ML20077K760

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Forwards Response to 830204 SERs & NRC Re Environ Qualification of safety-related Electrical Equipment.Util Plans to Address Remaining Outstanding Action Items Included
ML20077K760
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 05/20/1983
From: Clayton F
ALABAMA POWER CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8305250285
Download: ML20077K760 (118)


Text

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Melling AMmeo Alabama Power Company 600 North 18th street Post Office Box 2641 Birmingham. AIObama 35291 Telephone 205 ?83-6081 F. L Cleyton, Jr.

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the Southern electic system May 20,1983 Docket Hos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear' Regulatory Commission Washi ngton, D.C. 20555 Attention: M r. S. A. Va rga Joseph M. Farley Nuclear Plant - Units 1 and 2 Fire Protection - 10 CFR 50, Appendix R Gentlemen:

During the week of April 18, 1983, the Farley NRC Project Manager, Mr. E. A. Reeves, discussed the results of the NRC Staff's review of the design description for Alternative Shutdown Capability at Farley Nuclear Plant - Units 1 and 2 with Mr. R. L. George of Alabama Power Company.

This design description was transmitted to the NRC in Alabama Power Company letter dated July 1,1982 and outlines modifications to the Farley Nuclear Plant to satisfy 10 CFR 50, Appendix R, Section III.G.3.

Based on the NRC Staff's review, Mr. E. A. Reeves requested that Alabama Power Company temperature (RCS evaluate adding the reactor coolant system cold leg T cold) indication and source range neutron monitor to the Hot Shutdown Panels for Farley Nuclear Plant - Units 1 and 2.

of RCS T Alabama Power Company has completed an evaluation of th: additions cold indication and source range neutron monitor to the Farley Hot Shutdown Panels. Based on this evaluation, Alabama Power Company has determined that the addition of RCS T col d indication is an approp riate modification. Alabama Power Company ~ has determined that the addition of e source ' range neutron monitor to the Farley Hot Shutdown

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Panel would be a' very expensive modification ($390,000.00) that would l

not contribute to the ' determination of an adequate shutdown margin as defined P rocedu res .

by the Technical Specifications and current Emergency 0perating DRAkC 0 hg  !

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Mr. S. N. Varga . .

May 20, 1983 U.- S. Nuclear Regulatory Commission .Page 2 ,

its environmental qualification to be -in accordance with the Preliminary Farley Emergency Response Capability (ERC) Integrated Implementation Plan and Schedule.

- Section C of the reports provides a response to the NRC letter

-dated April 12, 1983 This section includes a review of the 30-day response to address the NRC clarifications, the identity of the pages of the TER that require proprietary protection along with a reference to

'previously submitted applications for withholding and affidavits for protection of the proprietary information, and a discussion of methods used to identify equipment addressed in 10 CFR 50.49(b)(2). It is the judgement of Alabama Power Company that previous submittals comply with 10 CFR 50.49 (a) .and (b) as described in this section.

If'there are any questions, please advise.

Yours very truly, A

F. .

Claytong J r.

FLCJr/DHJ:lsh-D22 Attachments-cc: Mr. R . A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford e e q<.*m'd  % g --

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JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 1 DOCKET NO. 50-348 ENVIRONMENTAL QUALIFICAi10N REPORT e

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, , JOSEPH M. FARLEY ' NUCLEAR PLANT UNIT 1-ENVIRONMENTAL QUALIFICATION REPORT Table of Contents Section A - 90 Day Submittal

-Section B - 10CFR50.49 Submittal

Section C - Response to NRC April 12, 1983 letter

~ Attachment 1 - Reference List for Westinghouse Justifications for Withholding Proprietary Information

' Atta'c hment 2 - Documentation Previously Considered Proprietary

- Attachment 3 - Qualified Equipment Master List 1

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SECTION A 90-CAY SUBMITTAL In response to the NRC's Safety Evaluation Report (SER) for the environmental qualification of safety-related electrical equipment, dated February 4,1983, Alabama Power Company provides this section of the report regarding the review of environmt ntal qualification of Class 1E electrical equipment for Farley Nuclear Plant (FNP) Unit 1. The subjects covered by this section include plans to resolve the outstanding items in Alabama Power Company's response dated March 14,1983, (30-day response to the SER) and information regarding proprietary portions of the Technical Evaluation Report (TER). The scope of this review ensures that equipment necessary to protect the public health and safety is capable of performing its intended function when subjected to a harsh environment.

Alabama Power Company's letter of March 14, 1983 stated that water-tight fittings were being installed on the Victoreen radiation detectors. Installation of these fittings has been completed and Alabama Power Company now considers the Victoreen radiation detectors fully qualified.

The qualification reports for the Target Rock solenoid valves used on the reactor head vent system are currently under development by Westinghouse with a scheduled completion of May 1983. Alabama Power Company installed these solenoid valves in order to provide the state-of-the-art coincident with the implementation dates required by NUREG-0737. Alabama Power Company will review the reports when issued to ensure that the solenoid valves are qualified to the specific Farley Nuclear Plant accident environment. These solenoid valves are not considered within the scope of 10 CFR 50.49 since, as stated in Alabama Pour Company letter of June 23, 1982, such equipment is addressed by the TMI Action Plan and is not essential to achieve a safe shutdown condition.

Additionally, the reactor head vent system is de-energized and can not be placed into operation without the approval of the NRC as specified by NUREG-0737, II.B.1. There is no known environmentally caused failure mode of these de-energized solenoid valves that could lead to the spurious or inadvertant operation of the reactor head vent system. The schedule for the full environmental qualification of these solenoid valves therefore does not impair the safe shutdown capability of Farley Nuclear Plant.

All vendors have responded to Alabama Power Company's request for providing justifications for withholding specific TER information from public disclosure. Westinghouse has reviewed the appropriate sections of the TER and has identified information that still requires protection from public disclosure. Applications for withholding and affidavits for protection of the proprietary information were submitted by Westinghouse to the NRC in accordance with 10 CFR 2.790(b) when the proprietary documents were originally submitted. The pages of the TER .that Westinghouse considers proprietary are Item No.16, pages 51, j, Item No.18, pages 5b,

c, d, e, f,_g, h, i, j, Item No. 21, pages Sa, d, e, g, i, j, k, and Item l

Section I A=

~ Page 2 No.L27, page 5f. . Attachment 1 provides a list of the applicable

- Westinghouse test' reports and associated Westinghouse transmittal letter
numbers and dates of. issue.to facilitate the retrieval of justifications for withholding. . BIW Cable Systems, General Electric, Okonite, Limitorque,

- Transamerica - Delaval, Joy Manufacturing and Automatic. Switch Company

. documents referenced in the TER are no longer considered proprietary. This completes the review of proprietary information contained .in the TER's as requested by Safety Evaluation Report and the NRC letter. dated April 12, 1983.

Equipment items in NRC Category IV " Documentation Not Made Available",

include Boston Insulated Wire and Barton Transmitters. Boston Insulated .

Wire'and Cable Company has reviewed the applicable portions of the TER and t has determined that their test report and letter of clarification no longer

! require proprietary protection. The Boston Insulated Wire and Cable Company Test Report 73E062 and letter of clarification, dated August 21, 1981, which addresses their Test Report- 73E062, are included as Attachment 2 of this report.

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SECTION B 10 CFR 50.49 SUBMITTAL In response to the NRC's request in 10 CFR 50.49, " Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants", Alabama Power Conpany provides this section of the report regarding the review of environmental qualification of electrical equipment inportant to safety within the scope of 10 CFR 50.49.

Attachment 3 of this report provides a Master List of all electrical equipment important to safety within the scope of 10 CFR 50.49 (b)(1) and (b)(2). This Master List identifies the system, plant ID number, generic name, manufacturer, model and location of each equipment item. All equipment identified in the Master List is environmenally qualified and, therefore, a schedule to upgrade the qualification of electrical equipment within the scope of paragraphs (b)(1) and (b)(2) of 10 CFR 50.49 is not necessary.

In accordance with Generic Letter 82-33, Alabama Power Company provided the NRC, by letter dated April 15, 1983, the Preliminary Farley Emergency Response Capability (ERC) Integrated Implementation Plan and Schedule for the installation of an integrated system for the enhancement

.of the existing and adequate ERC at FNP. This integrated system addresses Supplement 1 to NUREG-0737, whose basic provisions include Regulatory Guide 1.97. The schedule for the installation of this integrated system, including Regulatory Guide 1.97, is plant-specific and provides for prompt implementation while optimizing the use of utility and NRC resourceL R.G.1.97 includes provisions to upgrade the envi ronmental qualification of accident monitoring instrumentation. The provisions of R.G. 1.97 are addressed in the integrated implementation schedule for the ERC system.

Alabama Power Company will provide environmentally qualified accident monitoring equipment (Regulatory Guide 1.97) to satisfy 10 CFR 50.49(b)(3) in accordance with the Preliminary Farley ERC Integrated Implementation Schedule. Consequently, an exemption is requested, pursuant to 10 CFR 50.12, from the requirements of 10 CFR 50.49(g) to allow the schedule for identifying accident monitoring equipment (Regulatory Guide 1.97) as described in 10 CFR 50.49(b)(3) and upgrading its environmental qualification to be in accordance with the Preliminary Farley ERC Integrated Implementation Plan and Schedule in Alabama Power Company letter dated April 15, 1983.

The identity of equipment at FNP within the scope of 10 CFR 50.49(b)(1) and (b)(2) and its qualification is documented in previous

' Alabama Power Company IEB 79-01B responses, Appendices 1 and 2 In addition, equipment outside the scope of 10 CFR 50.49 has been qualified to satisfy the TM1 Action Plan requirements of NUREG-0737. The identity of this TMI Action Plan equipment and its qualification is documented in IEB 79-01B Response - Appendix 3, TMI Action Plan Equipment, transmitted in Alabama Power' Company: letter dated June 23, 1982 The equipment identified in Appendix.3, not previously addressed in Appendices 1 and 2, is not essential to achieve a safe shutdown condition and is not considered within

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Section B Page 2 the scope of 10 CFR 50.49. The qualified status of the TM1 Action Plan equipment, as with all electrical equipment important to safety, will be maintained environnentally qualified in accordance with the FNP L ' Environmental Qualification Administrative Program discussed in Section C of this report, i

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SECTION C RESPONSE TO NRC APRIL 12. 1983 LETTER I

i In response to the NRC's Safety Evaluation clarification letter dated April 12,1983, Alabama Power Conpany provides this section of the , report

' regarding the review of environmental qualification of Class 1E electrical equipment- for Farley Nuclear Plant (FNP) Unit 1. . .The subjects covered by

, -this section-include a review of. the Alabama Power Company letter dated 1 March 14,1983, (30-day response to the SER); a review of information in

the Technical. Evaluation Report (TER) claimed to be proprietary; a review of the programs and scope of equipment addressed by previous environmental qualification submittals for compliance with paragraphs (a) and (b) of 10 CFR 50.49; and a discussion of methods used to identify the equipment covered by paragraph 10 CFR 50.49 (b)(2). The scope of this review ensures that equipment necessary to protect the public health and safety is capable

. of performing its intended function when subjected to a harsh environment.

i As' stated in the letter dated March 14, 1983, it is the judgement of Alabama Power Company that all equipment, which includes I.B, II.A, and IV, i required to achieve a safe shutdown condition at FNP is environmentally qualified and Justifications for Continued Operation (JCO) for equipment  :

! items in these NRC categories are not necessary. Equipment items in NRC l

Category IV, " Documentation Not Made Available", are discussed in Section A of this report.

i All vendors have responded to Alabama Power Company's request for

[ providing justifications for withholding specific TER information from 4 . public disclosure. Information requiring and not requiring proprietary I' protection is discussed in Section A of this report.

E ' Subsequent to its publication in the Federal Register on January 21, i 1983, Alabama Power Conpany reviewed the provisions of 10 CFR 50.49 to t determine differences from the original licensing documents, IEB 79-01B and

, NUREG-0588. With regards to paragraph (a) of 10 CFR 50.49, Alabama Power i L Conpany is implementing an Environmental Qualification Administrative

! Program for FNP to maintain the qualification of safety-related electrical l- equipment required to perform its intended function when exposed to a harsh l environment. This program includes provisions for procurement that provides for-the replacement of electrical equipment important to safety l and TMI Action Plan equipment in accordance with 10 CFR 50.49.

Additionally, this program provides for design control, procurement control, storeroom contrei, preventive maintenance, environmental qualification surveillance and document control. This program addresses 11n-service degradation through preventive maintenance / surveillance with h equipment and component. refurbishment and/or replacement based on known

( susceptibility to aging degradation, the results of inspections, and 1 manufacturer's recommendations._ This program will maintain the continued

!. qualified status of equipment presently installed and the qualification of L  : equipment associated with any future modifications. Alabama Power Company will review Regulatory Guide l.89, Rev.1 upon its issuance and will l'

consider its guidance related to further program modificatons. This

_ . program, which ensures compliance with 10 CFR 50.49, will be implemented by i

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Section C ,

. Page'2

' the end' of the Unit 1 fifth refueling outage currently scheduled for the

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second quarter of 1984 In the opinion of Alabama Power Company, the FNP Environmental Qualification Administration Program and the methodology by .

which it was developed complies with 10 CFR 50.49(a).

- Additionally, Alabama Power Company has reviewed the scope of equipment' addressed in the previous FNP responses to IEB 79-01B and has

, determined that this scope of equipment satisfies the provisions of

. paragraphs .(b)(1) and (b)(2) of,10 CFR 50.49. The' establishment of new

qualification programs to address the equipment within the scope of paragraphs'(b)(1) and (b)(2) of 10 CFR 50.49 is not necessary.

I,

. Accident-monitoring instrumentation described in paragraph (b)(3) of

. 10 CFR' 50.49 will be identified in accordance with the Preliminary Farley l' ERC Integrated Implementation Plan and Schedule submitted in Alabama Power Company letter dated April '15,1983 An exemption regarding the identity i- of' accident monitoring equipment and its upgrading from the schedule l' provided in paragraph (g) of 10 CFR 50.49 has been requested with specificity in Section B of this report.

l A Master List of safety-related and nonsafety-related equipment within the scope of paragraphs _ (b)(1) and (b)(2) of 10 CFR 50.49 is presented in

Attachment 3 of this report. The Master List for Farley Nuclear Plant -

- Unit 1-was' developed by a systematic review of design and as-built

'; '_ documentation, the FSAR, Technical Specifications and Emergency Operating Procedures to determine the systems required to perform a safety-related function. The definition of safety-related equipment and its intended function used in developing the Master List is consistent with paragraph

, (b)(1) of 10 CFR 50.49. The review criteria and the methodology resulted l in a Master. List that includes safety-related and nonsafety-related equipment whose environmentally caused failure could unacceptably impair the intended function of safety-related equipment.

The review criteria and methodology utilized to develop the Master 4

List for Farley Nuclear Plant Unit l' are as follows:
1. .This review determined the systems and components required to perform ~a safety-related function. These components were included in the Master List.

2.. The control circuitry of components identified in Item 1 above was reviewed for connections (interlocks) to other safety-related and nonsafety-related components. If spurious or inadvertent operation due to environmentally induced failures 'of the connected i: components in the harsh environment could adversely' affect the completion .of a safety. function, the. connected (interlocks) safety-related or nonsafety-related components were included in the. Master List.-

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Section C _

Page 3 3.- The instrumentation circuitry of conponents identified in Item 1 above was' reviewed for connection to other safety-related and nonsafety-related components. If spurious or inadvertent operation-due to environmentally induced f ailures of the connected components in the harsh environment could cause erroneous indication of the status of safety-related components, the connected safety-related or nonsafety-related components were included in the Master List.

4. For the couponents identified in Item 1 above, the power circuitry inside the harsh environment was reviewed. If environmentally induced failures could result in a loss of power to components required to complete a safety-related function, the safety-related or nonsafety-related power circuitry components were included in the Master List. There are no connected safety-related/nonsafety-related power circuits in the harsh environment.

The Master List of Attachment 3 developed from this review criteria and methodology identifier safety-related equipment that is relied upon to remain functional during and following design basis events and nonsafety-related equipment whose environmentally caused failure could unacceptably impair the intended function of safety-related equipment. In the opinion of Alabama Power Conpany, the equipment identified in the Master List complies with paragraphs (b)(1) and (b)(2) of 10 CFR 50.49.

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jl ATTACHMENT-1  ;

Reference List; for Westinghouse Justifications for Withholding l

. Proprietary Information i

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4 Wdstinghouse+ Test Reports Westinghouse Letter No. Issue a

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7,WCAP-7820 Suppl. 1 ~, E-SL-336 05/31/72

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2, NS-RS-075 11/02/73

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2) WCAP- 7709L U 'E-SL-042 07/14/71 WCAP-7709L Suppl'.,1 E-SL-334 03/23/72

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e ATTACHMENT 2 Enclosed are two documents' which were ~previously not made available to the NRC for proprietary. reasons. .These documents are: (1) Boston Insulated Wire and Cable Company's Test Report 73E062, and (2) Boston

' Insulated Wire and Cable Company's letter of clarification, dated August

.21, 1981, which concerns their Test Report 73E062 These documents are no longer considered proprietary by Boston Insulated Wire and Cable Company.

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  • 16171 2 5 5-210 2 ve6t = 094-540 September 7, 1973 Mr. M. Malcom, Project Manager Bechtel Power Corporation P.O.! Box 607 Gaithersburg Maryland 20760

Subject:

P.O. #FNP-371 Instrument Cable Joseph M. Parley Nuclear Plant Prototype Test Program BIW Orders #B040, B041 B052. B053

Dear Mr. Malcom:

Please find enclosed the prototype test data for the subject order.

The data was obtained in accordance with Specification SS-1102-101, Rev. 1, and the test program outlined in our letter of April 13, 1973 We hope that the results of this program will be useful in your evalua-

.? % . .x,1; ion of the instrument cable.

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9 7507 03 U-TITLE: Prototype Test Program Results JOB: JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 ALABAMA POWER COMPANY MFR. P.O. FNP-371

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.l' f- Page 1 of 8 CUSTOMER: Bechtel Corp. Lab Test # 73E062

. (Parley Nuclear Plant)

BIW Job # B040, B041, Customer P.O. # F.N.P. 371 B052. B053 Customer Item # YO1 BIW P/N 9537-R-002 (LSS 1893A)

Spec. # SS-1102-101 Prototype test report per letter sent to Mr. M. Malcolm of Bechtel Co.

by J. Learn of Boston Insulated Wire on April 13, 1973 (1) Para. S.2.1 Radiation Resistance Test Conditioning: (a) Semples air oven aged for 168 hrs. 0 121 C.

(b) Aged agmples irradiated to a total dose of  ;

2 x 100 rada. (See attached radiation certificate -- Attachment I.)

Tests Spec. Para. Results High Voltage (ac) 8.3 1.la pass 4 KV ac for 5 min.

Insulation 8.3 1.1b 4.5 x 103 Mesa &

Resistance Continuity 8.3 1.2 pass Tensile Strength 8.3.2.1 1030 psi (0.T. )

Elongation 8.3.2.1) 70% (O.E.)

after conditioning Tensile Strength 8.3. 2.2a;RHTE . POWER CORf7. 9%. (O.T. ) .

Elongation 8._3 2.2a N"$ d$N/)E;5.8% (0.E.) ~

, 168 hrs.

e 121oC SE P 121973 8.32.2bf Nf.5%(0.T.)

Tensile Strength

Elongation 8.3.2.2b f ** N ~ "d3 % (0.E.)

, 42 hrs.

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j Tests Spec. Para. Results

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Gravimetric Water 8.3 2 3b 129 mg/ine Absorption Electrical Water 8.3 2 3a Dielectric Constant - 3 17 Absorption (E.M. 60) "

Increase in Capacitance

" (1-14 day) = 2 5T

" (7-14 day) - 2 9%

" Stability Factor (14 day) =03 (2) Para. 8.2.2 Plame Resistance Test (a)

  • Test Spec. Paragraph conditioning Result Vertical Flame 8.2.2.1 -

pass (IPCEA S-19-81) para. 6.19.6 Vertical Flame 8.2.2.1 168 hrs. 0 121 0C pass l (IPCEA S-19-81) para. 6.19.6  :

(b) The results of the vertical flame tray tests which were performed in accordance with paragraph 8.2.2.2 using a burlap igniter flame source are included as Attachments II, III and IV of this report.

BECHTEL POWER CO;;P.

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Sample was aged 168 hrs. e 1210C.

i Conditioning: (a)

(b) Aged agsple was irradiated to a dose of 2 x 100 rada. (See Attachment I for i radiation certificate.)

i The result of the autoclave test cycle as specified in para-j graph 8.2.3.3 is included as Attachment V. The insulation

' resistance measurements required by paragraph 8.2.3.5 are i also given in this attachment.

s l In accordance with paragraph 8.2.3.6, the physical and <

j electrical tests specified in paragraphs 8.3 1 and 8.3.2 l j were performed on the sample upon its removal from the  !

l i autoclave.

The results of the tests performed on this irradiated and autoclaved sample are given below. ,

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l l Tests Spec. Paragraph Results i

! High Voltage (ac) 8.3 1.la pass 4 KV ac for 5 min.

