuracy: Specified: N/A Demonstrated: N/A 14 cation: Areat Primary Containment Elevation: 254'-0" and above Flood Level

• levation:

239'-8" Above Flood Level Yes (E-1)

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 1 ITEM E NOTES: i (1) These switches are required only to anticipate the pressure and flux transient which would occur if the main steam isolation valves should close during an operational event. (2) 100% relative humidity has been assumed due to saturated steam condi tions. (3) A 40-year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present time, will be provided when it becomes available. DOCUMENTATION

REFERENCES:

051 Engineering Analysis #VY-105, " Radiological Dose Calculation". 052 Acme-Cleveland Development Company Test Plan dated 8/31/77, " Qualification of Series EA-180 and EA-740 switches for Class lE Use - in Nuclear Power Plants in Compliance with IEEE Standard 382-1972". 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. (E-2) r

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( c ITEM F i I s e

( t i FACILITY: VERMONT TANREE DOCEZT No.: 50-271 ENCLOSURE 1 s ENVIRONMENTAL QUALIFICATION WORRSHEET - ITEM F ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING FARAMETER SFECIFIED QUALIFIED SFECIFIED QUALIFIED METHOD I ITEMS Operating Long Note 1 Engir.eering Note 6 Time Ta ra / Analysis Tempera ture Fig. 5.1 Fig. F-1 901 063 Simultaneous Test Pressure Fig. 5.2 Fig. F-1 901 063 Simultaneous Test Relative 1001 1 00: Note 2 063 Simultaneous Bumidity Test Chemical N/A Spray 7 8 Radiation 6.3 x 10 R 2 x 10 R 061 063 Sequential Test Aging 40 years Note 3 Engineering Note 5 Analysis Submergence N/A Component: System: Solenoid Oper. Valve Automatic Depressurization Systes l Ma nu f acture r: Service s ASCO RV-2-71A, RV-2-713, RV-2-71C, RV-2-71D Kodel of Type: 206-381-6F Function: Filot Valve 1 Accuracy: Specified: N/A Demonstrated: N/A Location: Areat Primary Containment Elevation 272'-0* and above Flood Levels Elevation: 239'-8* I Above Flood Level Yes (F-1)

i FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM F { NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for 1 ng-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. DOCUMEh'IATION RE!rRENCES: 061 Engineering Analysis #VY-106, " Radiological Dose Calculation". 063 Test Re' port No. AQS21678/TR, " Qualification Tests of Solenoid Valves by Environmental Exposare to Elevated Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance, Accident Radiation and Loss-of-Coolant Accident (LOCA) Simulation," dated March,1978. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. (F-2) L-

N ) f" l l 346_,l f f h -346/110] e / 320/75 7 T 3 E 300._f280/70 OPEN-CLOSE D CYCLE c" Within g 10 sec. chemical 250/15 g ga spray to S be startc<1 oDR: 3 O L p 200/10 E S se 140 Pre-test Amb.ent i i s i .i i i f 3 5 8 11 4 DAYS 30 DAYS IIR llR IIR llR TIME F/GuRE F-/

7 i i f ITEM G 2 f ? k us u a n o n

( t . FACILITY: VERMONT TANKEE DOCKET No.: 50-271 ENCLOSURI 3 ENVIRONMENTAL QUALIFICATION IdORKSEEET - ITEM C ENVIRONMENT DOCUMENTATI0W REFERE!CE QUALIFICATI0!i OUTSTANDING FARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS } Operating Long Note 1 Engineering Note 6 Time Tera Analysis Temperature Fig. 5.1 Fig. G-1 901 073 Simultaneous Test Pressure Fig. 5.2 Fig. G-1 901 073 Simultaneous Test Relative 100% 100% Note 2 073 Simultaneous Humidity Test Chemical N/A Spr ay 7 8 Radiation 6.3 x 10 R 2 x 10 1 071 073 Sequential Test Aging 40 years Note 3 ~ Engineering Note 5 Analysis Submergence A Component: System: Solenoid Oper. Valve Main Steam System Manufacturer: Service: ASCO AOV-2-80A, A0V-2-805, A0V-2-80C, A0V-2-80D Model or Type I NF8323A36V (Note 7) Pt.netton: Filot Valve Accuracy: Specified: N/A Demonstrated: N/A Location: Areas Prima 7 Containment Elevation: 254'-0" and above FIood Levels-Elevation: 239'-8* Above Flood Invel Tes i (c-1)

FACILITY: VERM0hT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM G NOTES: k (1) A long-term operation requirement of 1 year has been assumed. r (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): (5) An aging evaluation 16 being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes a/ailable. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The solenoid operated valves currently installed are ASCO #HTX8320 and HV166-592. Although we have assurance from the vendor that these ~ solenoid operated valves will perform adequately; it is planned to replace them, as a precautionary seat 2re, with fully qualified ASCO

1. NP8323A36V SOV's.

The ASCO #NP8323A36V solenoid operated valves ~ will be installed during the 1980 refueling outage. DOCmiENTATION

REFERENCES:

071 Engineering Analysis #VY-107, E.-diological Dose Calculation". 073 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. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dat_a April 18, 1980. (G-2)

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i ( f i FACILITTa VERMONT YANKEE DOCEZT No. 50-271 ENCLOSLW 3 ENVIRONMENTAL QUALIFICATICN WORKSHEET - ITEM H ENVIRONMEhi DOCLHENTATION REFERENCE QUALIFICATION OL7 STANDING F @ ETER SFECIFIED QUALIFIED SFECIFIED QUALIFIED METHOD ITEMS Operating long Note 1 Engineering Note 6 Time Tera Analysis Temperature Fig. 5.1 fig. B-1 901 083 Simultaneous Test Pressure Fig. 5.2 Fig. H-1 901 083 Simultaneous Test Relative 1001 100% Note 2 083 Simultaneous Humidity Test Chemical Spray 7 8 Radia tion 6.3 x 10 R 2 x 10 R 081 083 Sequential Test Aging 40 Years Note 3 Engineering Note 5 Analysis Submergence N/A Component: Systent Thermocouple Assembly Post-Accident Monitoring System Manufacturert Service: FYC0 TE-16-19-30 Model or Typet 02-3171-08 (Note 7) Function: Drywell Temperature Monics. ring Ac cur ac y t Specified: N/A Demonstrated: N/A 14 cation: Areas Primary Containment Ilevation: 265'-0* Flood tevels Elevation: 239'-8* Above Flood Invel Tem e (M-1)

FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM H 7 .i NOTES: (1) A long-term operation requirement of 1 yeer has been assumed. i (2) 100% relative humidity has been assemed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Refereace(s): (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present time, will be provided when it beccmes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The thermocouple presently installed is a Thermo-Electric Co. Model Ce S16-2-516. Although Thermo-Electric has indicated that the thermocouple installed at Vermont Yankee would have been designed and manufactured to meet the specified environmental conditions, all records of any such action have been destroyed. Consequently, this thermocouple will be replaced with one having proper qualification documentation. The PYC0 model #02-3171-08 thermocouple will be installed during the 1980 refueling outage. DOCUMENTATION REFEP.ENCES: 081 Engineering Analysis #VY-108, " Radiological Dose Calculation". 083 Test Report Document #770831, " Qualification Tests of Thermocouples and RTD Assemblies by Environmental Exposures to Elevated Temperature, Radiation, Seismic Simulation, Vibration Endurance, and Loss-of-Coolant (LOCA) Simulation," dated April,1977. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. ~ (H-2) i

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FACILITY: VERMONT TANKEE J DOCKET No.: 50-271 ENCLCSUR2 3 i ENVIRONMENTAL QUALIFICATION WORKSHEET - ITEM I ENVIl0NMEST DOCLHENTATION REFERENCE QUALIFICATION OUTSTAS"JINO { PARAMETER SPECIFIED QUALIYIED SPECIFIED QUALIFIEP METHOD ITEMS Ope rating Long Note 1 Engineering Note 6 Time Tara Analysis Tempe rature Fig. 5.1 Fig. 1-1 901 093 Simultaneous Test Pressure Fig. 5.2 Fig. I-1 901 093 Simultaneous Test Relative 100% 100% Note 2 093 Simultaneous Humidity Test Chemical N/A Spray 7 8 Radiation 6.3 x 10 7. 10 R 091 093 Sequential Test Aging 40 Years Note 3 Engineering Note 5 Analysis Submergence N/A Component : System: Penetration Assembly All Systees Inside the Primary Containment Manufsettrer: Service: General Electric All Equipment Inside the Frimary Contalmeent Model or Type NS02, NS03, NSO4 Function: Electrical Penetration Accuracy: Specified: N/A Demonstrated: N/A Location: Area Primary Containment Elevation: 252'-0* and above Flood Levelt Elevation: 239'-8" Above Flood Level: Yes b (I-1)

FACILITY: VERMONI YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM 1 9 I { NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to sats rated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 094, 095. (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the prasent time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. DOCUMENTATION

REFERENCES:

091 Engineering Analysis #VY-109, " Radiological Dose Calculation". 093 General Electric Qualification Iest Report for Electrical Penetration Assemblies. 094 Letter dated September 6,1978, General Electric to Vermont Yankee Nuclear Power Station discussing electrical penetration assembly test re po rt. 095 Extract from the Vermont Yankee FSAR. croviding a further clarification of penetration qualification with respect to radiation. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 16, 1980. (1-2)

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FACILITY: VERM0!ff YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORK 3REET - ITEM J ENVIRO?ttENT MK:UMENTATION REFERENCE QUALIFICATION OUTSInNDING SFECIFIED QUALIFIED SFECIFIED QUALIFIED METROD', ITEMS fARAMETER Operating Long Note 1 Engineering Note 6 Analysis Time Ta ra Taeperature Fig. 5.1 Fig. J-1 901 103 Simultaneous Test Fressure Fig. 5.2 Fig. J-1 901 103 Simultaneous Tese Relativa 100% . 30% Note 2 103 Simultaneous Humidity Test Chemical N/A Spray 7 7 Radiation 6.3 x 10 R 8.7 x 10 R 101 104 Engineering Analysis Aging 40 Years Note 3 Engineering Note 5 Analysis Submergence N/A Component: System: Terminal Blocks Automatic Depressurization System Main Stena System Manufacturert Reactor Recirculation Systen States Reactor Water Cleanup System High Pressure Coolant Injection Systen Model or Type Reactor Core Isolation Cooling System Type NT Reactor Sampling System Residual Heat Renoval Systen Function: Electrical Connection Se rvice: RV-2-71A, KV-2-715 RY-2-71C, kV-2-71D Accuracy: MOV-23-15 A0V-2-80A, A0V-2-80B, A0V-2-SOC Specified: N/A A0V-2-80D, MOV-2-74, MOV-15-15, MOV-2-53A Demonstrated: N/A MOV-2-533, MOV-2-54A, MOV-2-548, FCV-2-39 MOV-12-15, MOV-10-18 MOV-10-32 Location: Area Frimary Containment Elevation: 252'-0" and above Flood Level: Elevation: 239'-8" Above Flood Level: Yes l l j (J-1)

FACIL7.TY: VERMONT YAhEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM J NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed bue to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 105. (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This informatien, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. DOCUMENTATION

REFERENCES:

101 Engineering Analysis #VY-110 " Radiological Dose Calculation". 103 Letter dated February 2,1978, General Electric to Vermont Yankee ~ Nuclear Power Station discussing electrical terminal block testing and terminal block materials. Test report is attached. 104 Engineering Analysis #VY-310, " Qualification for Radiation Environment." 105 Letter dated January 27, 1978, The States Company to Yankee Atomic Electric Company with enclosures describing terminal block materials. 901 Memo, B. C. Slifer to S. F. Urbanowski, " Post-Accident Containment Pressure / Temperatures, Vermont Yankee," NED 80-341, dated April 18, 1980. (J-2) i

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FACILITY: VERMONT TANKEE DOCKET NO.: 50-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORKSHEET - ITEM P ENVIR0!0 TENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS t Ope rating Long Note 1 Engineering Note 6 Time Tern Analysis i Tempe rature 300'F Fig. F-1 903 162 S.aultaneous Note 8 (Max.) Test Pressure 4 peig Fig. F-1 903 162 Simultaneous Note 8 (Max.) Test Relative 1001 100% 903 162 Simultaneous Bualdity Test Chemical N/A Spray b Radiation lo a 165 Engineering Note 7 Analysis Aging 40 years Note 2 Engineering Note 5 Analysis Submergence N/A Component: Systes: Power Cable Reactor Core Isolation Cooling Systen Manufacturer: Se rvice Rome Cable MOV-13-16 Modei or Type ILF/PVC Function: Electrical Power Accuracy: Specified: N/A Demons trated: N/A Location - Areat Steam Tunnel Elevation: Flood Level Elevation: N/A Above Flood Level N/A (F-1)