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Insulation 8.3 1.1b 2.8 x 104 Megn N j . Resistance Continuity 8.3 1.2 pass l

4 l Tensile Strength 8.3 2.1 920 psi (o.T.) -- -

Elongation 8.3 2.1) 80% (O.E.)

after autoclave and conditioning Tensile Strength 8.3 2.2a 52 3% (0.T. ) 7 , ,

l 168 hrs. 0 121 0C - - - -

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37.6% (0.E.) ;

l Elongation _

f Tensile Strength 8.3 2.2b 74% (o.T.) l l 42 hrs.Ggopsi l and 127 C Elongation 68.8% (0.E. ) l l Oravinetric Water 8.3 2.3b 15 0 mes/ine

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Electrical Water 8.3 2 3a Dielectric Constant - 3 16 Absorption (E.M. 60) Increase in Capacitance l BECHTtL POWER CORP. (1-14 day) = 2.6%

(7-14 day) = 1.8%

5.hk [hp Stability factor (14 day) = 0.2 l

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,T.fco'n'ditionst[.~ ,. Irradiation pertotmed .in air a.t.'a'mbient temperature

" .c

.,;f9;$f,...

-i .i..' . h. n.? ,

,...(70*F) i-and slight negative :.,pressure

( l/2" water).' . ,,

C'

-7.1 ,.n..z.~ N;.c ..::

.~.,.

.-Max.  ; . Temp.' of. Sample During Irradiation: // o* '/~ - .

  • p';~gy . . a - m . =, .. ; h. .

. i f 3g 7,Dosim'etry Sy. stein:,. Dosimetry,s as Iterformed using,,a Victo.reeri Model, w ,

.d-f.7 c sc ?. , y: ' ' * . ,555 Integrating Do.se. Rate Meter,.an,dfProb.e; :The .

. M ei,j). 9 *g,. ,.,....,.g unit was calibaated on January'15, 1971 by: the -

3 r '

Victoreen Instrumerrt Company, using. Cobalt-60 .

My c* .q - BC .a C'} . < ...< , - . 2 ~ .-(' ' #

and Cesium-137 sources.whose c'alibrari'ons' are . ~

,..J:;.

.w.

~

- Standards.-

tra'ceable .toA the U.S. National Bureau of copy of t,he calibration. certificate s.

./ O . . .'u .4 - ' -

~

~

~

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pg.m. ,s .'

a. .. . . .' ., .

..r is available. '

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.":.",... ,i w 0ther: ; Samples were rotated and turned during exposure to achieve W i..e.k. . s ~ ' a more uniform dose distribu~ .

.. \

tion. *.

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BECHTEL POWER CORP.

'l-\'I',2 Post-Irradiation Defects Observed:

.'MM .. < . . ,

D 2 C 2 )l T / F .

.:. y ,

' SEP 121973

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e . >. .,.

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..> JOB No,7597 ;.0. 3/2_0

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'TThis is t'o certify'that the subject product was radiation processed

~ -

.i . , : in the aforementioned manner.

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w. ., - -

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p.;..

- George . Dietz ,; '

i <G ,RD:mg .... .

, Manager, Radiation Services .

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r. : '

4  ;

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- a. - leomeicfix Inc.

  • 25 Eastmans Rd., Hanover. New Jersey Tele 6 hone (201) 887-4700 "

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  • Ronoit Stroct. e.
theeng As Mont. St. Hilairn.Oimbec, CQndo Telophorp a%at O,tese.ee f.It* Mees.m ,C.s h .

(514) 4671211 , 19- .

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Pcgo 5 of 8 I .30STON INSULATED WIRE & CABLE CO, j ATTACHMENT II

', . General Data Sheet TEST NO.:

PAR:

TEST:

Flame Test Inquiry #SS-1102-101 SPEC:

8.2.2.2 73P027A 0 6/18/73 CONDRIONING: Aged 168 hrs. e 121 0 TESTED BY:

PART. TYPE NO.:

W. Barnes LSS-1893A LAB. SUP. CHECK:

R. Oppenheim CUSTOMER: Farley (Alabama Power)

'y 2,*

TEST mEquinEuENTS: According to above spec. ,

Construction: 2X #16 AWG OR-853A min. wall .027, IX T-92, 2 lap. Wrap #18 AWG solid drain wire; IX T-33 alum.-Mylar, 2 lap, alum. down, OR-547-J min. wall

.o54 Burlap site 24" x 24" folded Sample #1 Soak time 5 m:Ln.

Unt:L1 159 s; rams rquained Drain time t Ignition t ime 35 asc.

Burlap burn time 16 nin. 45 sec.

6 m:Ln.

Continues to burm

  • Cable dams.ge 1 2 :Lnches Inaulatior, failure
L. No e-lectric al fail'are it.
3. t

)[,

5 w n N 4;,

N N of N

n. *

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4.

N 10.

" BECHTEL POWM Corf.

@jf' 39TP5!IrF

,,1 1 r "I t' % ' 'l Wt I

.n, atr121i 73 3

JOB No.7597 .03/2g i /

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Pcga 6 of 8

' " ATTACHMENT III

,...s.-

(~ ISTON INSULATED CIRE & CABLE C0.

' - - General Data Sheet 3

'~ PAR: TEST NO.:

T'15' FlameTestInouiry#S815:02-101 SP 8.2.2.2 73P027B

^ '

0 6/18/73 j Aged 168 hrs e 121 C PART. TYPE NO.:

TESTED g g cunoMER' Parley (Alabama Power) *g suP pnhieim il OUT []

i TEST REQUIREMENTS:

According to above spec. ,

__.v--_ l TEMP.: ' Rfi:

! /

i i

Sample #2 Burlap size 24" x 24" folded Sosik time 5 as.n.

Dratin time Unt$.1 158 grams remained Isttitiontjime 20 slec.

Burlap burning ti me 28 nin. 36 sec.

. Coritinues to burn 0 sco.

I Cable damage 14 f.nches ,

Inslulatiod failure

1. No electric al failure 0 . 8 min. O see. -- one cirettit oniv *
1. No electrioni failure L.

6.

I g w a w R H N i

3 ,

N N f ,_

R o .

1Ci. 19 min. 40 sec. -- one circuit anlye --

l

[

BECHTEL POWER WP

'One conductor -- shield fa ilure rg g g gg7,gj g; mu ->e o e qir l '

.ll tf 1413 / 3

a. p 1

Jos No.7497 03/20 I

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C . . ,: Paga 7 of 8

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!.J0STON INSULATED WIPE & CABLE C0. ATTACHMENT IV General Data Sheet SPEC. PAR: TEST N O.:

Flame Test Instuiry #SS-1102-101 8.2.2.2 73 P027C DATE'-

CONDITIONING: Aged 168 hrs. e 121*C 6/19/73 l TESTEQ JY: }

PART. TYPE NO.: w. Barnes <

LSS-1893A LAB. SUP. CHECK:

CU5 TOWER:

Parley (Alabama Power) R Oppenheim Tl CUT A TEST REQUIREMENTS: _ f_ * ,

Aeoording to above speo. . m. - . . -

TEMPl ' kH:

I Sampis,#3 Bu: Flap site 24" x 24" Soak time 7m Ln.

Drain timet Unt L1 165 grams remained Ignition t,ime 25 mee.

Buhlap buzning time 22 inin. 5 neo.

Continues to burr 0 sea.

Cable damatge 15 :Lnches _

Inkulatiori failure

L. 10 siin. 45 see. 10 min , 56 sec .*
12. No tilectric al failure 3, e a i n
L * " " o e, o,. - ~ . . ... __ ___

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10.

  • Two conductors -- shield (9 mdonductor -- conduo bor fai' Lure)

P g3 8 of 8'

  • ATTACEMElff V
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BOSTON INSULATED WIRE a CABLE CO.

General Data Sheet Test No.: 73E062B CUSTOMER: Alabama Power Company)

(Farley Nuclear Plant July 25, 1973 Date:

Spect Inquiry #SS-1102-101 Post-Incident Environment Test Para. 8.2.3 The electrical circuit specified in para. 8.2.3 2 was maintained for the duration of the test on this irradiated sample. No insulation failure took place.

The ehemical spray, consisting of a 10.000 nun mali +4 aa_ e f boric scid buffered with NaOH to give a Ph factor of 10.5. was also provided for.the test duration. The test cycle and the I.R.

readings taken at the required intervals as specified in para.

8.2.3 5 are given in Table 1 below.

TABI2 1 I.R. in Meg .r./Mi Temperature Pressure Cond. #1 Cond. #2 Time l 80'F 0 2 x 10 5 1.8 x 105 Initial Reading ,

300 0 F 80 psi i 7 x 10 2 8 x 10 22 1 hr.

7 x 10 2 8 x 10 2 2 hr.

7 x 10 2 8 x 10 3 hr.

5 x 10 6 x 102 4 hr.

Ego'F 16" pai 5xloj 7 x 1022 1 ,,7 5 x 10 7 x 10 2 2 days

" " 4 x 1033 7 x 1o 2 3 ,,,,

" " 1 x 10 2 7 x 10 4 days

" " 4 x 10 3 7 x 10 1 5 days l " "

1.7 x 10 3 e(go4 A 6 days 7 x 10 *(3 x 10 A) 7 days

  • Readings taken with Simpson meter.BECHTEL POWER CORP.

M H

M r'a41313 YI JOB NO.7592 :03/,20, ,

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B 5T N IN S U LATE D WIRE & CABLE CD.

55 B AY STR EET

  • WOSTO N . M ASS AC H UE ETTE O2 5 2 5 * (517) 255-2l02 L c August 21, 1981 E

~ h!=ppyp t u du

(

NJG2 51981 * $

Bechtel Power Corporation JOB 7597 03l20 15740 Shady Grove Road \ BECHTEL 7 Gaithersburg, Maryland 208.77 , .7 c-Attention: A. A. Vizzi Project Engineer Joseph M. Farley Nuclear Plant Units 1 and 2 Environmental Qualification Purchase Order FNP-371 Bechtel File E-91 V-3967 Gentlemen:

In reference to your-letter of August 14,1981, .we are enclosing Appendix A ti Figure I which apply to the cables with ethylene propylene rubber insulation. The slope of Figure I was derived from tests on EPR insulation as described in Appendix A. A line drawn through the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> /121*C point in Figure I with the same slope (slope represents rate of aging as described in Appendix A) shows a projected life of 40 years at 49'C. Consequently, aging for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121*C represents 40 years at 49*C for the ethylene propylene rubber insulation.

Please contact us if you have any questions.

Very truly yours, g a i u.a_:

cMf. ,

id ri BIW CABLE SYSTEMS, INC.

) -.? $y j.;f g l-og 7 M diY_

3t-- ( -

, ggf- 1 . R. Learn Nl Applications Engineer

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APPENDIX A

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H LONG-TERM PHYSICAL AGING PROPERIIES - 40 YEAR LIFE Long-term physical aging tests conducted on cables indicate a life in excess of 40 years .at 90c for BIW's ethylene propy-lene rubber insulation. This is shown by the Arrhenius plot in Figure I for cables aged at 200c,180c,1500,136c and 121c.

Accelerated agings were initially made at the five test temper-atures on specimens taken from slabs. The slope of the line determined by data points was found to be the same for differ-ent end points and can be taken to - represent the rate of change by the materials to any defined end condition. By using this slope to determine a line intersecting the 40 year life -- 90c temperature point as shown in Figure I -- we can determine <

what the expected cable life must be at any aging temperature  :

to represent the equivalent of 40 years at 90c, since any point on the line represents the equivalent of 40 years at 90c.

Specimens of BIW cables were removed from the ovens periodical-ly, as shown in Figure I, and subjected to a dielectric proof -

test of,2200 volts (twice rated voltage + 1000). After success-fully passing the test, the samples were returned to the oven for continued aging. As the data clearly' indicate, the cables withstand the proof test voltage when aged in excess of that representing 40. year service. The specimens were subjected to bending after aging in excess of the 40 year conditioning.

As Figure I indicates, cable samples at 200c,180c,150c,136c and 121c have surpassed the 40 year requirement. When bent around.a 40X diameter mandrel, the ethylene propylene rubber insulation was undamaged and still withstood the voltage proof test. Passing points above the 40 year-90c life line indicate i margin of performance.  ;

Figure I is offered for acceptance as evidence of 40 year life at 90c in lieu of additional testing or data. These tests were .

conducted in accordance with IEEE 383-1974, para. 2 3.'2.

4 g P 1

- IlECBVED -

(E A'JG2 51981 > [8 J03 7597 03[20

\ BECHTEL- G V 6/3-Y/TF I

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. ATTACHMENT.3

[QUALIFIEDEQUIPMENTITEMS This Master List includes the system, plant ID numbers, generic name,

~

manufacturer, model and location of each qualified equipment item. These

~

are safety-related, Class IE electrical equipment items, which are required

- to achieved a safe shutdown condition at FNP.

4 1

- D-22.

f f + -n y w .wg g q- p-w--- , w-n

MASTER LIST Section C.2.1 l Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS lE ELECTRICAL EQUlPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: REACTOR COOLANT INSTRUMENTATION B-13 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. E EV.

N1B13TE412B RTD Rosemount 176KF CTMP 174'-O"

[

N1B13TE412D RTD Rosemount _176KF CM 124'-0" N1B13TE422B RTD Rosemount 176KF CTMT 124'-0" N1B13TE422D RTD Rosemount 176KF CTMT 124'-0" NIB 13TE432B RTD Rosemount 176KF CTMT 124'-0" NIB 13TE432D RTD Roseraount 176KF CTMT 124'-0" General Q1T52B012 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B028 Penetration Electric 100 Series CTMr 143'-0" General Q1T52B030 Penetration Electric 100 Series CTMT 143'-0" 11TB001 Terminal Block States Co. Tyne ZWM CTMT ~>115 ' .

11TB002 Teminal Block States Co. Tvoe ZWM CINT >115' 21TB003 Terminal Block States Co. Type ZWM CTMT ~7115' 21TB004 Terminal Block States Co. Tvoe ZWM CTMT >115' _

31TB001 Terminal Block States Co. Tyne ZWM CTKr >115 '

31TB002 Terminal Block States Co. Tvne 2WM CTMT >115' Boston IVIV5002B.D Instr. Cables Inn. Wire None CTMT .7115' Boston IV2V5002B.D Instr. Cables Inn. Wire None CTMT P115' Boston IV3V5002B.D Instr. Cables Tne. Utre Mnne cTMT >11s' GPD 1374 Rev.6/81 l

MASTER LIST SGetion C.2.2 Sheet 1 .

Joseph M. Farley Nuclear Plant Unit 1 (CLASSlE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

REACTOR COOLANT SYSTEM - STEAM GENERATOR B-21 SYSTEM:

COMPONENTS GENERIC NAME MANUF ACTURER MODEL BLDG. ELEV.

PLANT ID NUMBER N1B21PT402 Press. Transmitter Barton 763 CTMT 129' 1

N1B21PT403 Press. Transmitter Barton 763 CTMT 129' _

l N1B21TE410 RTD Rosemount 176KS CTMT 122'-9" N1B21TE413 RTD Rosemount 176KS CTMT 122'-9" N1B21TE420 RTD Rosemount 176KS_ CTMT 122'-9" N1B21TE423 RTD Rosemount 176KS CTMT 122'-9" N1B21TE430 RTD Rosemount 176KS CTMT 122'-9" Rosemount 176KS cTMr 1??'-Q" N1B21TE433 RTD General Penetration Electric 100 Series CTMr 141'-0"  ;

Q1T52B012 General 01T52B030 Penetration Electric 100 Series enrr 141'-n" General Penetration Electric 100 Series CTMT 141'-0" Q1T52B040 11TB001 Terminal Block States Co. Tyne 7WM CTMT >10 '

cntr >115' 11TB003 Terminal Block States Co. Tyne 7 w Type Zw cntr >115 '

11TB004 Terminal Block States Co.

Tyne 7WM cntr >115 '

21TB001 Terminal Bloc'n crates Co.

Terminal Block States co. Tyne zuM cntr >115' 21TB002 Tyne zuM cntr >115' 21TB005 Terminal Block States Co.

Boston Ins. Wire None CTMr #119' IVYV5031B Instr. Cables Boston Inn. Wire Mnne cTMr 7119' IVYV5033B Instr. Cables Boston Inn. Wire None CTMT P119' IV1V5002E.F.C Instr. Cables Boston Inn. Ufra Nnne enrr 7119' IV2V5002E.F.G Instr. Cables I

i GPD.1374 Rev.6/81

MASTER LIST Section C.2.3 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 .

(CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: REACTOR COOLANT SYSTEE.- PRESSURIZER B-31 COMPONEN TS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

Q1B31SV8047 (HV8047) Solenoid Valve ASCO NP831654V CTMT 118'-0" N1B31ZS8047 (HV8047) Limit Switch NAMCO EA-180 CTMT 118'-0"

~

Q1T52B022 Penetration

((re '# **

100 Series CTMT 143' Q1T52B038 Penetration

((ffe N1B31SV8047-B/JB Terminal Block States Co. Type ZWM CTMT >115' Q1B31LT459 Bart n 764 N 132' T mitter Q1B31LT460 T n mitter Barton 764 CTMT 132' QlB31LT461 T mitter Barton 764 CTMT 132' Q1B31PT455 Foxboro E11GM(MCA) CTMT 166'-6" T ter P

Q1B31PT456 Foxboro EllGM(MCA) CTMT 166'-6" T m ter P

Q1B31PT457 Tr i ter Foxboro EllGM(MCA) CTMT 166'-6" 1UBL5078C Control Cable Okonite None CTMT >115' idBQ5021E Control Cable Okonite None CTMT ;P115' Q1T52B012 Penetration *[*f, 100 Series CTMT 143'

"[*f, Q1T52B028 Penetration 100 Series CTMT 143' QlT52B030 Penetration '[,f, 100 Series CTMT 143' Q1752B040 Penetration '[*f, 100 Series CTMT 143' IVYV5031D Instr. Cable None CTMT >115' IV1V5002U Instr. Cable $8* ,

None CTMT 7115' IV2V5002T.U Instr. Cables N'"""* ""*

None CTMT 7115' IV3V5002T U Instr. Cables "," None CTMT 7115' l GPD 1374 flev.8/81

MASTER LIST Section C.2.4 1 Sheet 2 Joseph M. Farley Nuclear Plant Unit (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

FEEDWATER CONTROL SYSTEM C-22 SYSTEM:

COMPON ENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

Mn.Stm.

IVAL5061C Control cable Okonite None Room 2 131' Mn.Stm.

IVBL5034C, D Control Cables Okonite None Room 2 131' Mn.Stm.

Control Cable Okonite None Room '> 131'  !

IVXL5072B Mn.Stm. l IVAL50623 Control Cable Okonite None Room 3 131' (

Mn.Stm.  !

IVBL5035B, D Control Cables Okonite None Room 2 131' Mn.Stm.

IVXL5073A Control Cable Okonite None Room 1 131'  :

764 CTMT 159' Q1C22LT474 Level Transmitter Barton Level Transmitter Barton 764 CTMT 1so' Q1C22LT475 Level Transmitter Barton 764 CTMT 150' Q1C22LT476 Level Transmitter Barton 764 CTMT 159' Q1C22LT484 764 CTMT 1sg' Q1C22LT485 Level Transmitter Barton 764 CTMT 159' Q1C22LT486 Level Transmitter Barton 764 CTMT 159' Q1C22LT494 Level Transmitter Barton 764 CTMr 159' Q1C22LT495 Level Transmitter Barton 159' Q1C22LT496 Level Transmitter Barton J64 CTMT Flow Transmitter Foxboro E13DM CTMr 180' Q1C22FT474 Flow Transmitter Foxboro E13DM CTMT 180' Q1C22FT475 Flow Transmitter Foxboro E13D)t CTMr 180' Q1C22FT484 Flow Transmitter Foxboro E13DM' CNT 180' Q1C22FT485 Flow Transmitter Foxboro E13DM CTMT 180' Q1C22FT494 Flow Transmitter Foxboro E13DM CET 180' Q1C22FT495 General Electric 100 Series CINT 14 3' Q1TS2B010 Penetration General Electric 100 Series CTMT 143' Q1T52B012 Penetration General p.n.eencinn v1.rer<c 100 Series CTMT 143' alts?no?n General 100 Series CTMT 143' 01T528030 Penetration Electric GPD 1374 Rev.6/81

MASTER LIST Section C.2.4 Sheet 3 1

Joseph M. Farley Nuclear Plant Unit (CLASS lE ELECTP.lCAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT C C-22 SYSTEM: FEEDWATER CONTROL SYSTEM COMPONENTS GENEFilC N AME MANUFACTURER MODEL BLDG. ELEV.

PLANT ID NUMBER Boston Instrument Cable Ins. Wire None CTMT > 115' IV1V5002L. M. N Boston Instrument Cable Ins. Wire None CTMT > 115' IV2V5002L. M. N Boston l IV3V5002H, J, K, Instrument Cable Ins. Wire None CTMT > 115' 1 L. M. N Boston Instrument Cable Ins. Wire None CTMT > 115' IV4V5002A. B. C I

i GPD 1374 Rev. 6/81

MASTER LIST Section C.2.5 Jo;eph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SAFEGUARD SYSTEMS. RHR/LESI E-11 SYSTEM:

COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1E11LT3594A Level Transmitter Gems XM-36495 CTMT 116'-0" Q1E11LT3594B Level Transmitter Gems XM-36495 CTMT 116'-0" Q1T52B006 Penetration Electric 100 Series CTMT 143'-0" Q1T52B020 Penetration Electric 200 Series CTMT 143'-0" 1VAIS009F Control Cable Okonite None CTMT '7115' IVBI5008C Control Cable Okonite None CTMT p115' 1

l l

l GPD 1374 Rev.6/81

MASTER LIST Section C.2.6 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: CONTAINMENT COOLING AND PURGE E-12. E-14. P-13 COMPONENTS PLANT ID NUMBER GENERIC NAM E MANUFACTURER MODEL BLDG. ELEV.

l M t r Operated Q1E14V002 (MOV3660) y ,

QlE14V004(MOV3318B) Goe Perated Limitoroue SMB-000 CTMT 116'-0" QlP13ZS3196(HV3196) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P13SV2867B(HV2867) Solenoid Valve ASCO NP831654V - CTMT 129'-0" QlP13ZS2867B(HV2867) Limit Switch NAMCO EA-740 CTMT 129'-0" Q1P13ZS3197(HV3197) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P13 V2866B(HV2866) Solenoid Valve ASCO NP831654V CTMT 129'-0" QlP13ZS2866B(HV2866 ) Limit Switch' NJC0 EA 740 CTMT 129'-0" QlE12SV3999A(HV3999A) Solenoid Valve ASCO NP8316A74E CTMT (105' Q1E12ZS3999A(HV3999A) Limit Switch NAMCO EA-180 CTMT (.105' QlE12SV3999B(HV3999 3) Solenoid Valve ASCO CTMT (105' NP8316A74E QlE12ZS3999B(HV39993) Limit Switch NAMCO EA-180 CTMT (105' QlE12M001A(H001A) CTMT Clr. Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" Q1E12M001B(H001B) CTMT Clr. Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" QlE12M001C(H001C) CTMT Clr. Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" Q1E12M001D(H001D) CTMT Clr. Fan Motor Joy Mfg. Co. Type P CTMT 155'-0"

""*#8 QlT52B005 Penetration Electric 100 Series CTMT 143'-0"

  • ""#8 Q1T52B007 Pen.etratlon Electric 100 Series CTMT 143'-0" Q1T52B019 Penetration Electric 100 Series CTMT 143'-0" Q1T52B002 Penetration 100 Series CTMT 143'-0" Electric Q1T52B006 Penetration 100 Series CTMT 143'-0" Electric QlT52B041 Penetration 100 Series CTMT 143'-0" Electric l QlT52B020 Penetration ""*'" Electric 100 Series CTMT 143'-0" f GPD.1374 Rev. 6/81

MASTER LIST Section C.2.6 1 Sheet 2 Joseph M. Farley Nucl:ar Plant Unit (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

E-12. E-14. P-13 SYSTEM: CONTATNMENT COOT.TNG AND PlfRCE COMPON ENTS PLANT ID NUMBER GEN ERIC NAME MANUFACTURER MODEL BLDG. ELEV.

i Q1P13SV3196-B/JB Terminal Block States Co. Type ZWM CTMT > 115'

"*#* 100 Series CTMT 143' Q1T52B022 ,

Penetration Electric Terminal Block States Co. Type ZWM CTMI > 115 '

Q1P13SV2867B-B/JB Terminal Block States Co. Type ZWM CTMT > 115 '

Q1P13SV3197-5/JB Q1P13SV2866B.B/JB Terminal Block States Co. Type ZWM CTMT >'115' Q1E12SV3999A-A/JB Terminal Block States Co. Type ZWM CTMT <.115' Q1T52B025 Penetration Electric 100 Series CTMT 143' Q1E12SV3999B-B/JB Terminal Block States Co. Type ZWM CTMT ( 115'

"*#81 100 Series CTMT 143' Q1T52B001 Penetration Electric enera1 100 Series CTMT 143' Q1T52B023 Penetration Electric IVAFU-R5Q Power Cable Okonite None CTMT 7 115' IVAFU-RSD Control Cable Okonite None CTMT 7 115' IVAQ5048F Control Cable Okonite None CTMT 7 115' IVXR5005H Control Cable Okonite None CTMT 7115' IVAFU-J4Q Power Cable Okonite None CTMT 7115' _

IVAFU-J4D Control Cable Okonite None CTMT >115' IVAQ5009C Control Cable Okonite None CTMT 7 115' s n ns. None CTMT 7 115' IVYR5066B Instrument Cable IVBL5008C.D K,L Control Cables Okonite None CTMT 7 115' Control Cable Okonite None CTMT  :* 115' IVBQ5010J IVYR5035D Control Cable Okonite Ncne CTMT 7115' IVBL5008X, W Control Cables Okonite None CTMT 7 115' Control Cable Okonite None CTMT 7115' IVBQ5012F IVYR5035F Control Cable Okonite None CTMT 7 115' t 1

Control Cable Okonite None CTMT > 115 '

IVAL5122C GPD 1374 Rev.6/81

MASTER LIST Section C.2.6 i Sheet 1 Joseph M. Farley Nuclear Plant Unit (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

F- 1 ') ; F-1L; p_1 4 SYSTEM: CONTAINMENT COOT _.ING AND PITRnF COMPON ENTS GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

PLANT ID NUMBER  ;

Control Cable Okonite None CTMT 7115' IVAQ5029E IVBL5094C - Control Cable Okonite None CTMT 7 115' IVBQ5029E Control Cable Okonite None CTMI 7 115' IVAED15Q Power Cable Okonite None CTMT 7115' IVAED16Q Power Cable Okonite None CTMT > 115' IVBEE08Q Power Cable Okonite None CTMT 7 115' Power Cable Okonite None CTMT > 115 '

IVBEE16Q l

GPD 1374 Rev.6/81

i MASTER LIST Secti n C.2.7 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

HYDROGEN RECOMBINER SYSTEM E-17 SYSTEM:

COMPONENTS PLANT ID NUMBER GENERIC NAME M ANUF ACTURE R MODEL BLDG. ELEV.

Recombiner Heater Westinghouse Type A CTMT 155'-0" 01E17G001A (K001A) 2 Recombiner Heater Westinghouse Type A CTMT 155'-0" Q1E17G001B- (K001B) 2 General 01T52B001 Penetration Electric 100 Series CTKr 143'-0" 1 General 01T52B023 Penetration Electric 100 Series CTMT 143'-0" General 01T52B024 Penetration Electric 100 Series CTMT 143'-0" General 01T52B042 Penetration Electric 100 series CTMT 143'-0" IVAFALL3T Power Cable Okonite None CTMT 7115' IVBFBRH6T Power Cable Okonite None CTMT  :>115' Boston

,IVXQ5009B,D,F Instrument Cables Ins. Wire None CTMT 7115' Boston IVYQ5017B,D,F Instrument Cables Ins. Wire None CTMT s115' l

I l

GPD.1374 Rev 6/81

MASTER LIST l Section C.2.8 1 Sheet 1 Joseph M. Farley Nuclear Plant Unit l

(CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) l SYSTEM: CONTAINMENT POST LOCA AIR MIXING SYSTEM E-19 i COMPON ENTS

PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

Q1E19M001A (C001A) Mixing Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" Q1E19M001B (C001B) Mixing Fan Motor Joy Mfg. Co. Type P CIMT 155'-0" i~

Q1E19M001C (C0010) Mixing Fan Motor Joy Mfg. Co. Type P CET 155'-0" j CNT Q1E19M001D (C001D) Mixing Fan Motor Joy Mfa. Co. Type P 155'-0" General Q1T52B002 Penetration Electric 100 Series CTMT 143'-0" ;

r General Q1T52B014 Penetration Electric 100 Series cmT 143'-0" 2 General Q1T52B015 Penetration Electric 100 series cmT 1438 0" 4 General

Q1752B017 Penetration Electric 100 serien cmT 1418 0"
- IVAFA-J50 Power Cable Okonita None CNT >11%'

IVAFA-150 Power Cable Okonite None CNT >115'

]

IVAFA-14Q Power Cable Okonite Non'e CNT >115' IVAFA-13Q Power Cable Okonite Non? cmT >115' l

3 i

s i

4

)

4 i

l 1

GPD 1374 Rev.6/81

MASTER LIST Section C.2.9 I

Joseph M Farley Nucle:r Plant Unit i Sheet (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) ruFMTrAT. AMn VnTBMF rnNTRnT3RAFFTV TN TFETTAM E-21 SYSTEM:

1-COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1E21V038A 12" Motor Operated (MOV8808A) Cate Valve Limitoroue SMB-4 CTMT 111'-6" Q1E21V038B 12" Motor Operated Gate Valve Limitoroue SMB-4 CTMT 112'-6" (NOV8808B)

Q1E21V038C 12" Motor Operated Gate Valve Limitoroue SMB-4 CTMT 113'-6" (MOV8808C)

Q1E21SV8871 (HV8871) Solenoid Valve ASCO NP831654V. cTMT 129'-0" Q1E212S8871 Limit Switch NAMCO EA-180 cTMT 179'-0" (HV8871)

Q1E21V249A 3" Motor Operated Cate Valve Limitornu. KMn-00 cTwr 19s' (MOV8112_)

NIE21ZS8149A Limit Switch NAMCO FA-1R0 cTMT 111' n" (HV8149A)

Q1E21SV8149AB Solenoid Valve ASCO .206-381-6EF. cTMT 111' n" (HV8149A)

NIE21ZS8149B (HV8149B) Limit Switch NAMCO EA-180 CTMT 111'-0" Q1E21SV8149BB (HV8149B) Solenoid Valve ASCO 206-381-6RF cTur 111' 0" NIE21ZS8149C (HV8149C) Limit Switch NAMCO EA-180 CTMT 111'-0" Q1E21SV8149CB ..

(HV8149C) Solenoid Valve ASCO 206-381-6RF CTMT 111'-0" General Penetration Electrie 100 serien cTwr 149'-0" Q1T52B002 General Penetration Electrie 100 serf.. cTMT 1 tN n" 01T52B016 General Penetration Electrie 100 s rt.. cTMT i zw n" 01T52B006 General Penetration riecerie 100 s.rt.. cTMT 1 tw n" 01TS2B038 General Q1T52B019 Penetration Electric 100 Series CTMT 143'-0" NIE21SV8871-A/JB Terminal Block States Co. Type ZWM CTMT > 1168 0" Q1E212S8808AB Limit Switch NAMCO EA-180 CTMT 111'-6" Q1E21SZ8808BB Limit Switch NAMCO EA-180 CTMT 112'-6" Q1E21ZS8808CB Limit Switch NAMCO EA-180 :TMr 113'-6" General Q1T52B014 Penetration Electric 100 Series :TMT 143'-0" Terminal Block States Co. Tvee ZWM  :~n4T P 116_'_- 0" NIE21SV8149AA-A/JB NIE21SV8149BA-A/JB Terminal Eleck Stat.m cn_ Tvn. 71JM ETwr 311A' n" GPD 1374 Rev.6/S1

4 MASTER LIST

' Section C.2.9 1 Sheet 2 Joseph M. Farltf Nuclear Pbsit Unit (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) cMFMTcAT. AND VOTAME CON 1701dSAFETY IN.7ECTION E-21 SYSTEM:

~

COMPON ENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

116'-0"

/ NIE21SV8149CA-A/JB Terminal Block States Co. Type Ziaf CTMT & above IVAFU-Z2Q Power Cable Okonite None CTMT > 115' IVAFU-22D G Control Cables Okonite None CDfr 7 115' IVAQ5023E Control Cable Okonite None CTMT 7 115' IVXKA163B Control Cable Okonite None CTMT >115' IVBFV-S2Q Power Cable Okonite None CTMT > 115' IVBFV-S2D,G Control Cables Okonite None CTMT > 115 '

IVBQ5024C Control Cable Okonite None CTMT > 115 '

IVYKA163B Control Cable Okonite None CDIT 7 115' IVAFU-230 Power Cable Okonite None CTMT 7 115' IVAFU-23D.C Control Cables Okonite None CTMT 7 115' IVAQ5024E Control Cable Okonite None CTKr 7 115' r

IVXA163D Control Cable Okonite None CTMT 7 115' IVAL5049C Control Cable . Okonite None CTMr 7 115' IVA05022H Control Cable Okonite None CTMT > 115' IVAFU-T40 Power Cable Okonite None CTMT 7115' IVAFU-T4D Control Cable Okonite None CTMr > 115' IVA0501BE Control Cable Okonite None CTMr 7 115' 1 VAL 5042F Control Cable Okonite None CTMT 7115' IVAL5042G Control Cable Okonite None CTgr 7 115' Control Ceble Okonite None CTgr 7 115' E AQ5022F f

Control Cable Okonite None CTKr 7 115' IVAL5043F Control Cable Okonite None CTur 7 115' i IVAL5043G Pantent'Pahim nkantto Mana P1Vr Y 115' l 1UAntnMP l

IVAL5044F Control Cable Okonite Non, Cntt 7 115' l

i GPD 1374 Rev. W81 s.

V

\

l MASTER LIST Joseph M. Farley Nuclear Plant Unit 1 heet l (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED AC SYSTEM: CHFMTCAT. AND VOLUME CONTROL / SAFETY INJECTION E-21 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL LOCATION BLDG. I ELEV.

IVAL5044G Control Cable Okonite None CTMT 5 115' IVAQ5024C Control Cable Okonite None CTMT 7 115' l

1 I

GPD 1374 Rev. 6/81

MASTER LIST Secti:nC .2.10 Joseph M. Farley Nuclear Plant Unit 1 Sheet I (CLASS 1E ELECTRICAL EOUlFMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: REACTOR CAVITY POST LOCA DILUTION SYSTEM E-22 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1E22M001A (C001A) Dilution Fan Motor Joy Mfg. Co. Type P CTMF 129'-0" Q1E22M001B (C001B) Dilution Fan Motor Joy Mfg. Co. Type P CTMT 129'-0" QlE22V001A 2%" Motor Operated (MOV3872A) Gate Valve Limitoraue SMB-000 CTMT 130'-0" QlE22V001B 2h" Motor Operated (MOV3872B) Cate Valve Limitoraue SMB-000 CTMT 13 0 ' - O

General Q1T52B001 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B019 Penetration Electric 100 Series CTMr 143'-0" General Q1T528023 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B020 Penetration Electric 100 Series CTMT 143'-0" IVAED06Q Power Cable Okonite None CTMT 7115' IVAED06E Control Cable Okonite None CTMT >115' IVBEE09Q Power Cable Okonite None CTMT 7115' IVBEE09E Control Cable Okonite None CTMT > 115 '

I GPD 1374 Rev.6/81

I MASTER LIST Secti:n C.2.11 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 .

(CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: POST ACCIDENT CONTAINMENT COMBUSTTRT.F CAR CON 11 TOT. F-21 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

2" Motor Operated Q1E23V021 (MOV3536) car, vaiy, Limitorque SMB-00 CIMT 116'-6" 6" Motor Operated Q1E23V003 (MOV3530) Gate Valve Limitorque SMB-00 CTMT 130'-6" Q1E23V022A 3/4" Motor Operated (MOV3528A) Globe Valve Limitorque SMB-000 CTMT 126'-6" Q1E23V022B ' 3/4" Motor Operated JMOV3528B) Globe Valve Limitorque SMB-000 CTMT 126'-6" Q1E23V022C 3/4" Motor operated (MOV3528C) Globe valve Limitorque SMB-000 CTMT 126'-6" Q1E23V022D 3/4" Motor Operated (MOV3528D) Globe Valve Limitoraue SMB-000 CTMT 126'-6" Q1E23V025A 3/4" Motor Operated (MOV3835A) Globe Valve Limitoraue SMB-000 CTMT 126'-6" Q1E23V025B 3/4" Motor Operated (MOV3835B) Globe Valve Limitoraue SMB-000 CTMT 126'-6" General Q1T52B005 Penetration Electric 100 Series Cmv 143'-0" General 01T52B017 Penetration Electric 100 Series CmT 1438-0" General Q1T52B007 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B019 Penetration Electric 100 Series CmT 143'-0" General Q1T52B020 Penetration Electric 100 Series Cmr 143'-0" General Q1T52B038 Penetration Electric 100 Series CmT 143'-0" General Q1T52B016 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B015 Penetration Electric 100 Series CTMT 143' 0" IVAFU-W40 Power Cable Okonite Mnna CTMT >115' IVBFU-N20 Power _Cah12 Oknnite None cmT >119' IVAFU-W4C Control Cable okonien Mnna cTMT >11;'

IVAED06E Control cable Okonite Mnne cmT 7119' IVBFV-N2C Control Cable ohnnire unn. curr 71158 IVBEE09E Control Cable Okonite Mnne cTMT >115' IVBFV-YSO Power cable ohnnire wnn. cmt 2111' IVBFV-YSC cnneval cahl. Okonite unn, cmT 7115' IVBW-Y4Q Power Cable Okonite None CIMT 7115' GPD 1374 Rev.6/81

MASTER LIST Section C.2.11 Joseph M. Farley Nuclear Plant Unit 1 Sheet 2 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM:

COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

IVBFV-YSC Control cable Okonite None cmT 7 115' IVAFU-L4Q Power Cable Okonfte None CMT 7115' IVAFU-L5Q Power Cable Okonite None CET 7115' IVBFV-H4Q Power Cable Okonite None CmT 2115' IVBFV-HSQ Power Cable Okonite None CMT >115' IVAFU-L4C Control Cable Okonite None CMT >115' IVAFU-L5C Control Cable Okonite None CTMr 7115' IVBFV-H4C Control Cable Okonite None CNT #115' IVBFV-H5C Control Cable Okonite None cmT 7115' IVAFU-M40 Power Cable Okonite None CmT 7 115' IVBFV-M3Q Power Cable Okonite None CmT >115' IVAFU-M4C control Cable Okonite None CNT 7115' IVBFV-M3C Control Cable Okonite None CmT 7 115' GPD 1374 Rev.6/81

MASTER LIST Section C.2.12 l Joseph M. Farley Nuclear Plant Unit I Sheet 1

)

(CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: LIOUID WASTE DISPOSAL SYSTEM G-21 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1G21SVJ376 (HV3376) Solenoid Valve ASCO NP8316A74V. CTMr 109'-0" Q1G21ZS3376 (HV3376)~ Limit Switch NAMCO EA-180 CTMT 109'-0" NIG21ZS1003B (LCV1003) Limit Switch NAMCO EA-180 CTMT 110'-0" NIG21SV1003B (LCV1003) Solenoid Valve ASCO 206-381-6RF CTHr 110'-0" Q1G21SV7126 (HV7126) Solenoid Valve ASCO NP8_31_6_54V CTMr 117'-0" Q1G21ZS7126 (HV7126) Limit Switch NAMCO EA-180 CTMr I 117'-0" General Q1T52B038 Penetration Electric 100 Series CTMr 143'-0" General 01T52B041 Penetration Electric 100 Series CTMT 143'-0" Q1G21SV3376-B/JB Terminal Block States Co. Type ZWM CYNr 116'-Q" General Q1T52B019 Penetration Electric 100 Series CTMT 143'-0" NIG21SV1003A-A/JB Terminal Block States Co. Type ZWM CTMT 4 116'-0'I NIG21SV7126-A/JB Terminal Block States Co. Type ZWM CTMT M116'-0" IVBL5045C Control Cable Okonite None CTMT > 115'

_ IVBQ50303 Control Cable Okonite None CTMT > 11!'

Boston IVYR5066G Instrument cable Ins. Wire None CTMT > 115' _

IVAL5037D Control Cable Okonite None CTMr > 115 '

IVAQ5021J Control Cable Okonite None CTMT > 115' IVAL5036C Control Cable Okonite None CTMT > 111' _

IVAQ5020J Control Cable Okonite None CTMT 7115' l

l GPD.t374 Rev. 6/81 l

MASTER LIST Sectisn C.2.13 I

Joseph M. Farley Nuclear Plant Unit 1 Sheet (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: MAIN STEAM N-11 COMPON EN TS

^ "

PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL RC ELEV.

Q1N11ZS3369A Mn.Stm.

01V3369Al Limit Switch NAMco EA- 180 Room 19ae Q1N11SV3369AC Mn.Stm.

(HV3369A) solenoid valve __ASco NP8316E36V Room d131' Q1N11ZS3369B Mn.Stm.

(HV3369B) Limit Switch NAMCO . EA.180 Room 128' Q1N11SV3369BC Mn.Stm. f (HV3369B) Solenoid Valve ASCO NP8316E36V _ Room 1131 Q1N11ZS3369C Mn.Stm.

(HV3369C) Limit Switch NAMCO EA- 180 Room 128' Q1N11SV3369CC Mn.Stm. f Solenoid Valve ASCO NP8316E36V noom h131 J HV3369C)

Q1N11ZS3370A Mn.Stm.

(HV3370A) Litnit Switch NAMCO EA- 180 goam ipgi Q1N11SV3370AC Mn.Stm.

(HV3370A) Solenoid Valve ASCO NP8316E36V nnnm 21,i*

Q1N112S3370B Mn.Stm.

(HV3370B) Limit Switch NAMCO EA- 180 Room 128' Q1N11SV3370BC Mn.Stm. f 01V3370B) Solenoid Valve ASCO NP8316E36V noom 313_1 Q1N11ZS3370C Mn.Sem.

(HV3370C) Limit Switch NAMCO EA- 180 goom 128' Q1N11SV3370CC Mn.Stm. /

(HV3370C) Solenoid Valve ASCO NP8316E36V toom h131 Q1N11ZS3368A Mn.Stm.

OlV3368A) Limit Switch NAMCO EA 180 nnn, gi 33 Q1N11SV3368AA . Mn.Stm.

01V3368A) Solenoid Valve ASCO NP8321A2V .pnn, gigi, Q1N11ZS3368B Mn.Stm.