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM P j NOTES: ? (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40-year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 163, 164. (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) A radiological evaluation is being performed by EDS Nuclear.. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (8) The basis for the entry under specified environment appears questionable and is S.Ang verified. If necessary, this value will be changed when thc verification is complete. DOCUMENTATION

REFERENCES:

l ,162 Correspondence between Rome Cable and Vermont Yankee Nuclear Power Station documenting environmental testing. 163 Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company transmitting Environmental Certification. i 164 Ebasco Specification, VYNP-IV-C-2B, "600V Auxiliary Power Cable" - Revision 5. 165 Engineering Analysis #VY-316, " Qualification for Radiation Environment". 903 Vermont Yankee FSAR Question / Answer 7.7. (P-2) l

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FACILITT. Vtan0NT YANEEE DOCERT No.: 50-271 ENCL 0tintE 3 ENVIRONMENTAL QUALIFICATION WORKSMEET - ITEM Q ENVIR0lMENT DOCUMENTATION RZFERENCE QUALIFICATION QUTSTANDING PARAMETER SFECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS i 'pperating Long Note 1 Engineering Note 6 ~ Time Tern Analysis Tempe rature 300'F Fig. Q-1 903 172 Simultaneous Note 8 (Mas.) Test Pressure 4 peig Fig. Q-1 903 172 Simultaneous Note 8 (Max.) Test Relative 1001 100% Note 2 172 Simultaneous Bualdity Test Chemical N/A Spray 8 Radiation 10 R 175 Engineering Note 7 Analysis Aging 40 Years Note 3 Engineering Note 5 Analysis Submergence N/A Component System: Control Cable High Pressure Coolant Injection System Reactor Core Isolation Cooling Systen Manufacturer: Main Steam Systen Rome Cable Service: Model or Type: MOV-23-16 M07-13-16 A0V-2-86A. A07-2-868 XLP/FVC/FVC ADV-2-86C, A0V-2-86D Function Electrical Control Accuracy: Specified: N/A i Demonstrated: N/A laestion: Area: Steam Tunnel Elevation: Flood tavel: Elevation: N/A Above Flood Level N/A (Q-1)

FACILITY: VERMONT YANKEE DOCKET No. : 00-271 ENCLOSURE 3 ITEM Q I NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A. rear qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 173, 174. (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qs_alifications have been determined for all environmental parameters. (7) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it'becomes available. (8) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCLHENTATION

REFERENCES:

172 Correspondence between Rome Cable and Vermont Yankee Nuclear Power Station documenting environmental testing. 173 Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company transmitting Environmental Qualification. 174 Ebasco Specification, VYNP-IV-C-2C, "600V Control Cable" - Revision 5, 175 Engineering Analysis #317, " Qualification for Radiation Environment". 903 Vermont Yankee FSAR Question / Answer 7.7. (Q-2)

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...n. FACILITY: 7taMolff TANEEE DOCIET m.: 30-271 INCtest:1tz 3 ENVIRONMENTAL QUALIFICATION WORKSEZET - gw I', EWVIROIGENT DOCUMENTATION REFERENCE QCALIFICATION OUTSTANDING PARAMETER SPECIFIED QUAL 171ED SFECIFIED QUALIFIED MET 50D ITIMS O'erating Imag Note 1 Engineering Note 6 p Time Tern Analysis Temperature 300*F Fig. 1-1 903 18k Simultaneous Note 8 (Max.) Test Fressure 4 pela Fig. 1-1 903 182 elmultaneous Note 8 (Max.) Test talative 1001 1001 Note 2 182 simultaneous Euaidity Test Chanical N/A Spray 8 Radiation 2 x 10 1 182 Sequential Note 7 Test Aging 40 Years Note 3 Engineering Note $ Analysis Submergence N/A component: Systent solenoid Oper. Velve Main Steas Systes Manufacturer Servleet Asco A0v-2-86A, Aov-2-863 Aov-2-86C, Aov-2-86D Nodel of Type NP8323A36V(Note 8) Funettons Filot Talve i Accurney 1 Specified: N/A * ~ ~ Demonstrated: N/A 14 cation dres: Steam Tunnel l Ilevation: 234'-0* and above l Flood levels i i Elevation N/A Above Fleed 149el: N/A i 1 l (R-1) l l

FACILITY: VERM0hT YAhTEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM R NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. i (8) The solenoid operated valves currently installed are ASCO fBTX8320 and HV166-592. Although we have assurance from the vendor that these solenoid operated valves will perform adequately; it is planned to replace them, as a precautionary measure, with ASCO fNP8323A36V SOV's. The ASCO #NP8323A36V solenoid operated valves will be installed during the 1980 refueling outage. (9) The basis for the entry under specified environment appears questionable and is being verified. If n&cessary, this value will be changed when the verification is complete. DOCUMEhTATION

REFERENCES:

182 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. 903 Vermont Yankee FSAR Question / Answer 7.7. (R-2) l l l

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FACILITY: VERMONT TANRIE DOCKET NO. 50-271 ENCI,0scRE 3 ENVIRotettrfAL QUALIFICATION WORK $NEET - ITEM S ENVIR0teENT DOCUMENIATION REFERENCE QUALIFICATION OUTSTANDING SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD. ITEMS ,FARAMETER ope rating (10 sec. 30 days Note 1 191 Simultaneous Time Test Tempe rature 300'r Fig. 5-1 903 191 Simultaneous Note 7 1 (Max.) Test Fressure 4 peig Fig. 5-1 903 191 Staultaneous Note 7 (Max.) Test Relative 100% 1001 Note 2 191 Slaultaneous Rumidity Test i Chemical N/A Spray 0 Radiation 2.04 x 10 R 191 Sequential Note 6 Test Aging 40 Tears Note 3 ' Engineering Note 5 Analysis Submergence N/A Ccaponent: Systems Limit Switch Main Steam Systen Manufacturer Services MAMCO A0V-2-86A, ADV-2-868, A0V-2-86C, A0Vu' 96D Nodel or Type: EA-740-86700 Rev. D Funetton Reactor Protection System Input Accuracy: Spec 111ed: N/A Demonstrated: N/A Location: Area: Steam Tunnel Elevation: 254'-0* and above Flood Level: ~" Elevation: N/A Above Flood Level N/A (S-1)

FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM S j NOTES: (1) These switches are required only to anticipate the pressure and flux trantient which would occur if the main steam isolation valves should close during an operational event. (2) 100% relative humidity has been assumed due to saturated steam condi tions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): (5) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (6) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCvMENTATION

REFERENCES:

191 Acme-Cleveland Development Company Test Plan dated 8/31/77, " Qualification of Series EA-180 and EA-740 switches for Class IE Use in Nuclear Power Plants in Compliance with IEEE Standard 382-1972". 903 Vermont Yankee FSAR Question / Answer 7.7. (S-2)

9 l 1 2 340 7 3 INDICATES CYCLING 320 L OF VALVE ACTUATOR ] 280 g [ 250 2 w N i iS 200 1 - Differential pressure - 63 PSI 2 ditto - 63 PSI 3 ditto . - 33 PSI 4 ditto - 18 PSI 5 ditto - 3 PSI I 140 u i i i 10' 3 5 8 11 4 14 10 SEC liR iiR HR IIR DAYS' DAYS DhYS 5 HR-10 SEC TIME F/GURE S-l

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FACILITTs VERMolff TANREE DOCKET NO. 50-271 Eset0Setz 3 ENVIRON'fENTAL QUALIFICATION 1dORKSHEET - ITEM T ENVIR0! MENT DOCLHENTATION REFERENCE QUALIFICATION OUTSTANDINO FARAMETER SPE*1FIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS i ~ 10perating Long Note 1 Engineering Note 6 Time Te rn Analysis Tempe rature 300*F Fig. T-1 903 202 Simultaneous Note 8 (Max.) Test Pressure 4 peig Fig. T-1 903 202 Simultaneous Note 8 (Max.) Test Relative 100Z 1 00I Note 2 202 Simultaneous Basidity Test Chealcal N/A Spray 7 Radiation 8.7 x 10 R 204 Engineering Note 7 Analysis Aging 40 Years Note 3 Engineering Note 5 ' Analysis Submergence N/A Component: System: Terminal Blocks Main Steam System Manufacturer Se rvice: States A0V-2-86A, A0V-2-868, ADV-2-86C, A0V-2-86D Model or Types Type NT Function Electrical Connection Accuracy: Specified N/A Demonstrated: N/A Location: Areas Stens Tunnel Elevations j Flood Levels Elevation N/A Above Flood Level N/A (T*1) l

FACILITY: VERM0hi YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM T ~ h NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40-year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 203. (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present 'j time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided ~ when it becomes available. (8) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMENTATION

REFERENCES:

202 Letter dated February 2,1978, General Electric to Vermont Yankee Nuclear Power Station discussing electrical terminal block testing and terminal block materials. Test report is attached. 1 203 Letter dated January 27, 1978, The States Company to Yankee Atomic i Electric Company with enclosures describing terminal block materials. j i 204 Engineering Analysis #320, " Qualification for Radiation Environment". 903 Vermont Yankee FSAR Question / Answer 7.7. (T-2)

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i FACILITTs 7ERMONT IANKEE l DOC' SET NO. $0-271 ENCLOSURE 3 ENVIRONY.NTAL QUALIFICATION WORK $REET - ITEM U ENVIR0!NENT DOC W NTATION RZFEAINCE QUALIFICATION OL*ISTANDING PARAMETER SPECIFIED QUALIFIED SPECW1ED QUALIFIED NET 1dCD, ITEMS I ' Ope r a ting (10 sec. Note 1 212 Simultaneous Time Test s Tempe rature 300'F Fig. U-1 903 212 Simultaneous - No te 7 (Max.) Test Pres sure 4 pois Fig. U-1 90 3 212 Sinultaneous Note 7 (Max.) Test R41stive loot 1001 Note 2 212 Simultaneous Eualdity Test Chemic al N/A Spray 8 Radiation 2 x 10 R 212 Sequential Note 6 Test Aging 40 years Note 3 -Engineering Note 5 Analysis Submergence N/A Component: Systems Control Cable Main Steam Systes Manufacturer Se rvice s Rockbe s tos A0V-2-86A.. ADV-2-665, ADV-2-86C, ACV-2-86D Model or Type Firewall SR Fucttion: Electrical control Accur acy: Spe cified : N/A Demonstrated : N/A Loestion: Areas Steam Tuamel Elevation: Flood Levelt Eleva tion: N/A Above Flood Involt N/A 4 (U-1)

FACILITY: VERMONT YANKEE' DOCKET No.: 50-271 ENCLOSURE 3 ITEM U k NOTES: (1) This cable is required only to anticipate the pressure and flux transient which would occur if the main steam isolation valves should close during an operational event. (2) 100% relative humidity has been assumed due to saturated steam conditions. (3) A 40 year qualified life requirement has been assumed. (4) Additional information is contained in Documentation Reference (s): 213. (5) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This information, which is incomplete at the present time, will be provided when it becomes available. (6) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMENTATION

REFERENCES:

} 212 Rockbestos Company Report - Qualification of Firewall SR Class lE Electric Cables. 213 Rockbestos Company Firewall SR Power and Control Cable Specification. 903 Vermont Yankee FSAR Question / Answer.7.7. (U-2) u

~ Spray for first 24 hrs, at rate of' O.15 ggn per square foot of spray area with solution of the following composition: 0.28 molar H 60 (3M pg= kron) 3 3 340 104 psfg 104 psIg 0.064 molar Na s 0 223 f[ Na0li to make pH between 9-11 at 77'F. 75 psfg 320 E .l ,2,,a n 3o. i 1 >h k250 35 PSI 9 ,g + LE k ~ 200. 0 P5i9 140 1 1 I I I I a 10 3 s e it is 4 nays. Sec Hr Hr He ifr ifr 30 TlHE Days FKru/?E U-/

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FACILIITs VERMONT YANKEE 30CEET Wo.: 50-271 ENetOSURI 3 ENVIRONMENTAL QUALIFICATION 1dORKSREET - ITEM AA ENVIR0!OTENT DOCUMENTAf10N REFERENCE QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SFECIFIED QUALIFIED METHOD ITEMS ope rating Long Note 1 8, Engineering Note 6 Time Te ru Analysis Temperature 150*F 150*F 903 511 Engineering Note 7 (Max.) Analysis Pressure 0.25 peig 0.25 peig 903 511 Engineering Note 7 (Max.) Analysis Relative 901 901 903 511 Engineering Note 7 Humidity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component Systems ~ Solenoid Operated Yelve Primary Containment and Atmospheric Control Systen Manu f acturers se rvice: ASCO V16-19-7A, 716-19-75 V16-19-8 V16-19-9, 716-19-10 Model or Type 8316315 Function: Containment Isolatio-Accuracy: Specified: N/A Demonstrated: N/A Location: Areas Reactor Building Elevations, Flood Level Elevation: N/A Above Flood Level N/A 1 \\ l i I (AA-1)