UIV3368B) Limit Switch NAMC0 EA-180 ann, 3133, Q1N11SV3368BA Mn.Stm.

(HV3368B) Solenoid Valve ASCO .NP8321A2V ,,,, p 33, Q1N112S3368C .

Mn.Stm.

NAMCO , EA 180 ann, gigi.

_(HV3368C) Limit Switch Q1N11SV3368CA Mn.Stm.

,NP8321A2V . n nn,,, pi 3 3_ ,

(HV3368C) Solenoid Valve ASCO Q1N11SV3976A Mn.Stm.

(HV3976A) Solenoid Valve ASco NP8321A2V nnn. P131' Q1N11ZS3976A Mn.Stm.

(HV3976A) Limit Switch NAMCO EA- 180 Room ?131' Q1N11SV3976B l Mn.Stm.

Solcnoid Valve ASCO NP8321A2V Room 2131' (HV3976B)

Q1N11ZS3976B Mn.Stm.

(HV3976B) Limit Switch NAMC0 EA-180 Room 2131' Q1N11SV3976C Mn.Stm.

(HV3976C) Solenoid Valve ASCO MP8321A2V. gno, gi3te-

,Q1N112S3976C Mn.Stm.

EA ,180 poo, 3131e

_(l!V3976C) umit Switen NAMCO _

nn.Stm.

Q1N11SV3369AA-A/JB Terminal Block States Co. Type ZWM Room h131' GPD.1374 Rev. 6/S1

MASTER LIST SectionC .2.13 2

Joseph M. Farley Nuclear Plant Unit 1 Sheet (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTJLATED ACCIDENT CONDITIONS)

SYSTEM: MAIN STEAM N-11 COMPON ENTS PLANT ID NUMBER GENEiilC NAME MANUFACTURER MODEL BLDG. ELEV.

Mn.stm.

Q1N11SV3369BA-A/JB Terminal Block States Co. Type ZWM Room }131' Mn.Stm.

Q1N11SV3369CA-A/JB Terminal Block States Co. Type ZWM Room }131' Mn.Sim.

Q1N11SV3370AA-B/JB Terminal Block States Co. Type ZWM Room 2131' Mn.Stm.

Q1N11SV3370BA-B/JB Terminal Block States Co. Type ZWM Room ?131' ~~

Mn.Stm.

Q1N11SV3370CA-B/JB Terminal Block States Co. Type ZWM Room 3131' hn.Stm.

Q1N11SV3368AA-A/JB Terminal Block States Co. Type ZWM Room 2131' Mn.Stm.

Q1N11SV3368BA- A/JB Terminal Block States Co. Type ZWM Room D131' Mn.Stm.

Q1N11SV3368CA-A/JB Terminal Block Etates Co. Type ZWM Room D131' Mn.Stm.

Q1N11SV3976A-B/JB Terminal Block States Co. Type ZWM Room 3131' Mn.Stm.

Q1N11SV3976B-B/JB Terminal Block States Co. Type ZWM Room D131' Q1N11SV3976C-B/JB Terminal Block States Co. Type ZWM Mn.Stm.f Room 131' Mn.Stm.

IVAL5019E,F Control Cables Okonite None Room ,131' Mn.Stm.

IVAL5045C Control Cable Okonite None Room 2131' Mn.Stm.

IVAQS013A Control Cable Okonite None Room ?131' Mn.Stm.

IVAT0001C,D.E Control Cable Okonite None Room h131' Mn.Stm.

IVAL5020E,F Control Cable Okonite None Room 2131' Mn.Stm.

1 VAL 5046C Control Cable Okonite None Room )131' Mn.Stm.

IVA05015A Control Cable Okonite None Room .?131' Mn.Stm.

IVAL5021E,F Control Cable 01 tonite None koom f131' GPO 1374 Rev.6/81

MASTER LIST Section C. 2.13 Joseph M. Farley Nuclear Plant Unit 1 Sheet 3 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: MAIM STEAM N-11 COMPON ENTS PLANT ID NUMBER GENERIC NAM E MANUFACTURER MODEL BLDG ELEV.

Mn.Stm .

IVAL5047C Control Cable Okonite None Room 2 131' Mn.Stm.

IVAQ5017A Control Cable Okonite None Rnnm 2 131' Mn.Stm.

IVBL5010E,D Control Cable Okonite None Room 3131' Mn.Stm.

IVBL5021C Control Cable Okonite None Room 2 131' Mn.Stm.

IVBQ5013D Control Cable Okonite None Room 5131' Mn.Stm.

IVBT0001F.G.H Control Cable Okonite None Room 2 131' Mn.Stm.

IVBL5011E.D Control Cable Okonite None Room D 131' Mn.Stm.

IVBL5022C Control Cable Okonite None Room D 191' Mn.Stm.

IVB05015D Control Cable Okonite None Room 3 131' Mn.Stm.

IUBL5012E.D Control Cable Okonite None Room E 131' Mn.Stm.

IVBL5023C Control Cable Okonite None Room 3 191' Mn.Stm.

IVB05017E Control Cable Okonite None Room 3111' Mn.Stm.

IVAL5045B Control cable Okonite None Rnom A lil' Mn.Stm.

IVA05013B Control Cable Okonite None Rnom U 191' Ma.Stm.

IVYR5008A Cnntrol Cable Okonite Nnne Rnnm d 191' Mn.Stm. 3 1VATM046 B Control Cable Oknnite Nnne Rnnm - 1 91 '

Mn.Stm.

1VAO5015R Control Cable Oknn{te Mnne Rnnm d 191' Mn.Stm.

IVYR5008B co ntrol Cable Okonite None Rnnm N 191' Mn.Stm.

1VATM047B Control Cable Okonite None Rnnm D 191' Mn.Stm. ,

1VAO5017Bt control Cable Okonite Nnne Rnnm

  • 1 91' Mn.Stm.

1VXR5008C Control Cable Okonite None Rnnm k 191' Mn.Stm.

_1VRTM 021 B Control Cable Okonite None Rnom 191' Mn.Sem.

1Vnn5019F Cnntral cable ohnnita Mnna unnm D 131' Mn.Stm.

_1VBL5022B Control Cable Okonite None Room 2 131' Mn.Ctm.

IVB05015E Control Cable Okonite None Room D 131' GMD 1374 Rw, W81

MASTER LIST Sectisn C.2.13 Sheet 4 Joseph M. Farley Nuclear Plant Unit 1 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

MATM STEAM N-11 SYSTEM:

COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

nn . xm .

IVBL5023B Control cable Okonite None Room } 131'

- Mn.Stm.

IVBQ5017F Control Cable Okonite None Room -- 131 '

Q1N11LT477 Level Transmitter Barton 764 CTMr 129' I

Level Transmitter Barton 764 CTMT 129' Q1N11LT487 Level Transmitter Barton 764 CTMr 129' Q1N11LT497 General Q1T52B040 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B041 Penetration Electric 100 Series CTMT 143'-0" Boston IVXV5013L Instrument Cable Ins. Wire None CTMT > 115'-0" Boston IVXV5014H,J Instrument Cable Ins. Wire None CTMr > 115'-O' i _

f.

I I

i GPD 1374 Rev.6/81

MASTER LIST Joseph M. Farley Nuclear Plant Unit 1 Secti:n Sheet C.{.14 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: AUXILIARY STEAM N-12 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1N12SV3234A MN. SDL (HV3234A) Solenoid Valve ASCO NP8320A186V ROOM >131' Q1N122S3234A MN. SD:

(HV3434A) Limit Switch NAMCO EA- 180 ROOM &131' Q1N12SV3234B MN. SD, (HV3234B) Solenoid Valve ASCO NP8320A186V R0011_ h131' Q1N12ZS3234B MN. SD.

(HV3234B) Limit Switch NAMCO EA-180 ROOM D131' Q1N12SV3235A MN.SD (HV3235A) Solenoid Valve ASCO NP8321A2V nooM 2131:

Q1N12ZS3235A MN SD.

(HV3235A) Limit Switch NAMC0 EA-180 nnnu hau i Q1N12SV3235B MN. SD:

(HV3235B) Solenoid Valve ASCO NP8321A2V nnnu 2 131' QlN12ZS3235B MN. SD1 (HV3235B) Limit Switch NAML') _ _ _ . EA-180 nnnw 2131' MN. SE Q1N12SV3234A-A/JB Terminal Block States Co. Tvpn WM nnnM 2131' Q1N12SV3234B-B/JB Terminal Block States Co. Type ZWM y bl31' MN. SDj Q1N12SV3235A-A/JB Terminal Block States Co. Type ZWM ROOM 2131' Q1N12SV3235B-B/JB Terminal Block States Co. Type ZWM bM D131' None MN. SDyD ; 131'

'lVAL5003B Control Cable nknn a ROOM

~

MN SDI IVAQ50llA Control Cable Okonite None R06M D-131 '

IVXR5007F Control Cable Okonite None u 1131' MN. SD1 IVBL5007B Control Cable Okonite None ROOM E131' MN. SD1 IVBQ5013B Control Cable Okonite None ROOM 3131' IVYR5033E Control Cable Okonite None 6M 131' ,

MN. Sni IVAL5004C Control Cable Okonite None ROOM l2131' MN. STM' IVAQ5010D Control Cable Okonite None ROOM 2131'

IVNR5003A,B
  • Instrument Cables kN Oire None bM 2131' IVBL5005C Control Cable Okonite None 6M E131' IVBQ50llB control cable Okonite None f06M hl31' MN. SD!

IVXKJ183C,D,G,H Control Cables Okonite None ROOM 2131' l

GPD.1374 Rev. 6/81 ,

MASTER LIST Section C.2.15 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: MAIN FEEDWATER AND CONDENSATE N-21 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1N21V001A-B 14" Motor Operated Mn.Stm.

(MOV3232A) Stop-Check Globe V1 Limitorque SMB-4T Room >j 131' Q1N21V001B-B 14" Motor Operated Mn.Stm.

(MOV3232B) Stop-Check Globe V1 Limitorque SMB-4T Room >j 131' Q1N21V001C-B 14" Motor Operated Mn.Stm.

(MOV3232C) Stop-Check Globe V1 Limitorque SMB-4T Room >j 131' Mn.Stm.

Q1N21LSH2828A Level Switch Gems LS-36497 Room 127'-6" Mn.Stm.

01N21LSH2828B Level Switch Gems LS36487 Room 127'-6" Mn.Stm.

01N21LSH2828C Level Switch Gems LS-36497 Room 127'-6" Mn.Stm.

01N21LSH2829A Level Switch Gems LS-36497 Room 127'-6" Mn.Stm.

01N21LSH2829B Level Switch Gems LS-36497 Room 127'-6" Mn.Stm.

01N21LSH2829C Level Switch Gems LS-36497 Room 127'-6" Mn.Stm.

AITB034 Terminal Block States Co. Type ZWM Room 2/ 131' Mn.Stm.

IVALS120A.B.C.D Control Cable Okonite None Room 2/ 131' Mn.Stm.

IVBL5092A, B. C Control Cable Okonite None Room >/ 131' Mn.Stm.

IVBFV-K20 Power Cable Okonite None Room 7/ 131'

. Mn.Stm.

IVBFV-K30 Power Cable Okonite None Room 2/ 131' Mn.Stm.

IVBFV-L20 Power Cable Okonite None Room kj 131' Mn.Stm.

IVBFV-K2A Control Cable Okonite None Room M/ 131' Mn.Stm.

IVBFV-K3A Control Cable Okonite None Room >/ 131' Mn.Stm.

IVBFV-L2A Control Cable Okonite None Room M / 131' GPD.1374 Rev. 6/81

.n. l

MASTER LIST Section C.2.16 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: AUXILIARY FEEDWATER N-23 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1N23V011A 4" Motor Operated Mn. Stm (MOV3350A) Stop-Check Globe VI Limitorque SMB-1 Room ?131' Q1N23V011B. 4" Motor Operated Mn. Stm (MOV3350B) Stop-Check Globe VI Limitorque SMB-1 Room E131' Q1N23V0 llc 4" Motor Operated Mn. Stm (MOV3350C) Stop-Check Globe VI Limitorque SMB-1 Room E 131' Q1N23ZS3228A Mn. Stm (HV3228A) Limit Switch NAMCO EA-180 Room E131' Q1N23SV3228AA Mn. Stm (HV3228A) Solenoid Valve ASCO NP8320A196E goom r131' Q1N23ZS3228B Mn. Stm (HV3228B) Limit Sw!.tch NAMCO EA 180 Room 2 131' Q1N23SV3228BA Mr.. Stm (HV3228B) Solenoid Valve ASCO NP8320A196E Room E131' Q1N23ZS3228C Mn. Stm (HV3228C) Limit Switch NAMCO EA-180 Room Z131' 01N23SV3228CA Mn. Stm (HV32280) Solenoid valve ASCO NP8320A196E- Room a 131' Q1N23ZS3227A Mn. Stm (HV3227A) Limit Switch NAMCO EA 180 Room E131' 01N23SV3227AA Mn. Stm (HV3227A) Solenoid Valve ASCO NP8320A196E Room E131' 01N23ZS3227B Mn. Stm (HV3227B) Limit Switch NAMCO EA-180 Room E131' Q1N23SV3227BA Mn. Stm (HV3227B) Solenoid Valve ASCO NPB320A196E Room z l31 '

Q1N233S3227C Mn. Stm (HV3227C) Limit Swit ch NAMCO EA-180 Room a 131' Q1N23SV3227CA Mn. Stm (HV3227C) Solenoid Valve ASCO NP83200 43E Room 2 131' Mn. Stm Q1N23SV3228AA-A/JB Terminal Block States Co. Type ZWM Room 2 131' Mn. Stm Q1N23SV3228BA-A/JB Terminal Block States Co. Type ZWM Room E 131' Mn. Stm Q1N23SV3228CA-A/JB Terminal Block States Co. Type ZWM Room E 131' Mn. Stm Q1N23SV3227AA-A/JB Terminal Block States Co. Type ZWM Room E 131' Mn. Stm Q1N23SV3227BA-A/JB Terminal Block States Co. Type ZWM Room 2 131' Mn. Stm Q1N23SV3227CA-A/JB Terminal Block States Co. Type ZWM Room E 131' Mn. Stm IVAFU-U4Q Power Cable Okonite None Room dC 131' Mn. Stm IVAFU-USQ Power Cable Okonite None Room 2 131' Mn. Stm IVAFU-12Q Power Cable Okonite None Room D 131' Mn . St m IVAFU-U4A, D Control Cables Okonite None Room .E 131' GPD 1374 Rev,6/81

MASTER LIST Joseph M. Farley Nuclear Plant Unit 1 Section C.2.16 Sheet 2 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER SYSTEM: AUXILIARY FEEDWATER

. N-23 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

IVAFU-USA, D Control Cables Mn. Sta Okonite None Room ) 131' IVAFU-12A, D Control Cables Mn. Sta Okonite None Room & 131' IVAL5007B Control Cable Mn. Sta Okonite None Room ) 131' IVAL5008B Mn. Stm Control Cable Okonite None Room 7 131' IVAL5009B Control Cable Mn. Stm Okonite None Room 2 131' Boston Mn. Sta IVAL5007C Instrument Cable

- Ins. Wire None Room >s 131' IVAL5008C Boston Mn. Stm Instrument Cable Ins. Wire None Room >,131' Boston Mn. Stm IVAL5009C Instrument Cable Ins. Wire None Room 2 131' IVAQ5010E, K Control Cables Mn. Stm Okonite None Room >,131' IVAQ5012E, K Control Cables Mn. Stm Okonite None Room ),131' IVAQ5014E, K Mn, Stm Control Cables Okonite None Room 4 131' IVXR5007K, L, M Control Cables Mn Stm Okonite None Room >,131' IVAL5013C Control Cable Mn Stm Okonite None Room ),131' IVAL5014C Centrcl Cable Mn. Stm Okonite None Room  % 131' IVAL5015C Control Cable Mn. Stm Okonite None Room D 131' Boston Mn. Stm IVAL5013D Instrument Cable Ins. Wire None Room 2 131' Boston Mn. Stm IVAL5014D Instrument Cable Ins. Wire None Room ) 131' Boston Mn. Stm IVAL5015D Instrument Cable Ins. Wire None Room  % 131' IVAQ5048H, K Control Cables Mn. Stm Okonite None Room A 131' IVAQ5006C, H Control Cables Mn. Stm Okonite None Room D 131' IVAQS008C, H Mn. Stm Control Cables Okonite None Room D131' IVXR5007G, H, J Control Cables Mn. Stm Okonite None Room D 131' I

l GPD 1374 Rev. 6/81

MASTER LIST Section C.2.17 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: CHEMICAL INJECTION SYSTEM _ N-25 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1N25SV3772A Mn.Stm.

(HV3772A) Solenoid Valve ASCO NP8316A74V aoom B 131' Q1N25ZS3772A Mn.Stm.

(HV3772A) Limit Switch NAMCO EA-180 goom 7 131 Q1N25SV3772B Mn.Stm.

(HV3772B) Solenoid Valve ASCO NP8316A74V goom 5 131 Q1N25ZS3772B

    • Mn.Stm.

(HV3772B) Limit Switch NAMCO EA-180 goom 3 131 Q1N25SV3772C Mn.Stm.

(HV3772C) Solenoid Valve ASCO NP8316A74V goom 7 131 Q1N25ZS3772C Mn.Stm.

(HV3772C) Limit Switch NAMCO EA-180 Room 7 131 Mn.Stm.

Q1N25SV3772A-A/JB Terminal Block States Co. Tvoe ZWM Room I 131' _

Mn.Stm.

01N25SV3772B-A/JB Terminal Block States Co. Tyne ZWM Room 131' Mn.Stm.

01N25SV3772C-A/JB Terminal Block States Co. Tvoe ZWM Room 131' Mn.Stm.

IVAL5076A Control Cable Okonite None Room E 131' Mn.Stm. g IVAL5077A Control Cable Okonite None Room 131' Mn.Stm. p IVAL5078A Control Cable Okonite None Room 131' Mn.Stm.

IVAQ5030E Control Cable Okonite None Room E 131'

' Mn.Stm.

IVAQ5031E Control Cable Okontte None Room M 131' Mn.Stm.

IVAQ5032E Control Cable Okonite None Room 191' Mn.Stm.

IVXR5008G. H. J Control Cable Okonite None Rnnm 111' 1

GPD 1374 Rev.6!81

MASTER LIST Section C.2.18 )

Joseph M. Farley Nuclear Plant Urit 1 Sheet 1 j

l (CLASS IE ELECTRICAL EQU:PMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: SAMPLING SYSTEM P-15 COMPON ENTS PLANT ID NUMBER GENERIC NAM E MANUFACTURER MODEL BLDG. ELEV.

Q1P155V3103 (HV3103) Solenoid Valve ASCO NP8320A184V CTMT 129'-0" Q1P15ZS3103 (HV310'O L{mie Rufech MAMCO FA-1Rn cTMT 190' n" (HV17Mi Rnl annid Valve ARCO NP8320A184V

_ _ CTMr 190'-n" Q1P15ZS3765 (HV3765) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3766 (HV3766) Solenoid Valve ASCO NP8320A184V CTMT 129'-0" Q1P15ZS3766 (HV3766) Limit Switch NAMCO EA 180 CTMT 129'-0" Q1P15SV3179A (HV3179A) Solenoid Valve ASCO E83201184V CTMT 129'-0" Q1P15ZS3179A (HV3179A) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3179B (HV3179B) Solenoid Valve ASCO NP8320A184V CTMT 129'-0" Q1P15ZS3179B (HV3179B) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3179C (HV3179C) Solenoid Valve ASCO NP8320A184V CTMr 129'-0" Q1P15ZS3179C

(

_ HV3179C) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3180A (HV3100A) Solenoid Valve ASCO NP8320A184V c7g7 399.on Q1P15ZS3180A (HV3180A) Limit Switch NAMCO FA-180 CTMT 179'-O" Q1P15SV3180B (HV3180B) Solenoid Valve ASCO NP8320A184V, I CTMT 199'-n" Q1P15ZS3180B (HV3180B) Limit Switch NAMCO F A-1 RO CTMT 190' n" Q1P15SV3180C (HV3180C) Solenoid Valve ASCO NP8320A184V CTMr 129'-0" Q1P15ZS3180C OlV3180C) Limit Switch NAMCO FA-180 CTMr 129'-0" Q1P15dV3181A (HV3181A) Solenoid Valve ASCO NP8320A184V CTMT 129'-0" Q1P15ZS3181A l (HV3181A) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3181B j (HV3181B) Solenoid Valve ASCO NP8320A184V CTMT 129'-0" 1 Q1P15ZS3181B (HV3181B) Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15SV3181C .

(HV3181C) Solenoid Valve ASCO NP8320A184V- CTMT 129'-0" l Q1P15ZS3181C (nV11 R1 ci Limit Switch NAMCO EA-180 CTMT 129'-0" Q1P15Sv3104 OlV3104) Solenoid Valve ASCO 'NP8370A184V CThrr 129'-0" j GPO 1374 Rev.6/81 l

MASTER LIST Section C.2.18 Joseph M. Farley Nuclear Plant Unit 1 Sheet 2 (CLASS IE ELECTRICAL EOulPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: SAMPLING SYSTEM P-15 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

Q1P15ZS3104 (HV3104) Limit Switch NAMCO EA-180 CTMT 179'-0" General Q1T52B019' Penetration Electric 100 Series CTMT 143'-n" Q1P15SV3103-A/JB Terminal Block States Co. Type ZW CTMT 131'-9" Q1P15SV3765-A/JB Terminal Block Sates Co. Type Z W CTMT 131'-9" General 01T528007 Penetration Electric 100 Series CTMT 143'-0" 01P15SV3766-A /JB Terminal Block States Co. Tyne ZW CTMT 131'-9" 01P15SV3179A-A/JB Terminal Block States Co. Type ZW CTMr 131'-9" 01P15SV3179B-A/JB Terminal Block States Co. Tvoe ZW CTMr 131'-9" 01P15SV3179C-B/JB Terminal Block States Co. Tvoe ZW CTMT 131'-9" General 01T5?B020 Penetration Electric 100 Series CTMT 143'-0" 01P15SV3180A-A/JB Terminal Block States Co. Type ZW CTMT 131 ' - 9

Q1P15SV3180B-A/JB Terminal Block States Co. Type ZW CTMT 131'-9" 01P15SV3180C-B/JB Terminal Block States Co. Type ZW CTMr 131'-9" 01P15SV3181A-A/JB Terminal Block States Co. Tvoe ZW CTMr 131'-9" 01P15SV3181B-A/JB Terminal Block States Co. Tvoe ZW CTMT 131'-9" CIP15SV3181C-A/JB Terminal Block States Co. Tvoe ZW CTMT 131'-9" 01P15SV3104-A/JB Terminal Block States Co. Type ZW CTMr 131'-9" IVAL5063B Control Cable Okonite None CTMT >115' IVAQ5049H Control Cable Okonite None CTMr >115' i l

IVXR5010B Control Cable Okonite None CTMr >115' IVAL5065B Control Cable Okonite None CTMT >115' IVAQ5032J Control Cable Okonite None CTMr >115' IVXR5010F Control Cable Okonite None CTMr >115' IVAL5066A Control Cable Okonite None CTMr >115' IVAQ5033J Control Cable Okonite None CTMT 7 115' GPD 1374 Rev.6/81

MASTER LIST Section C.2.18 Joseph M. Farley Nuclear Plant Unit 1 Sheet 3 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: SAMPLING SYSTEM P-15 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEV.

IVXR5010H Control Cable Okonite None CTMT > 115 '

IVAL5084B Control Cable Okonite None CTMT 2115' IVAL5085B Control Cable Okonite None CTMT >115' IVBL5074B Control Cable Okonite None CTMT >115' IVAL5086B Control Cable Okonite None CTMT >115' IVAL5087B Control Cable Okonite None CTMT >115' IVBL5075B Control Cable Okonite None CTW >115' IVAL5088B Control Cable Okonite None CTMT >115' IVAL5089B Control Cable Okonite None CTMT >115 '

1FBL5076B Control Cable Okonite None CTW N115' IVAL5064B Control Cable Okonite None CTMT >115' IVA05047H Control Cable Okonite None CTMT >115' IVXR5010D Control Cable Okonite None CTMT >115' 1

i GPD 1374 Rev.6/81

MASTER LIST Section C.2.19 I

Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: SERVICE WATER P-16 COMPONENTS PLANT ID NUMBER GENERIC NAM E MANUFACTURER MODEL BLDG. ELEV.

QlP16V207A 10" Motor Operated .

(MOV3441A) Gate Valve Limitoraue SMB-00 CTMT 130'-6" Q1P16V207B 10" Motor Operated (MOV3441B) Gate Valve Limitorcue SMB-00 CTMT 130'-6" Q1P16V207C 10" Motor Operated (MOV3441C) Gate Valve Limitoroue SMB-00 CTMT 122'-6" Q1P16V207D 10" Motor Operated (MOV3441D) Gate Valve Limitoraue SMB-00 CTMT 122'-6" Q1P16V081 6" Motor Operated (MOV3131) Gate Valve Limitoroue SMB-00 CTMT 130'-6" General Q1T52B005 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B015 Penetr.. tion Electric 100 Series CTMT 143'-0" General 01T52B007 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B020 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B014 Penetration Electric 100 Series CTMT 143'-0" General Q1T52B019 Penetration Electric 100 Series CTMT 143'-0" IVBFV-J40 Power Cable Okonite None CTMT 7 115' IVBFV-J4D Control Cable Okonite None CTMT > 115' IVBQ5007D Control Cable Okonite None CTMT 7 115' IVYR4006B,D Controi Cables Okonite None CTMT > 115' IVYKB164B.C Control Cables Okonite None CTMT > 115' IVBFV-J50 Power Cable Okonite None CTMT 7 115' IVBFV-JSD Control Cable Okonite None CTMT > 115' IVB05009D Control Cable Okonite None CTMT 7 115' IVAFU-K60 Power Cable Okonite None CTMT  ? 115' IVAFU-K6D Control Cable Okonite None CTMT } 115' TtVA05007D Control Cable Okonite None C'D4T 7 115' IVXR5005B.D F Control cablem oknnte. Knn, cTMT > 115' IVXKB164B C Control Cables Okonite None CTMT > 115' IVAFU-W2Q Power Cable Okonite None CTMr 7115' GPD 1374 Rev. 6/81

MASTER LIST Section C.2.20 Joseph M. Farley Nuclear Plant Unit 1 Sheet 1 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: COMPONENT COOLING WATER P-17 COMPON ENTS PLANT ID NUMBER GENERIC NAM E MANUFACTURER MODEL BLDG. ELEV.

Q1P17V097 6" Motor Operated (MOV3046) Gate Valve Limitoraue SMB-00 CTMT 130'-6" QlF175V3184 (HV3184) Solenoid Valve ASCO .NP8316A76V CINT 122'-6" Q1F17ZS3184 (HV3184) Limit Switch NAMCO EA-180 CTMT 122'-6" Q1P17SV3443 (HV3443) Solenoid Valve ASCO NP8316A74V CTMT 129'-0" Q1P17ZS3443 (HV3443) Limit Switch NAMCO EA-180 CTMr 129'-0" General Q1T52B016 Penetration Electric 100 Series CTMT 143'-0" General 01T52B038 Penetration Electric 100 Series CINT 143'-0" General Q1T52B020 Penetration Electric 100 Serfes CTMT 143'-0" Q1P17SV3184-B/JB Terminal Block States Co. Type ZWM CTMr 7 115'-0" General 01T52B019 Penetration Electric 100 Series CTMT 143'-0" General e Q1T52B041 Penetration Electric 100 Series CTMT 143'-0" Q1P17SV3443-A/JB Terminal Block States Co. Type ZWM CTMr > 115 '-0

IVBFV-C30 Power Cable Okonite None CTMT > 115.'_

IVBFV-C3D Control Cable Okonite None CTMT >115' IVB05017C Control Cable Okonite None CTMT > 115' IVYR5006F Control Cable Okonite None CINT >115' IVBL5009C.D.E.F Control Cables Okonite None CTMT >115' IVB05017H Control Cable Okonite None CIMI > 115 '

IVYR5035B Control Cable Okonite None CTMT 7115' IVAL5055C Control Cable Okonite None CTMT 7115' IVA05029H Control Cable Okonite None CTMT >115' IVYR5064F Control Cable Okonite None CTMT >115' l

l GPD 1374 Rev.6/81 l

MASTER LIST Secti:n C.2.19 1 Sheet 2 Joseph M. Farley Nuclear Plant Unit ,

(CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: SERVICE WATER P-16 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG. ELEV.

IVAFU-W2D Control Cable Okonite None CTMT > 115' IVAFU-b4Q Power Cable Okonite None CTMT > 115' IVAFU-H4A Control Cable Okonite None CTMT > 115' IVAQ5002F Control Cable Okonite None CTMr > 115' S

GPD 1374 Rev. 6/81

1 1

)

i JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 DOCKET NO. 50-364 ENVIRONMENTAL QUALIFICATION REPORT P

6

JOSEPH M. FARLEY NUCLEAR PLANT ,

UNIT 2 ENVIRONMENTAL QUALIFICATION REPORT Table of Contents

(

Section A - 90 Day Submittal Section B - 10CFR50.49 Submittal Section C - Response to NRC April 12, 1983 letter Attachment 1 - Reference List for Westinghouse '

Justifications for Withholding Proprietary Information '

Attachment 2 - Documentation Previously Considered Proprietary Attachment 3 - We~stinghouse Request for Withholding Proprietary .

Information Attachment 4 - Qualified Equipment Master List I

j

- D-22 -

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SECTION A 90-DAY SUBMITTAL In response to the NRC's NUREG-0588 Safety Evaluation Report (SER),

dated February 4,1983, Alabama Power Company provides this section of the report regarding the review of envi ronmental qualification of Class 1E electrical equipment for Farley Nuclear Plant (FNP) Unit 2. The subjects covered by this section include plans to resolve the outstanding items in Alabama Power Company letter dated March 14,1983, (30-day response to the SER) and information regarding proprietary portions of the Technical Evaluation Report (TER). The scope of this review ensures that equipment necessary to protect the public health and safety is capable of performing its intended function when subjected to a harsh environment.

Qualification Test Report No. 950.301, dated June 19, 1981, fully supports the qualification of Victoreen radiation detectors when the detector cables / connectors are sealed f rom the accident moisture envi ronment of the containment atmosphere. These detectors were installed as an enhancement to the radiation monitoring system to satisfy the requirements of NUREG-0737 and would be used to detect a radiation release due to a potential breach of the reactor coolant pressure boundary. Design of a water-tight sealing for the detector cable / connectors installed at FNP has been completed which duplicates the sealing procedure followed in the Victoreen Test Report No. 950.301. As stated in Alabama Power Company letter of March 14, 1983, the water tight fitting will be installed during the first outage of sufficient duration to complete the modification currently scheduled to begin in the fourth quarter of 1983. The Victoreen radiation detectcrs are not considered within the scope of 10 CFR 50.49 since, as stated in Alabama Power Company's letter dated June 23, 1982, such equipment is addressed by the TMI Action Plan and is not essential to achieve a safe shutdown condition. The installation of the water tight fittings on the radiation detectors therefore does not impair the safe shutdown capability of Farley Nuclear Plant.

The qualification reports for the Target Rock solenoid valves used on the reactor head vent system are aJrrently under development by Westinghouse with a scheduled completion of May 1983. Alabama Power Company installed these solenoid valves in order to provide the state-of-the-art coincident with the implementation dates required by NUREG-0737. Alabama Power Company will review the reports when issued to ensure that the solenoid valves are qualified to the specific Farley Nuclear Plant accident envi ronment. These solenoid valves are not

-considered within the scope of 10 CFR 50.49 since, as stated in Alabama Power Company's letter dated June 23, 1982, such equipment is addressed by the TMI Action plan and is not essential to achieve a safe shutdown

condition. Additionally, the reactor head vent system is de-energized and can.not be placed into operation without the approval of the NRC as specified by NURGE-0737, II.B.1. There is no known environmentally caused failure mode of these de-energized solenoid valves that could lead to the spurious or inadvertant operation of the reactor head vent system.

W

l Section A Page 2 All vendors have responded to Alabama Power Company's request for providing justifications for withholding specific TER information from public disclosure. Westinghouse has reviewed the appropriate sections of the TER and has identified information that still requires protection from public disclosure. Applications for withholding and affidavits for protection of the proprietary information were submitted by Westinghouse to the IRC in accordance with 10 CFR 2.790(b) when the proprietary documents were originally submitted. The pages of the TER that Westinghouse considers proprietary are Item No.11, pages 51, j and Item No.13, pages 5b,c,d,e,f,g,h,1,J. Attachment 1 provides a list of the applicable Westinghouse test reports and associated Westinghouse transmittal letter numbers and dates of issue to facilitate the retrieval of justification for withholding.- BIW Cable Systems, General Electric, Okonite, Limitorque, Transamerica - Delaval, Joy Manufacturing and Automatic Switch Company documents referenced in the TER are no longer considered proprietary. This completes the review of proprietary information contained in the TER's as requested by Safety Evaluation Report and the NRC letter dated April 12, 1983 Equipment items in NRC Category IV, " Documentation Not Made Available", include Boston Insulated Wire and Barton Transmitters. The Boston Insulated Wire and Cable Company has reviewed the applicable portions of the TER and has determined that their test report and letter of clarification no longer require proprietary protection. The Boston Insulated Wire and Cable Company Test Report 73E062 and letter of clarification, dated August 21, 1981, which addresses their Test Report 73E062, are included as Attachment 2 of this report. As stated in Alabama Power Company's response dated March 14, 1983, Westinghouse considers WCAP-9885, which fully qualifies the Barton transmitters installed in FNP, as a proprietary document. Westinghouse has requested (Attachment 3) that Alabama Power Company not submit their proprietary information to the Franklin Research Center. Pursuant to an agreement reached between Westinghouse and Mr. E. C. Shoemaker of the NRC Office of the Executive Legal Director, Westinghouse will ensure that any such requested material is, or has been, submitted directly to the NRC. Mr. E. C. Shoemaker has discussed this matter with Mr. Z. Rosztcczy of the Equipment Qualification Branch.

SECTION B 10 CFR 50.49 SUBMITTAL In' response to the NRC's request in 10 CFR 50.49, " Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants", Alabama Power Company provides this section of the report regarding the review of environmental qualification of Class 1E electrical equipment at Farley Nuclear Plant (FNP) Unit 2 regarding the review of environmental qualification of electrical equipment important to safety within the scope of 10 CFR 50.49.

Attachment 4 of this report provides a Master List of all electrical equipment important to safety within the scope of 10 CFR 50.49 (b)(1) and (b)(2). This Master List identifies the system, plant ID number, generic name, manufacturer, model and location of each equipment item. All equipment identified in the Master List is environmentally qualified and, l thererore, a schedule to upgrade the qualification of electrical equipment within the scope of paragraphs (b)(1) and (b)(2) of 10 CFR 50.49 is not necessa ry.

In accordance with Generic Letter 82-33, Alabama Power Company provided the NRC, by letter dated April 15, 1983, a Preliminary Farley Emergency Resporse Capability (ERC) Integrated Implementation Plan and Schedule for the installation of an integrated system for the enhancement of the existing and adequate ERC at FNP. The integrated system addresses Supplement 1 to NUREG-0737, whose basic provisions include Regulatory Guide 1.97. The schedule for the installation of this integrated system, including Regulatory Guide 1.97, is plant-specific and provides for prompt implementation while optimizing the use of utility and NRC resources.

R.G.1.97 includes provisions to upgrade the environmental qualification of accident monitoring instrumentation. The provisions of R.G. 1.97 are addressed in the implementation schedule for the integrated ERC system.

Alabama monitoringPower Company equipment (will provide Regulatory environmentally Guide 1.97) to satisfy 10 qualified accident CFR 50.49(b)(3) in accordance with the Preliminary Farley ERC Integrated Implementation Plan and Schedule. Consequently, an exemption is requested, pursuant to 10 CFR 50.12, from the requirements of 10 CFR 50.49(g) to allow the schedule for identifying accident monitoring equipment (Pegulatory Guide 1.97) as described in 10 CFR 50.49(b)(3) and upgrading its environmental qualification of to be in accordance with the Preliminary Farley ERC Integrated Implementation Plan and Schedule in Alabama Power Company letter dated April 15, 1983.

The identity of equipment at FNP within the scope of 10 CFR 50.49(b)(1) and (b)(2) and its qualification is documented in previous Alabama Power. Company NUREG-0588 responses, Appendices 1 through 5. In addition, equipment outside the scope of 10 CFR 50.49 has been qualified to satisfy the TMI Action Plan requirements of NUREG-0737. The identity of this TMI Action Plan equipment and its qualification is documented in

, NUREG-0588 Response - Appendix 6 TMI Action Plan Equipment, transmitted in Alabama Power Company letter dated June 23, 1982. The equipment identified

-in Appendix 6, not previously addressed in Appendices 1 through 5, is not

Section B Page 2 ~

essential to achieve a' safe shutdown condition and -is not considered within the scope of 10 CFR 50.49. The qualified status of the TMI Action Plan equipment, as with all electrical equipment important to safety, will be maintained environmentally qualified in accordance with the FNP Environmental . Qualification Administrative Program discussed in Section C - ,

of this report.

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SECTION C

. . RESPONSE TO NRC APRIL 12, 1983 LETTER ,

4 In response to the NRC's' Safety Evaluation clarification letter dated i April 12, 1983, Alabama Power Cogany provides this section of the report '

regarding the review of environmental qualification of Class 1E electrical equipment for Farley Nuclear Plant (FNP) Unit 2. The subjects covered by

. . this.section include .a review of the Alabama Power Company letter dated March 14,1983, (30-day response to the SER); a review of information in

.the -Technical Evaluation Report -(TER) claimed to be proprietary; a review  ;

of the programs and scope of equipment addressed by previous environmental qualification submittals for compliance with paragraphs (a) and (b) of 10 '

CFR. 50.49; and a discussion of methods used to identify the equipment ,

t covered by paragraph 10CFR50.49 (b)(2). The scope of this review ensures that equipment necessary to protect the public health and safety is capable of performing its intended function when subjected to a harsh environment.

As state'd in the letter dated March 14, 1983, it is the judgement of '

Alabama ' Power Company that all' equipment, which includes NRC Categories I.B,11_I_'.A, and IV, required to achieve a safe shutdown condition at FNP is environmentally qualified and Justifications for Continued Operation (JCO) for equipment items in these NRC categories are not necessary. Equipment items in NRC Category _IV, " Documentation Not Made Available", are discussed in Section A of this report.

All vendors have responded to Alabama Power Company's request for

providing justifications for withholding specific TER information from public disclosure. Information requiring and not requiring proprietary

- protection is discussed in Section A of this report.

Subsequent to its publication in the Federal Register on January 21, 1983, Alabama Power Cogany reviewed the provisions of 10 CFR 50.49 to

. determine differences from the nriginal licensing documents, IEB 79-01B and NUREG-0588 With regards to paragraph (a) of 10 CFR 50.49, Alabama Power 1 _ Cogany is iglementing an Environmental Qualification Administrative Program for FNP to maintain the qualification of safety-related electrical

~ equipment required to perform its intended function when exposed to a harsh

. environment. .This program includes provisions for procurement that provides for the replacement of electrical equipment igortant to safety 1and TMI Action Plan equipment in accordance with 10 CFR 50.49. Addition-ally, this: program provides for design control, procurement control, storeroom-control, preventive maintenance, environmental ~ qualification-surveillance land document control. .This. program addresses in-service degradation through preventive _ maintenance / surveillance with equipment and l

' component refurbishment _and/or . replacement' based on' known susceptibility to aging: degradation,. the results of 1 inspections, and manufacturer's recommendations._ This program will maintain the continued qualified status

. of- equipment presently installed and thb qualification of equipment associated with. any future modifications.' , Alabama Power Company will

review Regulatory Guidet i.89,LRev.1 upon its issuance and will consider l

its-guidance related to further; program modifications. This program,.

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j' i which ensures compliance dth J10 CFR 50.49, will be implemented by the end fy, of the Unit 2 second refueling outage currently scheduled for the fourth 3 quarter of 1983 In the opinion of Alabama Power Company, the FNP e Environmental Qualification Administrative Program and the methodology by which it was developed complies with 10 CFR 50.49(a).

Additionally,' Alabama Power Company has reviewed the scope of g equipment addresped .in the previous FNP responses to NUREG-0588 and has

, _ ,,(( del.emined that this scope of equipment satisfies the provisions of

^ paragraphs (b)(1) and (b)(2) of 10 CFR 50.49. The establishment of new

y

- qualification ^ programs to address the equipment within the scope of paragraphs (b)(1) and (b)(2) of 10 CFR 50.49 is not necessary.

, Accident-monitorbg instrumentation described in paragraph (b)(3) of 10 CFR'50.49 will be identified in accordance with the Preliminary Farley ERC Integrattd Implementation Plan and Schedule submitted in Alabama Power Company letter dated April 15, 1983 An exemption regarding the identity of accident, monitoring equipment and its upgrading from the schedule provided in paragraph (g) of 10 CFR 50.49 nas been requested with specificity in Section B of this report.

A Master List.Nf safety-related and nonsafety-related equipment within the scope of paragra'phs -(b)(1) and (b)(2) of 10 CFR 50.49 is presented in Attachment 4 of this report. The Master List for Farley Nuclear Plant -

t S Unit ?_ das developed by a systematic review of design and as-built documentation, the FSAR, Technical Specifications and Emergency Operating

, Procedures to determine the systems required to perform a safety-related function. The definition of safety-related equipment and its intended functhp used in developing the Master List is consistent with paragraph (b)(1) of 10 CFR 50.49. The review criteria and methodology resulted in a Master Cist that includes safety-related and nonsafety-related equipment whose environmentally caused failure could unacceptably impair the intended functioQ of safety-related equipment.

The' review criteria ~ and methodology utilized to develop the Master List for;Farley Nuclear Plant Unit 2 are as follows:

~

1. This review determined the systems and components required to perform a safety-related function or support for the performance of a safety-related function. These components were included in the Master List.
2. ~The control circuitry of components identified in Item 1 above was
g reviewed for connections (interlocks) to other' safety-related and nonsafety-related components. If spurious or inadvertent

, , operation due to environmentally induced f ailures of the connected

.j t components in the harsh environment could adversely affect the conpletion of.a safety furiction, the connected (interlocks) safety-related or nonsafety-related components were included in

'... A the Master List.

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3. The instrumentation circuitry of components identified in Item 1 above was reviewed for connection to other safety-related and.

nonsafety-related components. If spurious or inadvertent operation due to environmentally induced failures of the connected components in the harsh environment could cause erroneous indication of the status of safety-related components, the connected safety-related or.nonsafety-related components were included in the Master List.