FACILITY: VERM0h7 YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM AA i } NOTES: (1) A long-term operation requiretant of one year has been assumed. (2) A 40 year qualified life requirement has been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s) (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incom'plete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualificat*.ons have been determined for all environmental parameters. (7) The basis for the entry under sper.ified environment appears questionable and is being verified. If necessary, this value will be changed w'aen tiie verification is complete. DOCIMENTATION

REFERENCES:

511 Engineering Analysis #511, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 9 (AA-2) l I i

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FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM BB NOTES: (1) A long-term operation requirement of one, year has been assumed. (2) A 40 year qualified life requirement has been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all envitonmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will i be changed when the verification is complete. l DOCUMEh'IATION

REFERENCES:

521 Engineering Analysis #521, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 4 4 (BB-2) l i

... ~. ~. i FACILITY: VERMONT TANREE DOCERT No.: 50-271 J ENCt0setE 3 ~ ENTIRONENTAL QUALIFICATION WORESEET - ITEN BB 3 ENVIROISBNT DOCUMENTATION REFERENCE QCALIFICATION OUTSTANDING

PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFtID METHOD

ITEMS t Operating Long Note 1 Engineering Note 6 Time Te ru e Analysis 1 Tempe rature 150*F 150*F 903 521 Engineering Note 7 (Max.) Analysis Pressure 0.25 peig 0.25 peig 903 521 Engineering Note 7 (Max.) Analysis Relative 901 902 903 521 Engineering Note 7 Bunidity (K22.) Analysis Chemical N/A Spray I Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A 1 J Components Systeen Solenoid Operated Valve Primary Containment and Atasepheric Control Systes a Manufgeturer: Services ASCO V-SB-6, V-$3-7 Model or Type 8302C29RF Punctions Containment Isolation r Accuracy: - Specified: N/A Demonetrated: N/A Location: Areas Reactor Building Elevation: 4 Flood Levels Elevatteer 5/A Above Flood Imvels-N/A e (BB-1)

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FACILITY: TERMONT YAMEEE DOCEET No.: 30-271 ENCLOSt*RE 3 ENVIRONMENTAL QUALIFICATION WORKSREET - ITEM CC ENVIROM4ENT DOCLHENTATION REFERENCE QUALIFICATION OUTSTANDING

• FARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Operating Long Note 1 Engineering Note 6 Tina Te rm Analysis Tempera ture 150*F 150*F 903 531 Engineering Note 7 (Max.)

Analysis Pressure 0.25 psia 0.25 peig 903 531 Engineering Note 7 (Max.) Anslysis Relative 90% 90% 903 531 Engineering Note 7 Humidity (Kax.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis 4, Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: Systet Solenoid Operated Valve Ftinary Containment and Atmospheric Control Systee Manu f acture r Service: ASCO V16-19-23 Model or Type 8321A6 Function: Containment Isolation Accuracy: Specified: N/A Demonstrated: N/A Location: Areas Reactor Building Elevation: Flood Level Elevation: N/A Above Flood Invel: N/A (CC-1)

FACILITY: VERM0hi YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM CC NOTES: i (1) A long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has*been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionsble and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMEhiATION

REFERENCES:

531 Engineering Analysis #531, " Evaluation of invironmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. (CC-2)

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FACILITY: VERMONT YANREE DOCKET NO.: 50-271 ENCLOSURE 3 ENVIROMNTAL QUALIFICATION SORKSHEET - ITEM DD ENVIRoleENT DOCUMENTA*t10N REFERENCE QUALIFICATION 01, STANDING 7 FARAMETER SPECIFIED QUALIFIID SPECIFIED QUALIFIED METHOD ITEMS operating long Note 1 Engineering Note 6 Time Tera i Analysis Tempe rature 150*F Fig. DD-1 503 541 Engineering Note 7 (Max.) Analysis Pressure 0 25 peig Fig. DD-1 903 541 Engineering Note 7 (Max.) Analysis Relative 90% 1001 903 541 Engineering Note 7 Eunidity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: Systems Control Cable Hasting and Ventilation Systes Containasent Atmosphere Dilution Systes Manufacturer Residual Heat Removal Systes Rome Cable Primary Containment and Atmospheric Control System Model or Type r Service: ILP/PVC/PVC Mov-14-11A, MOV-14-113, M07-14-12A, MOV-14-125 MOV-14-26A, MOV-10-13A. M0y-10-135, NOV-10-13C Function: MOV-10-13D, MOV-10.-17, MOV-10-15A, Mov-10-158 Electrical Control MOV-10-15C, MV-10-15D, NOV-10-27A. MOV-10-278 MOV-10-25A, MOV-10-255, MOV-10-26A, MOV-10-268 Accuracy: MOV-10-31A, MOV-10-313, MOV-10-38A, MOV-10-388 Specified: N/A P10-1A, P10-15,' P10-1C, P10-1D Demorstrated : N/A P8-1A, P8-18 F8-1C. P8-ID RRU-5, RRU-6, RRU-7, RRU-8 Location: V-SB6, V-SB7, V16-19-7A, V16-19-78 Areas Reactor Building V16-19-8 V16-19-9, V16-19-10 V16-19-23 Elevation: FS0-109-75A1, F50-109-75A2, FS0-109-7551 F50-109-7582, FSO-109-75C1, FSO-109-75C2, FSO-109-75D1, FS0-109-75D2, Flood Level FSO-109-76A, FSO-109-763, VG-9A, VG-98 Eleva tion: N/A VG-11A, VG-113 VG-12A, VG-125 Above Flood IAvel NsA VG-13A. VG-135, VG-22A, VG-228 VG-24, VG-25 VG-33, VG-34 V16-19-6A, V16-19-68, M0V-11-268 l (DD-1)

FACILITY: VERM0hT YAhE E DOCKET No. : 50-271 ENCLOSURE 3 ITEM DD NOTES: (1) A long-term operation requirement of one, year has been assumed. (2) A 40 year qualified life requirement has'been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): 542, 543. (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMENTATION

REFERENCES:

541 Correspondence between Rome Cable and Vermont Yankee Nuclear Power Station documenting environmental testing. 542 Letter dated August 17, 1978, Cyprus Wire and Cable Company to Yankee Atomic Electric Company transmitting Environmental Certification. 543 Ebasco Specification, VYNP-IV-C-2B, "600V Auxiliary Poser Cable" - Revision 5. 903 Vermont Yankee FSAR Question / Answer 7.7. ) l (DD-2)