4. Forithe components identified in Item 1 above, the power circuitry inside the harsh environment was reviewed.- If environmentally induced f ailures could result in a loss of power to components required to complete 'a safety-related function, the safety-related or nonsafety-related power circuitry components were included in the Master-List. There are no connected safety-related/nonsafety-related power circuits in the harsh environment.

. The Master List of Attachment 4 developed from this review criteria and ' methodology identifies safety-related equipment that is relied upon to remain functional during and following design basis events and nonsafety-related equipment whose environmentally caused failure could unacceptably impair the intended function of safety-related equipment. In

. the opinion of Alabama Power. Company, the equipment identified in the Master List complies with paragraphs (b)(1) and (b)(2) of 10 CFR 50.49.

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ATTACHMENT-1 Reference List .for Westinghouse Justifications for Withholding Proprietary Information Date of

Westinghouse Test ' Reports - Westinghouse Letter No. Issue-

- 1) WCAP-7820 E-SL-100 12/16/71 WCAP-7820 Suppl. 1 E-SL-336 l05/31/72

-2 NS-RS-075 11/02/73

. 3 NS-RS-183 03/22/74 4&5 N/A' 6 NS-CE-1268 11/05/76 7 N/A

2) WCAP-7709L .

E-SL-042 07/14/71 WCAP-7709L Suppl. 1 E-SL-334 03/23/72 2 N/A 3 NS-RS-128 01/23/74 4 NS-RS-212' 04/21/74 3)-WCAP.9157 .NS-LE-1600 12/16/77

, NS-TMA-2202 02/14/80 I

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ATTA.CHMENT 2

. Enclosed are two documents which were previously not made available to the NRC for proprietar.y . reasons. - These documents 'are: - (1) Boston Insulated Wire.and Cable Company's Test Report 73E062, and.(2) Boston Insulated Wire and Cable Comoany's letter of clarification, dated August.

21,1981'. which concerns thei r Test Report 73E062. These documents are no

- longer considered proprietarv ~ by Boston Insulated Wi re and Cable Company. ,

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B ET N IN S U L AT'E D WIRE & CABLE CD.

S S W AY STR E ET . 5 O ST O N . M A5 5 AC H U S ETTE O 212 5

  • ts t 7? 2 5 5-210 2 * *c6c = 0 94 54 0 September 7, 1973 Mr. M. Malcom, Project Manager
  • Bechtel Power Corporation P.O.IBox 607 Gaithersburg. Maryland 20760

Subject:

P.O. #FNP-371 ,

Instrument Cable Joseph M. Parley Nuclear Plant Prototype Test Program BIW Orders #B040, B041 B052. B053

Dear Mr. Malcom:

l Please find enclosed the prototype test data for the subject order.

The data was obtained in accordance with Specification SS-1102-101, Rev.1, and the test program outlined in our letter of April 13, 1973 We hope that the results of this program will be useful in your evalua-

.N - of the instrument cable.

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,IT.rr7. * ~ ""h, ave . ques

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-- : - . --  : 3 Very truly yours.

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RECORD SEPI A 7597-0 3- EGS *d -/o -/

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TITLE: Prototype Test Program Results JOB: JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 ALABAMA POWER COMPANY P.O. FNP-371 MFR.

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VENDOR'S DRAWING REVIEW 1 @ Approved.we.mer pe esed.

2 Approved . summit and e.g. we. may pressed appread sesept es nome . eneks ehenges and euhmit final shug. . htfg. may preened as approved.

4 Not approved . Correst and reautenit.

a noviour not respaired . h88 9 . seer pressed.

Approval of this alrewing deem not relieve supplier from fult compliones esiih senerset er purehses order reesleemorres.

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JOB NO. BECHTEL POWER CORPORATION

' 7597 43 P.o.cox eer aAmeEnssuno.aso.

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RECORDS TuaNOVER _;

L 7597-03-E25.6-10-1 RECORD SEPIA

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CUSTOMER: Bechtel Corp. Lab Test # 73E062

- (Parley Nuclear Plant)

BIW Job # B040, B041, Customer P.O. # F.N.P. 371 B052 B053 Customer Item # Y01 BIW P/N 9537-R-002 (Lss 1893A)

Spec. # SS-1102-101 Prototype test report per letter sent to Mr. M. Malcolm of Bechtel Co.

by J. Learn of Boston Insulated Wire on April 13, 1973 (1) Para. S.2.1 Radiation Resistance Test Conditioning: (a) Samples air oven aged for 168 hrs. 0 121 0C.

(b) Aged samples irradiated to a total dose of 2 x 100 rada. (See attached radiation certificate -- Attachment I. )

4 Tests Spec. Para. Results High Voltage (ac) 8.3 1.la pass 4 KV ac for 5 min.

j Insulation 8.3.1.lb 4.5 x 103 Megn &

Resistance Continuity 8.3.1.2 pass Tensile Strength 8.3.2.1 1030 pai (0.T.)

Elongation 8.3 2.11 70% (O.E.)

after conditioning Tensile Strength 8.3 2.2a;bECHTE!. POWER co67. 9%. (O.T. ) _

Elongation 8.3.2.2a hM 168 hrs.

d5N/)N .8% (0.E. ) --

9 1210C 3[ p 12 }g73 8.32.2bf N.5%(0.T.)

Tensile Strength Elongation 8.3 2.2bN #' N # E%% (O.E.)

42 hrs.

- - G 80 psi 1270C O l _ __ -- _ _ . _ . _ _ - . - . _ . _ _ _ _ . . _ _ _ . _ . _ _ _ _ _ . . _ _ _ _ . _ . _ . _ _ . _ _ _ _ . _ _ _ , _ .

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Tr.blo continued from prcvicus paga

.- (1) Para. 8.2.1 Tests Spec. Para. Results l

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Gravimetric Water 8.3.2 3b 129 mg/ine Absorption Electrical Water 8.3.E.3a

. . - . . . = __

Dielectric Constant

'4.17

' Absorption (E.M. 60) "

Increase in Capacitance

" (1-14 day) =25T

" (7-14 day) - 2.9%

" Stability Factor (14 day) - 0.3 (2) Para. 8.2.2 Flame Resistance Test (a)

  • Test Spec. Paragraph Conditioning Result

~

Vertical Flame 8.2.2.1 -

pass (IPCEA S-19-81) para. 6.19.6 Vertical Flame 8.2.2.1 168 hrs. # 12100 pass (IPCEA S-l')-81) para. 6.19.6 (b) The results of the vertical flame tray tests which were performed in accordance with paragraph 8.2.2.2 using a burlap igniter flame source are included as Attachments II, III and IV of this report.

BECHTEL POWER COi:P.

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.. (3) Para. 8.2.3 Post-Accident Environment Tcst Sample was aged 168 hrs. e 1210C.

Conditioning: (a)

(b) Aged agsple was irradiated to a dose of 2 x 1 @ rada. (See Attachment I for radiation certificate.)

The result of the autoclave test cycle as specified in para-graph 8.2.3 3 is included as Attachment V. The insulation resistance measurements required by paragraph 8.2 3 5 are l also given in this attachment.

In accordance with paragraph 8.2.3.6, the physical and electrical tests specified in paragraphs 8.31 and 8.3 2 were performed on the sample upon its removal from the autoclave.

The results of the tests performed on this irradiated and autoclaved sample are given below. ,

f Tests Spec. Paragraph Results High Voltage (ac) 8.3 1.la pass 4 KY ac for 5 min.

Insulation 8.3.1.1b 2.8 x 104 Megr1/k'
. . Resistance Continuity 8.3 1.2 pass Tensile Strength 8.3 2.1 920 psi (o.T. ) -- ' -

Elongation 8.3 2.1) 80% (0.E.)

after autoclave l and conditioning Tensile Strength 8.3 2.2a 52 3% (0.T.) 7 ,

168 hrs. 4 121 0C -- - - i ~ '

i Elongation _

37.6% (0.E.) }

Tensile Strength 8 3 2.2b 74% (o.T.)

42 hrs.Ogopsi and 127 C Elongation 68.8% (0.E.)

Gravimetric Water 8.3 2.3b 15 0 meg /ine Absorption Electrical Water 8.3 2 3a Dielectric Constant = 3 16 Absorption (E.M. 60) Increase in Capacitance BSCHUK POMMR CORP. (1-14 day) - 2.6%

(7-14 day) = 1.8%

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/b Stability factor (14 day) = 0.2 SEP 121973 1.h . JL JOB Mo. T M1, 03/20 9

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1,./.**,;pb'jDosim'atry _ Systems , Dosimetry ywas performed using,,a Victoree:i Model. ,

c ;'*- f . r. . %i. , y: ' '. * ^. 555 Integrating Do.se. Rate Meter..and.' Probe; ;The unit was -calibaated on January'15,1971 by: the

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Company, using. Cobalt-60

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( ,. Victoreen Instrument _and Cesium-137 sources whose' calibra C.$ $:4 '[" -

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N .' Post-Irradiation Defects Observed: ' '

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  • Ronnit .m Street.

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.wo...-s.na-o,. .c Doohee", CQndo Telephorie'(514) 4671211 ,

v . -.

,; .. ~ .. .-

s.:.4 .z ./.. . -s. . ..

.e . .,4.

,...,,=

. ** j g

Pago 5 of 8

)

ATTACHMENT II f .30STON INSULATED WIRE & CABLE C0.

Ger;ral Data Sheet TEST N O.:

FAR:

TEST:

Flame Test Inquiry #SS-1102-101 SPEC:

8.2.2.2 73P027A

^

0 6/18 /73 ,

  • * ' " " ' * *
  • Aged 168 hrs. e 121 0 TESTED BY: f PART. TYPE NO.:

W. Barnes l LSS-1893A LAB. SUP. CHECK:

R. Oppenheim CUSTOMER: Parley (Alabama Power)

TEST REquiREwENTS: According to above spec. 'y ,

((1 -

Construction: 2X #16 AWG OR-853A min, wall .027, IX T-92, 2 lap. Wrap #18 AWG solid drain wire; IX T-33 alum.-Mylar, 2 lap, alum. down, OR-547-J min. wall-

.054.

lap sin e 24" x 24" folded Sample #1 Bu1 5 m:Ln.

Sottk time Unt:L1 159 grams remained Drain time.

Ignition t ime 35 aec.

Bu1 lap burn time 16inin. 45 see.

6 mLn.

~

Continues to burn

  • Cable dams.ge 1 2 :Lnches ._

Inaulatier, failur e

L. No a'lectric al failure It.

i ll.

M N

)(, " .

!5.

6.

N N ey N n_

9.

" " " BECHTEL Po wr > < n--

10.

M B'iFWi!Tiik$

= , ~2 r m f % '

'l@

g Otr12y 73 --

I JOBUn,75py ., oggn .__

/

Y r7- _

Pega 6 of 8 ATTACHMEFF III

.- '.- ( ISTON INSULATED WIRE & CABLE C0.

    • - General Data Sheet Flame Test Inquiry #SS13IO2-101 8.2.2.2 * *73P027B

^ '

" " 6/18/73 Aged 168 hrs. e 121'C PART, TYPE NO.: TESTED E Barnes 5 MEC C""" Parley (Alabama Power) **'g , U P p. leim 11 CUT //

TEST REQUIREMENT 5:

According to above spee. ,

. F. ? ._

~

TEMP.2 ' Rfi:

I Sample #2 Burlap size 24" x 24" folded Sosik time 5 utn.

Dratin time Until 158 grams remained IgrLition time 20 siec.

Burlap burning time 28 nin. 36 see.

Coritinues to burn 0 see.

~

Cable damage 14 f.nches Inslulation failure

1. No electric al failure E!. 8 min. O sec. -- one circuit oniv
  • 1 . No electric ni failure t a " "

a a n s;,

6 .

e a w 7 ,

E.

t ,

ICi. 19 min. 40 see. -- one circuit anive BECHTEl. POWER N -* _

'One donductor -- stield fa ilure '3 9@@9,7u r meme a ri pT att 14101 3

u. .s JOB NO,7597 03]20 I

~_ ~~~. _ _ _ _ , _ _ _ _. .. --

,< P2g3 'T of' 8

.,*YJ.'. . ' J0STON INSULATED WIRE & CABLE C0.

ATTACHMENT IV

~

,' General Data Sheet 1

$PEC: PAR: TEST N O.:

TEST:

Flame Test Inquiry #SS-1102-101 8.2.2.2 73P027C

^

cONDITIONINGr Aged 168 hrs. 0 121*C 6/19/73 TESTE Y:

FART, TYPE NO.:

LAB. SUP. CHECK:

CU5 TOWER:

Farley (Alabama Power) R Oppenheim Tl e OUT A TEST REQUIREMENT 5:

According to above spec. , g7- - L..

TEMPl: ' hH:

i Sample #3 Bu: Flap site 24" x 24" Sokktime 7m Ln.

DriEin timet Unt L1 165 nrams resained Ignition t.ime 25 iseo.

Buhlap burning time 22 inin. 5 sieo.

4 Continues to burr. O s<no.

Cable damose 15 :Lnches l Inisulatiori failure

L. 10 siin. 45 sec. 10 min , 56 see ,e
2. No atiectric al fail are 3, w n i =
  1. # " .,o... - ~ . . .._ __ -

< E_ n wei s a a. a v vv1;n by,g. ,

a a a mto menon --- r

m

, , , unq w-a \v/ g,,

n.

f_ # # # 3CF 1 2 3/3 p' W w n O- Z

q. " *
  • JOBlan 7<ov ' ' ' '

_ no ion s.- -

  • Fwo conductors -- shield (otmdondt otor -- conduo bor fai' Lure) 9
  • ' Pcga 8 of 8'
  • ATTACHMENT V l

. .1: ,'.

BOSTON INSULATED WIRE O CABLE CO.

, General Data Sheet CUSTOMER:

Test No.: 73E062B Alabama Power Company)

(Farley Nuclear Plant Date: July 25, 1973 Spect Inquiry #SS-1102-101 Post-Incident Environment Test Para. 8.2.3 The electrical circuit specified in para. 8.2.3 2 was maintained for the durstion of the test on this irradiated sample. No insulation failure took place.

The chemical spray, consisting of a 10.000 nmn mainHa= af boric acid buffered with NaOH to give a Ph factor of 10.5. was also provided for.the test duration. The test cycle and the I.R.

readings taken at the required intervals as specified in para.

8.2.3 5 are given in Table i below.

TABLE 1 I.R. in Meg a M4' Temperature Pressure Cond. #1 Cond. #2 Time l

80'F 0 2 x 10 5 1.8 x 105 Initial Reading 300 0F 80 psi i 7 x 10 2 8 x 10 22 1 hr.

7 x 10 2 8 x 10 2 2 hr.

7 x 10 2 8 x 10 3 hr.

5 x 10 6 x 102 4 hr.

2g0F 0 16" pai 5 x 103 7 x 1o 22 1 day 5 x 10 7 x 10 2 2 days

" " 4 x 1033 7 x 1o 3 ,,y, 1 x 10 2 7 x to2

" " 4 days

" " 4x1 7 x 410 1 5 days 1.7 x 1 #(10 Al 6 days 7x1 *(3 x 103A) 7 days

  • Readings taken with Simpson meter.BECHTEL POWER COF.

n h bbEl x.c a e ai3 LiL 4

- Jos tio. ng .03/.20 Y.

/

4 r ,

i%._

L~: <L t . i BOST N IN S U L ATE t3 WIRE & CABLE CD.

55 B AY STR EET. WOETON

  • M AES AC HUS ETTS O2125 . (517) 255-2102 6 c August 21, 1981

[ fyljg 2] AUG2 51981

  • 18 Bechtel Power Corporation JOB 7597 03l20 15740 Shady Grove Road \ BECHTEL y Gaithersburg, Maryland 20877

% _t7 Attention: A. A. Vizzi Project Engineer Joseph M. Farley Nuclear Plant Units 1 and 2 Environmental Qualification Purchase Order FNP-371 Bechtel File E-91 V-3967 Gentlemen:

. In reference to your letter of August 14, 1981, we are enclosing Appendix A t Figure I which apply to the cables with ethylene propylene rubber insulation. The slope of Figure I was derived from tests on EPR insulation as described in Appendix A. A line drawn through the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> /121*C point in Figure I with the same slope (slope represents rate of aging as described in Appendix A) shows a projected life of 40 years at 49'C. Consequently, aging for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121 C represents 40 years at 49*C for the ethylene propylene rubber insulation.

Please contact us if you have any questions.

Very truly yours, khi BIW CABLE SYSTEMS, INC.

n cGr**%"),&

~.'. j ~~  ;

.g43 7 *- . __ J. R. Learn

} . 3:y- _i Applications Engineer e.* .;.r, .-g m ,

g

, ' I t' ', t */- L + - ----"

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L e ss '.'*;__.-.

. ,3 -- " '

q i--

7-g i _

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Y, c;j d "V- 91 -

1 j.!

APPENDIX A M .

LONG-TERM PHYSICAL AGING PROPER"IES - 40 YEAR LIFE Long-term physical aging tests conducted on cables indicate a life in excess of 40 years - at 900 for BIW's ethylene propy-lene rubber insulation. This is shown by the Arrhenius plot in Figure-I for cables aged at 2000, 180C, 1500, 136C and

)

121C.

Accelerated agings were initially made at the five test temper-atures on specimens taken from slabs. The slope of the line determined by data points was found to be the same for differ-ent end points and can be taken to represent the rate of change by the materials to any defined end condition. By using this slope to determine a line intersecting the 40 year life -- 900 temperature point as shown in Figure I -- we can determine what the expected cable life must be at any aging temperature to represent the equivalent of 40 years at 900, since any r point on the line represents the equivalent of 40 years at 900.

, Specimens of BIW cables were removed from the ovens periodical-ly, as shown. in Figure I, and subjected to a dielectric proof

  • test of,2200 volts (twice rated voltage + 1000). After success-fully passing the test, the samples were returned to the oven for continued aging. As the data clearly ~ indicate, the cables 4

withstnnd the proof test voltage when aged in excess of that representing 40. year service. The specimens were subjected to bending after aging in excess of the 40 year conditioning.

As Figure I indicates, cable samples at 2000, 180C, 1500, 136C and-121C have surpassed the 40 year requirement. When bent around.a 40X diameter mandrel, the ethylene propylene rubber insulation was undamaged and still withstood the. voltage proof test.. Passing points above the 40 year-90C life line indicate ,

margin of performance.

i Figure I is offered for acceptance as evidence of 40 year life at 900 in lieu of additional testing or data. These tests were .

i conducted in accordance with IEEE 383-1974, para. 2.3.'2.

D 0 1

- RE0BVED -

5' AUG2 51981 > @

J03 7597 03/20 i

\ BECHTEL &

j _

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9.WY.,3 W

Attachment 3 n-sa mma ,

' Westinghouse Water Reactor n,m3

!! :tr!:Cor;ctatlen O!vis!ons tenere m pr e 9 February 19, 1982 i ALA-82-506 Mr. H. O. Th' rash, Manager

' Nuclear Generation Alabama Power Company 600 North Eighteenth Street Birmingham, Alabama 35291

Dear Mr. Thrash:

Alabama Power Company J. M. Farley Unit 1 and 2 SAFETY EVALUATION ON EQUIPMENT QUALIFICATION Recently the NRC has issued letters to some utilities regarding the results of the staff review of the utility response to the Safety Evaluation onThe Equipment Qualification.information from the utility central file be forwarded to Fra Center to facilitate the NRC contractor review.

Where the requested information is not proprietary to Westinghouse, it is

, appropriate for utilities to submit such information directly to

~

the NRC Office of the Executive Legal Director, who has discussed this matter with Mr. 2. Rosztoczy of the Equipment Qualification Brar.ch, we ask that you Westinghouse not submit Westinghouse proprietary information to Franklin.

will ensure that any such requested material is, or has been, submitted directly to the NRC on a timely basis.

Should you have any questions concerning this advice, please contact myself or Mr. George Butterworth of our Nuclear Safety Department (412) 373-5761.

Very truly yours.

t J. . Mil r, Manager trating P ant Service So thern Region

~~~

VLM/93L ,,-

Attachment J. R. Crane /

k' 4 -

cc: R. P. Mcdonald W. G. Hairston, III p'. g yE b- 0. D. Kingsley, Jr. I

0. Batum R. W. Wise y g' RECElvEo l '- R. H. Bau11g NETS c

l ,

\.

Y.

' ~.$.' .'. '

~

1 i 1

,.________________________________________l

~

~-ATTACHMENT 4

- QUALIFIED EQUIPMENT ITEMS This Master List' includes :the system, plant ID numbers, generic name, manufacturer, model and location of each qualified equipment item. These are safety-related, Class IE electrical equipment items, which are required to achieve 'a safe shutdown condition at FNP.

h 1

. ) 4.'

D-22 F

Y q , < - A r- ,-A, ,,+,w y <v  :--e

MASTER LIST Sectien C.2.1 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 ICLASS IE ELECTRICAL EOulPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM. REACTOR COO 1. ANT INSTRUNENTATION B-13 3

COMPONENTS PLANT ID NLHBER GENERIC NAME MANUFACTURER K) DEL LOCATION BLDG ELEV N2B13TE412B RTD Ros'emount 176KF CTMI 124'-0" N2B13TE412D RTD Rosemount 176KF CTMr 124'-0" N2B13TE422B RTD Rosemount 176KT CTMT 124'-0" N2B13TE422D RTD Rosemount 176KF CTMT 124'-0" N2B13TE432B RTD Rosemount 176KF CTMT 124'-0" N2B13TE432D RTD Rosemount ,

176KF CTMT 124'-0" General Q2T52B012 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B028 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B030 Penetration Electric 100 Series CTMT 143'-0" 12TB001 Terminal Block States Co. Type Zkt CTMT 124'-0" 12TB002 Terminal Block States Co. Type Zsy CTMT 124'-0" 22TBr03 Terminal Block States Co. Type Zky CTMT 124'-0" 22*.3004 Terminal Block States Co. Type 2km CTMT 124'-0" 32TB001 Terminal Block States Co. Type Zkt CTMT 124'-0" _

32TB002 Terminal Block States Co. Type 2kT CTMT 124'-0" Boston 2V1V5002B, D Instr. Cables Ins. Wire None CTMT 124'-0" Boston l 2V2V5002B, D Instr. Cables Ins. Wire Nnno CTMT 124'-0" Boston 2V3V5002B, D Instr. Cables Ins. Wire None CTMT 124'-0" m

GFD 13741/3)

MASTER LIST Seetien C.2.2 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 (CLASS IE El.ECTRICAL EQUIPMENT GEOUIRED TO FUNCTlHN UNDER POSTULATED ACCIDENT CONDITIONSI SYSTEM: REACTOR COOLANT SYSTEM - STEAM CENERATOR B-21 COMPONENTS PLANT ID NLHBER GENERIC NAME MANUFACTURER PODEL LOCATION BLDG ELEV N2B21PT402 Press. Transmitter Bar' ton 763 CTMT 116'-0" N2B215'T403 Press. Transmitter Barton ,

763 C n tr. 116'-0" N2B21TE410 RTD Rosemount 176KS CTKr 122'-9" N2B21TE413 RTD Rosemount 176KS CTMT 122'-9" N2B21TE420 RTD Rosemount 176FS CTMT 122'-9" N2B21TE423 RTD -

Rosemount 176KS Cntr 122'-9" N2B21TE430 RTD Rosemount 176KS CTMT 122'-9" N2B21TE433 RTD Rosemount 176KS CTMT 122'-9" venerat Q2T52B040 Penetration Electric 100 Series CTMT 143'-0" General Q2TS2B012 Penetration Electric 100 Series CTMT 141'-0" General Q2T52B030 Penetration Electric 100 Series CTMT 143'-0" 12TB001 Terminal Block States Co. Type 2km CTKr 122'-9" 12TB003 Terminal Block States Co. Type ZbH CTNT 122'-9" 12TB004 Terminal Block States Co. Tvoe 2kT CTMT 122'-9" 22TB001 Terminal Block States Co. Tvoe 2kT CTFtr 122'-9" 22TB002 Terminal Block States Co. Tvoe ZWM CTMT 122'-9" 22TB005 Terminal Block States Co. Tvoe ZkN cTMT 122'-9" Boston

,2VYV5031B Instr. Cables Ins. Wire CT'ff 122' 0" None Boston ,

2VYV5033B Instr. Cables Ins. Wire None cT3rf 122'-9" Boston 2VIV5002E, F, G Instr. Cables Ins. Wire Nono Boston CTMf 1??' o" .  !

)

2V2V5002E, F, G Instr. Cables Ins. Wire None cTMT 1??'-9" _

l l

{

GPD 1374 tiso l ,

MASTER LIST Secticn C.2.3 Jowph M. Farley Nuclear Plant Unit 2 Sheet i ICLASS lE ELECTRICAL EQUIPMENT REQUl;ED T3 FUNCTION UNDER POSTULATED ACCIDENT CONDITIONSI system: REACTOR COOLANT SYSTEM - PRESSURIZER B-31 l COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER 70 DEL LOCATION BLDG ELEV O2B31SV6047 .

(HV8047) _

Solenoid Valve ASCO NP831654E CTFtr 118'-0" N2B3}2S8047 i (HV8047) Limit Switch NAMCO EA-180 CThrr 118'-0" i

. C'eneral  !

_ Q2T52B002 Penetration Electrie 100 Series CTMT 147'-0" General )

Q2T52B038 Penetration Electric 100 Series CTMT 147'-0" N2 B31SV8047-B /J B Terminal Block States Co. Type ZWM CTMT 118'-0" Level Q2B31LT459 Transmitter Barton 764 CThrr 116'-0" Level Q2B31LT460 Tre smitter Barton _764 CTFtr 116'-0" Level Q2B31LT461 Transmitter Barton 764 CTMT 116'-0" Pressure Q2B31PT455 Transmitter Barton J 6 3__ CTMT 116'-0" Pressure Q2B31PT456 Transmitter Barton _763_ CTMT 116'-0" Pressure Q2B31PT457 Transmitter Barton _763 CTirr 116'-0" 116'-0" 2VBL5078C Control Cable Okonite None CThrt ' & above 116'-0" 2VBQ5021E Control Cable Okonite None CTFrr * & above General Q2T52B012 Penetration Electric 100 Series CTirr ' 147'-0" General Q2T52B028 Penetration Electric 100 Series CTirr

  • 147'-0" General Q2I52B030 Penetration Electric 100 Series CTirr ' 147'-0" General Q2752B040 Penetration Electric 100 Series CThrr
  • 147'-0" Boston 116'-0" 2VYV5031D Instr. Cable Ins. Wire None cThrr * & abova Boston 116'-0" 2V1V5002U Instr. Cable Ins. Wire None cTirr * & above Boston 116'-0" 2V2V5002T, U Instr. Cables Ins. Wire None cTMT' & nhnvn Boston 116'-0" 2V3V5002T, U Instr. Cables Ins. Wire None cTMT' & nbovo l

1 b.D1374 1/3)

C2 ASTER LIST Seetion C.2. 4 Joseph M. Faley Nuclear Mant Unit 2 Sheet 1 4 CLASS IE ELECTRICAL BOUIPMENT REQUIRED TO FUNCTION UNDER POETULATED ACCIDENT CONDITIONS)

,FSTEM FEENATER C0FTROL STS'ITM . C-22 (XMPONENTS FLANT ID NUMBER GENERIC NA." MANUFACTURER IODEL LOCATION ,

_. _ BLDG ELn' I N Cu?.504 75 . Aux.  ;

(FCV478) ; Limit Switch NAMCO EA - 180 side. 121'-0" N2C22SV0476A K7-206-381-2Rl Ayx. i

_ (FCV4 78)- Solenoid Valve ASCO side. 121'-0" '

i N2C22SV04785 qv.206-381-2RL Aux.

(FCV478) Solenoid Valve ASCO Elde. 121'-0" N2C22ZSO486 Aux.

_(FCV488) Lieft. Switch NAMCO EA-180 Aldo 121'-0" N2C22SV0488A HV-206-381-2Rt A"** t (FCV488) Solenoid Valve ASCO -' Blde. 191'_n" N2C22SV0488B Aux.

(FCV488) Solenoid Valve 6-381-2RL ASCO 81de. 121'-0"

_N2C222SO498 Aux.

(FCV498) Lieft Switch NAMCO EA 1.80 B1de. 121'-0" N2C22SV0498A Aux.

iV-206-381-2RL (FCV498) Solenoid Valve ASCO B1de. 121'-0" N2C22SV0498B Aux.  !

(FCV498) Solenoid Valve iV-206-381-2RL ASCO Bide. 121'-0" N2C22ZSO479 Aux.

(FCV479) Lieft Switch NAMCO EA-180 B1da. 121'-0" N2C22SV0479A iV-206-381-4U Aux.

__(FCV479) Solenoid valve ASCO Blde. 121'-0" N2C22SV0479B 4V-206-381-4U ^"X*

Solenoid valve (FCV479) ASCO B1de. 121'-0" N2C222SO489 Aux.

-_ __(FCV489) Lielt Switch NAMCO EA-180 Blde. 121'-0" -

N2C22SV0489A qv.206-381-4U Aux. 4 (FCV489) Solenoid Valve ASCO Elde. 121'-n" '

N2C22SV04898 iV-206-381-4U' . Aux.

(FCV489) Solenoid Valve ASCO Blde. 121'-0" N2C222SO499

  • Aux.

(FCV499) Limit Switch NAMCO EA 180 B1de. 121'-0" N2C22SVD499A 4y.206-381-4U< Aux.

_(FCV499) Solenoid valve ASCO __ R1do- 191' n" N2C22SV0499B #"**

(FCV499) Solenoid valve ASCO (V-206-381-4U R1a,_ 121,-0n Aux. ,

N2C22SV0478A-A/JB Terminal Block States Co. Me hv Blde. 121'-0" '

Aux.

N2C22SVO488A-A/JB Terminal Block Etaten ca. Me hv Blde. 171'-n" Aux.

N2C22SV0498A-A/JB Terminal Block States Co. Type EWM 31d c_ . 121'-0" _.

Aux.

Control Cable 2 VAL 5060B Okonite None Bidc. __121'-0" Aux.

2VBL&O255 Control Cable Okonite None Elde. 121'-0" _

Aux.

2VIL5071A Control Cable Okonite None Bldg. 121'-0" _.

l

  1. D 1374 1 3 l

Joseph M. Farley Nuclear Plant Unit 2 Sheet 2 (CLASS IE ELECTRICAL EQUIPMENT REOUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

FEEDL'ATER CONTROL SYSTEM C-22 SYSTEM.

. COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER HDDEL LOCA7 ION BLDG ELEV Aux.

2 VAL 5061C Control Cable Okonite None Bld g. 121'-0"

Aux.

2VBL5034C D Control Cables Okonite None Bldg. 121'-0" Ai2 x .

2VXL5072B Centrol Cable Okonite None Bld g. 121'-0" Aux.

2 VAL 5062B Centrol Cable Okonite None Bldg. 121'-0" Aux.

2 VEL 5035B. D Control Cables Okonite None Bldg. 121'-0" Aux.

2VXL5073A Control Cable Okonite None Bldg. 121'-0" Q2C22LT474 Level Transmitter Barton 164_

CTMT 121'-0" Q2C22LT475 Level Transmitter Barton _764 CTMT 121'-0" _

Q2C22LT476 Level Transmitter Barton 764 CTMT 121'-0" Q2C22LT484 Level Transmitter- Barton _764 CTMT 121'-0" Q2C22LT485 Level Transmitter Barton 764_ CTMT 121'-0" Q2C22LT486 Level Transmitter Barton _764 CTMT 121'-0" Q2C22LT494 Level Transmitter Barton 764 CTMT '121'-0" Q2C22LT495 Level Transmitter Barton 764 CTMT '121'-0" Q2C22LT496 Level Transmitter Barton 764 CTMT 121'-0" Q2C22FT474 Flow Transmitter Barton 764 CTMT 121'-0" Q2C22FT475 Flow Transmitter Barton .764 CTMT 121'-0" Q2C22FT484 Flow Transmitter Barton 764 CTMT .121'-0" Q2C22FT485 Flow Transmitter Barton 764 CTMT 121'-0"

_02C22FT494 Flow Transeitter Barton . _764 CTMT *121'-0" 02C22FT495 Flow Transmitter Barton 764 CTMT .121'-0" General Q2T52B010 Penetration Electric 100 Series CTMT 121'-0" General Q2T52B012 Penetration Electric 100 Series CTFtr 121'-0" General Q2T525028 Penetration Electric 100 Series CTMI 121'-0" General Q2T525030 Penetration Electric 100 Series CTMT 121'-0" GFD.1374 Sts0 l

.s I

MASTEA List Sactien C.2.4 Joseph M. Farley Nuclear Plant Unit 2 Sheet 3 lCLAts IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) l VSTEM. FEEIMAITR CONTROL SYSTEM C-22  !

i COMPONENTS PLANT ID NL% ER GENERIC NAME MANUFACTURER IODEL LOCATION BLDG ELEY Boston 2V1V5002L, M, N Instrument Cable Ins. Wire None cTMT 121'-0" Boston 2V2V5002L, M, N Instrument Cable Ins. Wire None CTMT 121'-0" 2V3V5002H, J, K, Boston L. M. N Instrument Cable Ins. Wire None CTMT 121'-0" Boston 2V4V5002A B. C Instrueent Cable Ins. Wire None cTMT 121'-0" GFD 1374 treo

MASTER LIST Section C.2.5 Joseph M. Farl;y Nucl:ar Plant Unit 2 Sheet 1 cf ICLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: SAFEGUARD SYSTEMS, RHR/LHS1 E-11 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER !ODEL LOCATION BLDG ELEV Q2E11LT3594A Level Transmitter Gems XM-36495 CTMT 116'-0" 02E11LT3594B Level Transmitter Gems XM-36495 cThrr 116'-0" General 02T52B006 Penetration Electric 100 Series cT3rr 141'-n" General 02T52B020 Penetration Electric 100 Series cT5tr 141'_n" 116'-0" 2VAIS009F Control Cable Okonite None CTMT A nhnvn 116'-0" 2VBI5008C Control Cable Okonite None CTMT & nhnvn i

l w

l l

GFD 1374 1/30

MASTER LIST Section C.2. 6 Jowph M. Farley Nuclear Plant Unit 2 Sheet 1 (CLAS$ IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITION CONTAINMENT COOLING AND PURCE E -12 ." E -14. P-13 SYSTEM:

COMPONENTS GENERIC NAME MANUPACTURER PODEL LOCATION l FLANT-ID NUM5ER ,

BLDG ELEV j

' N'E*r 0perated 134'-6"

~

Q2E14V002 (MOV3660: , g,,3 Li itorcue SMB-000 C n tr 3

I Q2E14V004 - 1" Notor Operated Globe valve Limitorque SMB-000 Cntr 116'-0" l (MOV3318B)

DELETED- f Q2P13ZS3196 129'-0" (Hv3196) Limit Switch NAMCO EA-180 Cntr Q2P13SV2867B 129'-0" Solenoid Valve ASCO NP831654V Cntr (HV2867) i Q2P132S2867B 129 -0" (HV2867) Limit Switch NAMCO EA-740 Curr _

(

i DELETED -

TT11T3zS3197 Limit Switch NAMCO EA-180 Cntr 129'-0" (HV3197) verA m 45bbb 129'-0" Solenoid Valve ASCO NP831654V_ C n tr (HV2866)

Q2P13ZS2866B 129'-0" FAMCO EA 740 Cntr (HV2866) Limit Switch _

Q2E12SV3999A Cntr 89'-4" (HV3999A) Solenoid Valve ASCO NP8316A74E Q2E12ZS3999A NAMCO EA-180 Cntr 89'-4" (HV3999A) Lielt Switch Q2E12SV3999B NP8316A74E CTFT 91'-4" (HV3999B) Solenoid Valve ASCO Q2E122S3999B EA-1BO CT:fr 91'-4" (HV39995) Limit Switch NAMCO Q2E12H001A CT:Tr 155'-0" (H001A) CTMT Cir. Tan Motor .fev Nfa. Co. Tvne ?

Q2E12M301B Cntr 155'-0" (H001B) CTMT Clr. Tan Noter . Tov Mfe. ca. Tvne y Q2E12M001C Cntr 155'-0" (H001C) C1NT Cir. Tan Motor Joy Nft. Co. Tvoe ?

__Q2E12M001D Cm 155,-0o (H001D) C1NT Cir. Tan Motor Joy Mfr. Co. Tvoe P g

General 143'-0" r

Cm

l. Q27525005 Penetration Electrie 100 series b- General Cm 14 3, -0,,

[. Q27523007 Penetration Electrie 103 series General 143'-0" h.

m- Q2T523019 Penetration Electrie 100 series Cntr

... General C n tr 143'-0" 32T525002 Penetration Electrie 100 Series

(

- General Cm M 3, -0,,

N. 02T523006 Penetration Electric 100 Series g

e,, Q2T525041 Penetration General Electric 100 Series Cntr 143'-0" W General Cm 143'-0" A Q27525020 Penetration Electrie 100 Series N

.,y MASTER LIST Secticn C.2.6 2 Sheet 2 Joseph M. Farley Nuclear Plant Unit (CLASS lE ELECTRICAL EOulPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CON CONTAINMENT COOLING AND PURGE E-12. E-14. P-13 SYSTEM: ,

COMPONENTS MANUFACTURER K) DEL LOCATION PLANT ID NUMBER GENERIC NAME BLDG ELEY

.~

Terminal Block States Co. Type ZkH cTMT 129'-0" Q2P13SV3196-B/JB l

- General taq'_q" CT?tT Q2T523022 Penetration Electric 100 Series States Co. Type ZkT cTMT 190'_nn Q2P135V2867B-B/JB Terminal Block States Co. Type ZbT cTur 129'-0" Q2P13SV3197-B/JB Terr inal Block Terminal Block States Co. Type Z'aH CTMT 129'-0" Q2P13SV2866B-B /JB States Co. Type Zk"4 CTNT 118' Q2E12SV3999A-A/JB Terminal Block States Co. Type Zbt CTMT 118' Q2T52B025 Terminal Block Terminal Block States Co. Type Zkt cntr 118' Q2E12Sv39993-B/JB General Penetration Electric 100 Series cntr 143'-0" Q2T52B001 General Penetration Electric 100 Series cver 143' Q2T52B023 2VAFU-R5Q Power Cable Okonite None , enrr Varies i

Okonite None e n rr Varies 2VATU-R53  ::ontrol cable Okonite None CTMr Varies 2VAQ5048F Control Cable en-r None varies 2VXR500$H Control Cable Okonite 2VATU-J40 Power Cable Okonite None cver varies  !

2VATU-J4D Control Cable Okonite None enrr varies Control Cable Okonite None enrr Varies l 2VAQ5009C _

Bosten 2VYR5066B Instruirent Cable Ins. Wire None enrr varies okonite None enrr vnrfac 2VBL500BC.D.K.L Control _ Cables Okonite None CTMT Varies 2VB05010J Control Cable None

_0konite CThrr vnrina 2VYR5035D Contrcl Cable s l

Okottite None CThrr Vnrio=

2VBL5008X. W Control Cables Okonite None CT?rr varies 2VB05012F _ Control Cable Okonite NOD

  • CTMT Varies j 2VYR5035F Control Cable l

Okonite None CTIrr varies 2 vat 5122C Control cable' ,

-\

j eco.ux uso

l MASTER LIST sectien C.2. 6

. 'f , .

i Joseph M. Farley Nuclear Plant Unit 2 , Sheet 3 cf l> (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYShEM: CONTAINMENT COOLING AND PURGE E-12. E-14, P-13

( ., .

COMPONENTS PLANT IL'NU'GER GENERIC NAME MANUFACTURER PODEL LOCATION l

+ -

BLDG ELEV 2VAQ5029E Control Cable Okonite None CTMT Varies

,2VBL5094C Control Cable Okonite None CTirr Varies 2VBQ5029E Control Cable Okonite None CTfrr Varies 2VAED15Q l Power Cable Okonite None CT?T Varies 2VAE3,16Q Power Cable Okonite None CTtfT Varies 2VBEE08Q Power Cable Okonite None CT:fr Varies 2VBEE16Q Power cable Okonite None CTirr varies ij n

J J

e 4

  • f

~

i l 1

1 l

1 i

l l GPD 1374 t/So

. ,.__ . 1.  :- a . --2_

MASTER LIST S2ction C.2.7 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 QCLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

HYDROGEN RECOMBINER SYSTEM E-17 SYSTEM:

COMPONENTS GENERIC NAy2 NANUTACTURER PODEL LOCATION j PLANT ID NUMBER BLDG ELEY Westinghouse Type A 155'-0" Q2E17G001A (K001A) H2 Recombiner Heater CTMT Q2E17G001B (K001B) H2 Recombiner Heater Westinghouse Type'A CTitT 155'-0" oeuesas ,

Q2T52B001 ranetration Electric 100 Series CTitT. 143'-0" General Q2T52B023 Penetration Electric 100 Series CTMT. 143'-0" General Q2T52B024 Penetration Electric 100 Series CTMT. 143'-0" General D

Q2T52B042 Penetration Electric 100 Series CTMT 143'-0" 143'-U' 2VAFALL3T Power Cable Okonite None CTMT & above 14 4 ' -U ' '

2VBFBRH6T Power Cable Okonite None CTllT & above ,

Boston 143'-0" CTMT & above 2VXQ5009B, D. F Instrument Cables Ins. Wire None Boston 143'-0" 2VYQ5017B, D, F Instrume w Cables Ins. Wire None CTMT g ,3nyg 4

'A %

l

.I 4

i i

8' F

i f2S M .111A 1e

MASTER LIST ssetien C.2,8 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 of ICLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITION CONTAI} MENT POST LOCA AIR MIXING SYSTEM E-19 WSTEM:

COMPONENTS MANUFACTURER 10 DEL LOCATION PLANT ID NUMBER GENERIC NAME BLDG ELEV 155'-0" Mixing Fan Motor Joy Mfg. Co. Type P CTMT Q2E19M001A (C001A Q2E19M001B (C001B; Mixing Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" Joy Mfg. Co. Type P CTMT 155'-0" Q2E19M001C (C001C? Mixing Fan Motor Joy Mfg. Co. Type P CTMT 155'-0" Q2E19M001D (C001D? Mixing Fan Motor General Penetration Electric 100 Series CTMT 143'-0" Q2T52B002

. General Penetration Electric 100 Series CTMT 143'-0" Q2T52B014 General Penetration Electric 100 Series CTMT 143'-0" Q2T52B015 General Penetration Electric 100 Series CTMT 143'-0" Q2T52B017 143'-0" Power Cable Okonite None CTMT & above 2VAFA-J5Q 143'-0" Power Cable Okonite None CTMT & above 2VAFA-ISQ 143'-0" Power Cable Okonite None CTMT & above 2VAFA-14Q 143'-0" Power Cable Okonite None CTMT & above 2VAFA-13Q GFD.1374 t/30

~

- -. . - - . . . ~ . - . _ . _ , _

l

  • MASTER LIST Smetion C.2. 9 Joseph M. Farley Nuclear Plant Unit 2 Sheet _, 1 gCLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONSI

' E-21

( STEM: CHEMICAL AND VOLtHE CONTROL / SAFETY INJECTION COMPONEh75 MAh07ACTURER PODEL LOCATION PLANT ID NUMSER GENERIC NAME t

BLDG l ELEY Q2E21V036A 12" Hotor Operated .

111'-6" SMB-4 CT?tT (NOV8088A) Cate Valve Limitorcue Q2E21V038B 12" Motor Operated 112'-6" (MOV80883) Cate Valve Limitoreue s"B-4 r TitT Q2E21V03EC 12" Hotor Operated 113'-6" TAM tereue swa-4 CT'4T (MOV8088C) Cate Valve Q2E21SV8871 NP831654V Cn!T 129'-0" Solenoid Valve ASCO (HV8871) ,

Q2E21Z58871 EA-180 CTMT 129'-0" l (MV8671) Limit Switch NAMCO Q2E21V249A 3" Hotor Operated CTMT 123' Gate Valve Limitoreue EMB-00 (MOV8112) ,

N2E21ZS8149A CniT 111'-0" '

Limit Switch NAMCO EA-180 (HV8149A)

' Q2E21SV8149AB NP831654V CTMT 111'-0"

. (HV8149A) Solenoid Valve ASCO l

N2E212S81495 CTt'T 111'-0" Limit Switch NAMCO EA-180 (HV8149B)

Q2E21SV8149BB NP831654V Cntr 111'-o" (HV8149B) Solenoid Valve ASCO N2E21ZS8149C EA-180 CT?rr 111'-0" (HV8149C) Limit Switch NAMCO '

Q2E21SV8149CB NP831654V CT?iT 111'-o"

,_ (MV8149C) Solenoid Valve ASCO General 100 series CTitt 143'-0" 02T523002 Penetration Electrie General 143'-0" 100 Series rTur Penetration Electric _

Q2T52B016 General Penetration Electric 100 Series CTFn 141'-n" Q2T523006 General Penetration Electric 100 Series crvT tal'-o" __

_.Q2T525038 General Q2T523019 Penetration Electric 100 Series rTvr 143'-0" _

N2E21SV8871-A/JB Junction Box SMS [c ((pe ZWM CDrr 143'-0" EA-180 . J,ntr 111'-6" Q2E212S8808AB Limit Switch NAMCO _

Limit Switch NAMCO E/.-180 CT?rr 112'-6" _

Q2E21SZ8808BB EA-180 CTirr 111' A" Q2E21258808CB Limit Switch NAMCO General .

Q2T525014 Penetration Electric 100 Series enrr 161' n" General 100 Series enrr 143'-0" Penetration Q2T525019 Electric 1(~ States Co. Type ZWM Cnft 116'-0" N2E21SV8149AA-A/J1 Terminal Block States Co. Type ZWM Cntr 116'-0" N2E21SV8149BA-A/J1 Terminal Box _

GFD 13M 1480

  • l MASTER LIST Section C.2.9 l Joseph M. Farley Nuclear Plant Unit 2 Sheet 2 of l (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) 1YSTEM: CHEMICAL AND VOLUME CONTROL / SAFETY INJECTION E-21 l

COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL LOCATION BLDG ELEV 116'-0" N2E21SV8149CA-A/JB Terminal Block States Co. Type ZkH CTMT & above 2VAFU-22Q. Power Cable Okonite None CTMT Varies 2VAFU-Z2D, G Control Cables Okonite None ':TIIT Varies 2VAQS023E Control Cable Okonite None CTMT Varies 2VXKA163B Control Cable Okonite None CTMT Varies 2VBFV-S2Q Power Cable Okonite None CTMT Varies 2VBFV-S2D, G Control Cables Okonite None CTMT Varies 2VBQ5024C Control Cable Okonite None CTMT Varies 2VYKA163B Control Cable Okonite None CTMT Varies 2VAFU-23Q Power Cable Okonite None CDE Varies 2VAFU-23D, G Control Cables Okonite None CTMT Varies 2VAQ5024E Control Cable Okonite None CTMT Varies 2VXA163D Control Cable Okonite None CTMT Varies 2 VAL 5049C Control Cable Okonite None CTMT Varies 2VAQ5022H Control Cable Okonite None CTMT Varies 2VAFU-T4Q Power Cable Okonite None CTMT Varies 2VAFU-T4D Control Cable Okonite None CTMT Varies 2VAQ5018E Control Cable Okonite None CTMT Varies

_2 VAL 5042F Control Cable Okonite None CTMT Varies 2 VAL 5042G Control Cable Okonite None CTMT Varies 2VAQ5022F Control Cable Okonite None CTMT Varies 2 VAL 5043F Control Cable Okonite None CTMT Varies 2 VAL 5043G Control Cable Okonite None CTMT Varies 2VAQ5023C Control Cable Okonite None CTMT Varies 2 VAL 5044F Control Cable Okonite None CTMT Varies GFD 1374 1/00

MASTER LIST Section C.2.9 Joseph M. Farley Nuclear PI:nt Unit 2 Sheet 3 of ICLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: CHEMICAL AND VOLUME CONTROL / SAFETY INJECTION E-21 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL LOCATION BLDG ELEY 2 VAL 5044G Control Cable Ok5 nite None CTMT Varies 2VAQ5024C. Control Cable Okonite None CTMT Varies j

^

l 1

GPD 1374 t/80

MASTER LIST Section C.2.10 Joseph M. Farley Nuclear Plant Unit 2 Sheet i ef (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

REACTOR CAVITY POST LOCA DILUTION SYSTEM E-22 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER EDEL LOCA!!ON BLDG ELEV Q2E22M001A (C001A) Dilution Fan Motor Joy Mfg. Co. Type P CTMT 129'-0" Q2E22M001B (C001B) Dilution Fan Motor Joy Mfg. Co. Type P CTKr 129'-0" Q2E22V001A 2%" Motor Operated (MOV3872A) Cate Valve Limitorque SMB-03 CTMT 130'-0" Q2E22V001B 2%" Motor Operated (MOV3872B) Gate Valve Limitorque SMB-00 CTMT 130'-0" General Q2T52B001 Penetration Electric 100 Series CTMT 143'-0" General Q2TS2B019 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B023 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B020 Penetration Electric 100 Series CTMT 143'-0" 2VAED06Q Power Cable Okonite None CTMT 129'-0" 2VAED06E Control Cable Okonite None CTMT 129'-0" 2VBEE09Q Power Cable Okonite None CTMT 129'-0" 2VBEE09E Control Cable Okonite None CTMT 129'-0" GF D.1374 1/So

MASTER LIST Sectien C.2.11 Joseph M. Farley Nuclear Plant Unit 2 Sheet I cf ICLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: POST ACCIDENT CONTAINMENT COMBUSTIBLE CAS_ CONTROL E-23 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER F0 DEL LOCATION BLDG ELEV 2" Motor Operated .

02E23V021 (MOV3536: Gate Valve Limitorcue SMB-00 CTMT 116'-6" 6" Motor Operated Q2E23V003_(Mov3530: cate Valve Limitoreue SMB-00 CTMT 130'-6" Q2E23V022A 3/4" Motor Operated (MOV3528A) Globe Valve Limitoraue SMB-000 CTMT 126'-6"

_Q2E23V002B 3/4" Notor Operated (MOV3528B) Globe Valve Limitoraue sMB-000 CTMT 126'-6" Q2E23V022C 3/4" Motor Operated (MOV3528C) Globe Valve Limitorcue sMB-000 CTMT 126'-6" Q2E23V022D 3/4" Motor Operated (MOV3528D) Globe Valve Limitoroae SMB-000 CTMT 126'-6" Q2E23V025A 3/4" Motor Operated (MOV3835A) Globe Valve Limitoraue RMR-000 CTMT 126'-6" Q2E23V025B 3/4" Motor Operated  ;

(MOV3835B) Globe Valve Limitoroue SMB-000 CTMT 126'-6" General Q2TS2B005 Penetration Electric 100 Series CTMT 143'-0" I General Q2T52B017 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B007 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B019 Penetration Electric 100 Series CTC 143'-0" General Q2TS2B020 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B038 Penetration Electric 100 series CTMT 143'-0" General Penetration Electric 100 series CTMT 143'-0" Q2T52B016 General Q2T52B015 Penetration Electric .00 Series CTMT 143'-0" 116'-0" 2VAFU-W4Q Power Cable Okonite None CTMT & nbnvn 116'-0" 2VBFU-N20 Power Cable Okonite None CTMT A nhnun 116'-0" 2VAFU-W4C Control Cable Okonite None CTMT & above 116'-0" 2VAED06E Control Cable Okonite None cTyr & above 116'-O" 2VBFV-N2C Control Cable Okonite None CTMT & above 116'-0" 2VBEE09E Control Cable Okonite None CTMT & above -

116'-0" 2VBFV-Y5Q Powar Cable Okonite None CTMr & above 116'-0" 2VBFV-Y5C Control Cable Okonite None CTMT & above 116'-0" 2VBFV-Y4Q Power Cable Okonite None CTMT & above GFD 13741/Bo

MASTER LIST Ssetion C.2.11 Joseph M. Farley Nuclear Plant Unit 2 Sheet 2 of ICLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: POST ACCIDENT CONTAINMENT COMBUSTIBLE _ GAS CONTROL E-23 COMPONENTS PLANT ID NUMBER CENERIC NAME MANUFACTURER MODEL LOCATION BLDG ELEY 116'-U" 2VBFV-YSC Control Cable Okonite None CTMT & abc,ve 116'-0" 2VAFU-L4Q Powar Cable Okonite None CTMr & above 116'-0" Okonite 2VAFU-t5Q Power Cable None CD1T & above 116'-0" 2VBFV-H4Q Powar Cable Okonite None CTMT & above 116'-0" 2VBFV-H5Q Power Cable Okonite None CTMT & above 116'-0" 2VAFU-L4C Control Cable Okonite None CTMT & above 116'-0" 2VAFU-LSC Control Cable Okonite None CTMT & above 116'-0" 2VBFV-H4C Control Cable Okonite None CTMT & above 116'-0" 2VBFV-H5C Control Cable Okonite None CTMT & above 116'-0" 2VAFU-M4Q Power Cable Okonite None CTMT & above 116'-0" 2VBFV-M3Q Power Cable Okonite None CT!!T & above 116'-0" 2VAFU-N4C Control Cable Okonite None CTMT & above 116'-0" 2VBFV-M3C Control Cable Okonite None CTMT & above Gro me uso l

MASTER LIST Soctica C.2.12 Joseph M. F.wley Nuclear Plant Unit 2 Sheet I cf ,

ICLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDEN G-21

.., STEM:

LIQUID WASTE DISPOSAL SYSTEM COMPONENTS MANUFACTURER PODEL l_ LOCATION PLANT ID NUMBER GENERIC NAME BLDG ELEV Q2G21SV3376 NP8316A74E CTMT 109'_o" Solenoid Valve ASCO (HV3376)

Q2G21ZS3376 NAMCO EA-180 CTMT 109'-o" (HV3376) Limit Switch N2G21ZS1003 EA-180 CT'1T 110'-0" (LCV1003) Limit Switch NAMCO N2G21SV1003B ,

206-381-6RF CT:fT 110'-0" (LCV1003) Solenoid Valve ASCO Q2G21SV7126 ASCO NP8316A54E CUTT I17'-0" (HV7126) Solenoid Valve Q2G21ZS7126 NAMCO EA-180 Cntr 117'-0" (HV7126) Limit Switch General Electric 100 Series CnfT 14 3'-0" 02T52B038 Penetration General Electric 100 Series Cnrr 143'-0" 02T52B041 Penetration States Co. Type ZWM Cntr 116'-0" 02G21SV3376-B/JB Terminal Block General Electric 100 Series CTMT 143'-0" 02T523019 Penetration States Co. Type ZWM CT!!T 116'-0" N2G21SV1003A-A/JB Terminal Block States Co. Type ZWM CTMT 116'-0" N2G21SV7126-A /JB Terminal Block 116'-0" Okonite None CTitT & above 2VBL5045C Control Cable 116'-0" None CTI!T & above Control table Okonite 2VB050303 116'-0" Boston Cn!T & above 2VYR5065G Instrument cable Ins. Wire None _

116'-0" None Ct!T & above Control Cable Okonite 2 VAL 5037D 116'-0" Okonite None CTMT & above 2VA050213 Control Cable 116'-0" None CTMT & above Control Cable Okonite

_2 VAL 5036c e

DD 1374 t/m

MASTER UST Section C.2.13 Joseph M. Farley Nuclear Plant Unit 2 Sheet i grtAss IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

NAIN STEAM N-II

.f ' STEM: .

COMPONENTS GENERIC NAME MANUTACTURER )ODEL LOCATION FLANT ID NUMSEK BLDC ELEV Mn. Stm Q2N11253369A .

127'-5',

(HV3369A)' Limit Switch NAMCO EA-180 Room DELET:D .

Q2511SV3369AC Mn. Stmy Solenoid Valve ASCO NP8316E36V annm 135'-0" (EV3369A)

Mn. Stm Q2N112S33693 EA-180 127'-5" Limit Switch NAMCO Room (EV3369B)

DELET ED Q2N11SV3369BC Mn. Stm (HV3369B) Solenoid Valve ASCO NP8316E36V Room 135'-0" Q2N11ZS3369C Mn. Stm (HV3369C) Limit Switch NAMCO EA-180 Room '127'-5" DELET D Mn. Stm Q2N11SV3369CC (HV3369C) Solenoid Valve ASCO NP8316E36V Room 135'-0" 02N112S3370A Mn. Stm V3370A) Limit Switch NAMCO EA-180 Room 127'-5" i DELETED Q2N11SV3370AC

, Mn. Stm' (RV3370A) Solenoid Valve ASCO NP8316E36V Room 135'-0" Q2511253370B Mn. Stm<

(HV3370B) Limit Switch NAMCO EA-180 Room 127'-5" DELE 1ED l Q2N11SV3370BC Mn . S tm-(RV3370B) Solenoid Valve ASCO NP8316E36V Room 11s'-n" Q2N112S3370C Mn. Stm (MV3370C) Limit Switch RAMCO EA-180 Ronm 127'-5" DELE 1 ED Mn. S tm, Q2N11SV3370CC '

Room 13s'-n" (HV3370C) Solenoid Valve ASCO NP_8.3.16.E36V Mn. Stm, Q2N11ZS3368A AMCO EA-_180 Room 111'_7" (Hv3368A) Limit Switch _ _

Mn. Stm.

Q2N11SV3368AA (Rv3368A) Solenoid Valve ASCO NP8321A2V