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FACILITY: TERM 0NT YANEEE DOCIET No.: 50-271 ENCLOSURE 3 ENV'10NNENTAL QUALIFICATION WORKSEEET - ITEM EE ENVIR0! MENT DOCUhtNTATION REFERENCE l QUALIFICATION OUTSTANDING I FARAMETER SPECIFIED QUALIFIED SPECIFIEC QUALIFIED NETHOD ITEMS

Operating long Note 1 Engineering Note 6

~ Time Ta ra Analysis Tamperature 150'F 903 Engineering , Note 7,8 Analysis Pressure 0.25 peig 903 Engineering Note 7,8 Analysis Relative 1001 903 Engineering Note 7,8 Bumidity Analysis Chealcal N/A Spray Radiation Engineering Note $ Analysis Aging 40 Tears Note 2 Engineering Note 4 Analysis ) Submergence N/A Component: Systems Solenoid Operated Valve Containment Atacephere Dilution System Manufacturer: Services Atkoma tic F50-109-76A. FSO-109-768 Model or Ty gt 31840-VPI-MOD Fuactions Containment Isolation Accur acy: Specified: N/A Demonstrated: N/A locatiot ' Areas Reactor Building Elevation: Flood Levels Elevation: N/A Above Flood Invel: N/A l (EE-1)

FACILITY: VERM01C YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM EE i NOTES: (1) A long-term operation requirement of one ypar has been assuned. (2) A 4D-year qualified life requirement has een assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed whra the verification is complete. ~ (8) Qualification documentation is expected from the vendor. When this information is received it will be entered in the table. DOCUMENTATION

REFERENCES:

903 Vermont Yankee PSAR Question / Answer 7.7. 4 (EE-2)

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FACILITY: TERMONT YAMEE DOCIET No.: 30-271 EwetoSURE 3 ENVIRONMElf7AL QUALIFICATION WORKSHEET - ITEM F7 ENVIRONMEhT DOCLMENTATION REFERINCE QUALIFICATION CLTSTANDING PASAMETER SPECIf1ED QUALIFIED SPECIFIED QUALIFIED METHOD' ITEMS Ope ra ting Long Note 1 Engineering Note 6 Time Te rn i Analysis 76 ape rature 148'T 148*F 904 561 Engineering Note 7 (Max.) Analysis Pre ssure 0.25 pois Atmospheric 903 561 Engineering Note 7 (Max.) Analysis Relative 901 1001 903 561 Engineering Note 7 Bualdity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: System: Motor Residual Beat Removal Systen Manufacturer: Service: General Electric F10-1A, F10-15, F10-1C. F10-1D Model or Type BEJ-205002,8EJ-212003 BEJ-219001,BEJ-219003 Tunettons REA Puep Accuracy: Specified: N/A Demonstrated: N/A Location: Areet Reactor Building Elevation: 213' Flood Level Elevation: N/A Above Flood 149el N/A (FF-1)

FACILITY: VERM0hi YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM FF NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40-year qualified life requirement ha been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laboratory. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under spacified environment appears questionable and is being verified. If necessary, this value will l be changed when the verification is complete. (8) Qualification documentation is expected from the vendor. When this j information is received it will be entered in the table. l DOCUMENTATION

REFERENCES:

561 Engineering Analysis #561, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 904 Vermont Yankee FSAR Section 10.12. (FF-2)

I e' 6 e ITEM GG ? a i l 'l

FACILITY: VERMOFT TANIZE DOCKET No.: 50-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORKSHEET - ITEM CC ENVIR0!4 TENT DOCUMENTATION REFERENCE QCALIFICATION OUTSTANDING FARAMETER SFECIFIED QUALIFIED SFECIFIED QUALITIED METHOD ITEMS Operating Long Note 1 Engineering Note 6 Time Tern Analysis Tempe rature 148*F 148"F 904 571 Engineering Note 7 (Max.) Analysis Pressure 0.25 pois Atmospheric 903 571 Engineering Note 7 (Max.) Analysis Relative 90% 100 903 571 Engineering Note 7 Bualdity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: System: Motor Residual Beat Removal Systen Manu f a c tur e r Service: Westinghouse F8-1A. F8-15, F8-IC, FS-1D Model or Type: 50 #b9F46553 Function: RER Service Water Pump Accuracy: Specified: N/A Demonstrat ed: N/A Location: Area Reactor Building Elevation: 232' Flood Level Elevation: N/A Above Flood Level N/A (CG-1)

FACILITY: VERM0hT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM GG i NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40-year qualified life requirement has/been assumed unless otherwise noted. i (3) Additional information is contained in documentation Reference (s): (4) An aging evaluatinn is being performed by Acton Environmental Testing Laboratory. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of

• the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters.

(7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMENTATION

REFERENCES:

571 Engineering Analysis #571, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 904 Vermont Yankee FSAR Section 10.12. (GG-2-)

t ITEM HH

FACILITY: VERMorf YANKEE 3 - DOCERT 180.: 50-271 ENCLOSL1tt 3 ENVIRONMENTAL QUALIFICATION WORKSREET - ITEM RR ENVIRONMENT DOCUME!rTATION REFERENCE QUALIFICATION OLTSTANDING FARAMETER SFECIFIED QUALIFIED SPECIFIED QUALIFIED

METh0D, ITEMS E

Operating Long Note 1 Engineering Note 6 Time Tern AnalTeis 4 Tempe rature 148'F 904 Engineering Wote 7,9 (Max.) Analysis Pressure 0.25 psig 903 Engineering Note 7,8 (Max.) Analysis Relative 90% 903 Engineering Note 7,8 Busidity (Max.) Analysis Cheetcal N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: System: !!o tor Beating and Ventilation System Manufacturer: Service: Allis-Chalmers RRU-6 Model or type 51-208-578 Function: Reactor Recirculation Unit Accuracy: Specified: N/A Demonstrated: N/A Location Areat Reactor Building Elevation: 232' Flood Level Lleva ttoon N/A Above Flood Level: N/A (na-1)

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM RH I NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40-year qualified life requirement has' been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the ecmponent's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. (8) Qualification documentation is expected from the vendor. When this information is received it will be entered in the table. DOCUMENTATION

REFERENCES:

581 Engineering Analysis #581, " Evaluation' of Envirotsental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 904 Vermont Yankee FSAR Section 10.12. l (HH-2) e e n

I ITEM II 9 9 i L,..

FACILITY: TERMONT TANEEE DOCIET No.: 50-271 ENCLOSURE 3 ENurMNIENTAL QUALIFICATION WORKSHEET - ITEM II P- .9, ENVIRotetENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS hperating Long Note 1 Engineering Note 6 Time Te rn Analysis Tempe rature 150'F 903 Engineering Note 7,8 (Kax.) Analysis Pressure 0.25 peig 903 Engineering Note 7,8 (Max.) Analysis Relative 90% 903 Engineering Note 7,B Humidity (Mar.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: System: Motor Heating and Ventilation System Manufacturers Service: Allis-Cha[mers RRU-5, R10-7, RRU-8 Model or Type 1-5101-39529-2-2 1-5101-39529-3-1 1-5101-39529-3-2 Function: Reactor Racirculation Unit Accuracy: Specified: N/A , Demonstrated: N/A Location: Area: Reactor Building Elevation: 226' and 232' Flood Level Elevation: N/A Above Flood Level N/A (II-1) I

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENOLOSURE 3 ITEM II NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has' been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluatioc of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. (8) Qualification documentation is expected from the vendor. When this information is received it will be entered in the table. l DOCUMENTATION

REFERENCES:

591 Engineering Analysis #591, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. i 1 i i t (II-2) --r =

y. e* o ITEM JJ E I v

FACILITY: VERM0!ff TANKEE wr77 JIO.: 30-271 FNcI.05tRE 3 ENVIRONMENTAL QUALIFICATION idORKSEEET - ITEM JJ ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICA* ION OUTSTANDING FARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Operating Long Note 1 Engineering Note 6 Time Tern Analysis Temperature 148'T 148'F 904 60s Engineering Note 7 (Max.) Analysis Pressure 0.25 pois Atmospheric 903 601 Engineering Note 7 (Max.) Analysis Relative 901 90% 903 601 Engineering Note i Humidity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis { Submergence N/A ) l Component: System Motor 1 Core Spray System Manufacturer Services General Electric F46-1A, P46-15 Model or Type FEJ604010 FEJ604011 i Function: Core Spray Fusp Accuracy: Specified: N/A Demonstrated: N/A Locationt Areas Reactor Building - l Elevation: 213' i Flood Levels Eleration: N/A t Above Flood Level N/A l t l (JJ-1)

FACILITY: VERM0!E YANKEE ENCLOSURE 3 DOCKET No. : 50-271 ITEM JJ NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40-year qualified life requirement has been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, i will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. I (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be chan3ed when the verification is complete. DOCUME!GATION

REFERENCES:

601 Engineering Analysis #601, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. 904 Vermont Yankee FSAR Section 10.12. a t (JJ-2) G

e. no

y 9 9 g 4 4 f r b ITEM KK 4 6 _g

FACILITY: VERMolfF YANKEE DOCKET NO. 50-271 1 ENCLOSL1tE 3 ENVIRONMENTAL QUALIFICATION WORK 5REET - ITEM ltlt EINIRONMENT DOCUMENTATION REFERINCE QUALIFICATION OUTSTANDING 7ARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITEMS Ope rating Long Note 1 l Engineering Note 6 Time Te rs Analysis Temperature 150'F 150*F 903 611 Engineering Note 7 (Max.) i Analysis Fressure 0.25 poig 0.25 peig 903 611 Engineering Note 7 (Max.) Analysis Relative 90: 93: 903 611 Engineering Note 7 Humidity (Max.) Analysis Cheatcal N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A j Component System: i Power Cs' le Core Spray Systee Manufact' er Service: Collyer"~~ F46-1A. F46-13 Model or Type Buty1/ Neoprene Function: Electrical Power Accuracy: Specified: N/A l Demonstrated: N/A j l Location: Areas Reactor Building Elevations i Flood Levels l l ~~dlevation: N/A { Above Flood Level N/A i I l (KK-1) L._

FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM KK NOTES: i (1) ?. long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has,'been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is bei.a performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been detercined for all environmental parameters. 1 (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUME!TIATION

REFERENCES:

611 Engineering Analysis #611, " Evaluation of Environmental Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. l L i (KK-2) i

(- 4 ? f { ( ITEM LL l 1 l 1 f 1 I ( ( l ) k

0 FACILITY: VERMONT YANKEE DOCKET NO.: 50-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORKSHEET - ITEM LL ENVIR0tHENT DOCUMENTATION REFERENCE QUALIFICATION CUTSTANDING FARAMETER SPECIFIED QUALIFIED SPECLFIED QUALIFIED METB00 ITEMS Operating Long Note 1 Engineering Note 6 Time Term 's Analysis 0 Temperature 150 F >150'F 903 621 Engineering Note 7 (Max.) Analysis Pressure 0.25 peig >0.25 psig 903 621 Engineering Note 7 (Max.) Analysis Relative 90% >90Z 903 621 Engineering Note 7 Hualdity ( Max. ) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component System Motor Operator Residual Heat Removal System Core Spray Systen Manufseturer Limitorque Se rvlee Mov-10-25A, NOV-10-258, MOV-10-27A, MOV-10-278 Model or Types M0V-10-265, NOV-10-265, NOV-10-31A, MOV-10-318 SMS-0 SMB-00 SMB-000, SMS-2 MOV-14-11A, MOV-14-118, MOV-10-38A, MOV-10-388 SMB-3, SMB-4, SMB-4T. SMS-1 MOV-14-12A, MOV-10-17 MOV-10-13A, MOV-10-135 MOV-10-13C, MOV-10-13D, MOV-10-15A, MOV-10-158 Function: MOV-10-15C NOV-10-15D, MOV-14-123. NOV-14-26A Valve Operation MOV-14-268 Accuracy - Specified: N/A Demonstrated: N/A Location: Area; Reactor Building Elevations various I Flood Levels Elevation: N/A Above Flood Level N/A (LL-1)

1 FACILITY: VERMONI YANKEE DOCKET No. : 50-271 ENCLOSL*RE 3 ITEM LL NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has'been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will ~ be changed when the verification is complete. DOCintENIATION

REFERENCES:

621 Engineering Analysis #621, " Evaluation of Environmentel Qualifications." 903 Vermont Yankee FSAR Question / Answer 7.7. (LL-2) l l i

(. m J 4 t I A ITEM MM L

FACILITY: VERMONT YANKEE DOCKET No.: 50-271 ENCLOSURE 3 ITEM MM NOTES: i ~ (1) A long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has?been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): 632, 633. (4) An aging evaluation is being performed by Ac. ton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears question'able and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMENTATION

REFERENCES:

631 Correspondence between Rome Cable and Vermont Yaakee Nuclear Power Station documenting environmental testing. 632 Letter dated August 17, 1978, Cyprus Wire and Cable Company *o Yankee Atomic Electric Company transmitting Environmental Certifica clon. 633 Ebasco Specification, VYNP-IV-C-2C, "600V Control Cable" - Revision 5. 903 Vermoct Yankee FSAR Question / Answer 7.7. (MM-2)

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FACILITY: YERMONT TANKEE DOCKET NO.s 50-271 ENCLOS'JRE 3 ENVIR0f0 ENTAL QUALIFICATION 'dORKSHEET - ITEM NN ENVIROttENT DOCLHENTATION REFERENCE QUALIFICATION OUTSTANDINC .FARAKETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METJ0D* ITEMS Opera ting Long Note 1 Engineering Note 6 Time Ters Analysis Temperature 150'F 150*F 903 641 Engineering Note 7 (Max.) Analysis Pressure 0.25 psig 0.25 psig 903 641 Engineering Note 7 (Max.) Analysis Relative 90% 90% 903 641 Engineering Note 7 Eualdity (Max.) Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 years Note 2 Engineering Note 4 Analysis Submergence N/A Component: Systes: Sotenoid Operated Valve Primary Containment and Atmospheric Control Systes Manufacturert Se rvlee t ASCO V16-19-6A, V16-19-68 Model or Typet 8317A29 Function Containment Isolation Accurney: Speciflod s N/A Demonstrated: N/A Location Areas Reactor Building Elevation Flood Levelt Elevation: N/A Above Flood Level: N/A e (NN-1)

FACILITY: VERM0hT YAhTEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM NN j NOTES: (1) A long-term operation requirement of one year has been assumed. (2) A 40 year qualified life requirement has> been assumed unless otherwise noted. (3) Additional information is contained in documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value will be changed when the verification is complete. DOCUMEhTATION

REFERENCES:

641 Engineering Analysis #641, " Evaluation of Environmental Qualifications." 903' Vermont Yankee FSAR Question / Answer 7.7. (NN-2)

r h 8 ITEM 00 i w r, m

FACILITY: VERMONT YANRIE DOCKET NO. $0-271 ENCLOSURE 3 ENVIRONMENTAL QUALIFICATION WORKSEEET - ITEM 00 ENVIRONMENT DOCLHENTATION REFERENCE QUALIFICATION CL*TSTANDING PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED

METHOD, ITEMS Operating Long Note 1 Engineering Note 6 Time Tern Analysis l

Tempe ra ture 150'F 903 Engineering pote 7.8 Analysis Pressure 0.25 peig 903 Engineering Note 7.8 Analysis Relative 100E 903 Engineering Note 7.8 Bualdity Analysis Chemical N/A Spray Radiation Engineering Note 5 Analysis Aging 40 Years Note 2 Engineering Note 4 Analysis submergence N/A Component : Systes: Solenoid Operated Valve Containment Atmosphere Dilution System Manufacturer: Service: Atkomatic FSO-109-75A1. FSO-109-75A2. F30-109-75Bl. F50-109-7532 FSO-109-75C1. FSO-109-75C2. FSO-109-75D1 F50-109-75D2 Model or Type 15840-VFI-MOD Function: Containment Isolation Accuracy: Specified: N/A Demonstrated: N/A Location: "Areat Reactor Building Elevation: Flood Levels Elevation: N/A Above Flood Level: N/A I (00-1)

FACILITY: VERMONT YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM 00 NOTES: (1) A long-term operation requirement of 1 year has been assumed. (2) A 40 year qualified life requirement has'been assumed unless otherwise noted. (3) Additional information is contained in Documentation Refe ence(s): i (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDS Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being verified. If necessary, this value vill be changed when the verification is complete. ~ (8) Qualification documentation is expected from the vendor. When this information is received it will be entered in the table. DOCQ4EhTATION

REFERENCES:

903 Vermont Yankee FSAR Question / Answer 7.7. (00-2)

e 9 e s t I f r f ITEM PP i

FACILITY: VERMONT YANIEE DOCKET No.: 50-271 EMCLOSURE 3 ENVIt010 ENTAL QUALIFICATION IdCRKSEEET _ ITEM PP ENVIR0! GENT DOCLHENIATION REFERENCE PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED METHOD ITD.S QUALIFICATION OUTSTAC ING { 0perating Long Note 1 Time Tern Engineering Note 6 Analysis Temperature 150'F e, 90 3 Engineering Notw 7,8 i Analysis Pressare 0.25 psig 903 Engi.- e'

• 3 Note 7.S Anal},*

Relative 1002 ?03 Bumidity Engineering Note 7,8 Analysis Chemical N/A Spray l Radiation Engineering Note 5 Analysis Aging 40 Years Note 2 Engineering Note 4 Analysis Submergence N/A l Component i Systes: Solenoid Operated Valve Containment Atmosphere Dilution Systen Manufacturer Se rvice: Taraat Rock VG-23, VG-26, VG-75A3, VG-75A4 _Model or Type VC-9A, VG-98, VG-11A, VG-115 75E002 VC-12A, VG-128, VG-13A, VC-138 ) VG-22A, VG-223, VG-24, VG-25 Function VG-33, VG-34 Containment Isolation ' Accuracy: Speciflod N/A

• Demonstrated: N/A i

Locations { ,Areat Reactor Building { Elevation: Flood Levels Elevation: N/A Above Flood 14 vel: N/A e 4 (FF-1)

6 FACILITY: VERM0hi YANKEE DOCKET No. : 50-271 ENCLOSURE 3 ITEM PP NOTES: \\ (1) A long-term operation requirement of 1 year has been assumed. (2) A 40 year qualified life requirement has been assumed unless otherwise noted. (3) Additional information is contained in Documentation Reference (s): (4) An aging evaluation is being performed by Acton Environmental Testing Laborato ry. This information, which is incomplete at the present time, will be provided when it becomes available. (5) A radiological evaluation is being performed by EDE Nuclear. This evaluation, which is incomplete at the present time, will be provided when it becomes available. (6) Evaluation of the component for long-term operability cannot be completed until the component's qualifications have been determined for all environmental parameters. (7) The basis for the entry under specified environment appears questionable and is being - verified. If necessary, this value will be changed when the verification is complete. (8) Qualification documentation is expected from the vendor. When this information is received it will be entered in the tabit. DOCLHENTATION

REFERENCES:

903 Vermont Yankee FSAR Question / Answer 7.7. 1 (PP-2) i l ,}}