~~~

Room 131'-7" Mn. Stm Q2N112533688 (RV33688) Limit Switch NAMCO E6-180 _ Room _ J31'-7" _

Q2N11SV3368BA

, Mn. Stm 131'-7" (NV33683) Solenoid Valve ASCO NP8321A2V Room _

Q2N11253368C Mn. Stm (Rv336BC) Limit Switch NAMCO EA-1Rn Room 131'-7" Q2N11SV3368CA Mn. Stm l Room 131'-7" (Rv3368C) Solenoid Yalve ASCO NP8321A2V Q4n113VJV7hA Mn. Stmi (RV3976A) Solecoid Valve ASCO NP8321A2V Room 131'-7" 09D 131418

- ~ ~ .

MASTER UST Ssetion C.2.13 Joseph M. Farley Nuclear Plant Unit 2 Short 2 _

frLASE If ELECTRICAL EOulPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

, ' gygg.

  • MAIN STEAM N-11 COMPONENTS FLANT ID NUMBER GENERIC NAME MANUTACTURER IODEL LOCATION BLDG ELEV Q2N11IS3976A Mn. Stm EA-180 131'-7" (HV3976A') Limit Switch NAMCO pong c Q2N11SV3976B Mn. Stm (HV3976B) Solenoid valve ASCO NP8321A2V ann, 131'-7" Q2N112S3976B Mn. Stm (HV3976B) Limit Switch NAMCO EA-180 Room i 131'-7" Q2N11SV3976C Mn. Stm (HV3976C) Solenoid valve ASCO NP8321A2V Room 131'-7" Q2N11253976C Mn. Stm (HV3976C) Limit Switch NAMCO . EA-180 Room 131'-7" Mn. Stm Q2N11SV3369AA-A/JB Teminal Block States Co. Type ZLH Room 131'-0" Mn. Stm Q2N11SV3369BA-A/JB Teminal Block States Co. Type ZLH Rnnn 131'-0" Mn. Stm Q2N11SV3369CA-A/JB Teminal Block States Co. Type Z%M nnn, 131'-0" Mn. Stm Q2N11SV3370AA-B/JB Teminal Block States Co. Type Zkt Room 137'-0" Mn. Stm Q2N11SV3370BA-B/JB Terminal Block States Co. Type ZLH Room 137'-0" Mn. Stm ,

Q2N11SV3370CA-B/JB Terminal Block States Co. Type ZhH 'Roon 137'-0" i

J l

l Mn. Sto Q2N11SV3368AA-A/JB Terminal Block States Co. Tyne 2WM Room 137'-0" Mn. Scm Q2N11SV3368BA-A/JB Terminal Block States Co. Twee m Room .137'-0"

. Mn. Sto Q2N11SV3368CA-A/JB Terminal Block States Co. Twne m Room .137'-0" Mn. Str 02N11EV3976B-E/JE Terminal Block States Co. Tyne 2WM Roon 137'-0" _

Mn. Str l

Q2N11573976C-3/JB Teriminal Block States Co. Type EUM '

Room 197'-n" Mn. Str 135'

( 2 VAL 5019E F Control Cables Okonite None Room & nbove

/ Mn. Stn 135' 2 VAL 5045C Control Cable Okonita None Room .& above _

Mn.Sn 135" 2VAQ5013A Control Cable Okomite Bone . Room ,& above

~

eco un uso

MASTER LIST Saction C.2.13 Joseph M. Fart:y Nuclear Plant Unit 2 Sheet 3 cf ICLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: MAIN STEAM N-11 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER FODEL LOCATION BLDG ELEV Mn. Stm 127'-5" 2 VAT 0001C, D, E Control Cable Okonite None Room & above Mn. Stm 127'-5" 2 VAL 5020E, F Control Cable Okonite None Room & above Mn. Stm 127'-5" 2 VAL 5046C Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VAQ5015A Control Cable Okonite None Room & above Mn. Stm 127'-5" 2 VAL 5021E, F Control Cable Okonite None Room & above Mn. Stm 127'-5" 2 VAL 5047C Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VAQ5017A Control Cable Okonite None Room & above Mn, Stm 127'-5" 2VBL5010E, D Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBL5021C Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBQ5013D Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBT0001F, G, H Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBL5011E, D Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBL5022C Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBQS015D Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBL5012E, D Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBL5023C Control Cable Okonite None Room & above Mn. Stm 127'-5" 2VBQ5017E Control Cable Okonite None Room & above Mn. Str 127'-5" 2 VAL 5045B Control Cable Okonite None Room & above Mn. Stu 127'-5" 2VAQ5013B Control Cable Okonite None Room & above Mn. Str 127'-5" 2VXR5008A Control Cable Okonite None Room & nbovo Mn. Str 127'-5" 2 VAL 5046B Control Cable Okonite None Room & nbove Mn. Str 127'-5" 2VAQ5015B Control Cable Okonite None Room & nbnve Mn. Stu 127'-5" 2VXR5008B Control Cable Okonite None Room & nbove Mn. Stu 127'-5" 2 VAL 5047B Control Cable Okonite None Room & above Mn. Stu 127'-5" 2VAQ5017B Control Cable Okonite None Room & above GFD.1374 IISo

MASTER LIST Section C.2.13 Joseph M. Farley Nucl:ar Plant Unit 2 Sheet t of (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

SYSTEM: MAIN STEAM N-11 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER PODEL LOCATION BLDG ELEV Mn. Stm 127'-0" 2VXR5008C Control Cable Okonite None Room & above Mn. Stm 127'-0" 2VBL5021B Control Cable Okonite None Room & above Mn. Stm 127'-0" 2VBQ5013E Control Cable Okonite None Room & above Mn. Stm 127'-0" 2VBL5022B Control Cable Okonite None Room & above Mn. Stm 127'-0" 2VBQ5015E Control Cable Okonite None Room & above Mn. Str 127'-0" 2VBL5023B Control Cable Okonite None Room & above Mn. Str 127'-0" 2VBQ5017F Control Cable Okonite None Room & above Q2N11LT477 Level Transmitter Barton 764 CTMT 116'-0" Q2N11LT487 Level Transmitter Barton 764 CTMT 116'-0" Q2N11LT497 Level Transmitter Barton 764 CTMT 116'-0" General Q2T52B040 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B041 Penetration Electric 100 Series CTMT 143'-0" Boston 2VXV5013L _

, Instrument Cable Ins. Wire None CTMT 116'-0" Boston 2VXV5014H, J Instrument Cable Ins. Wire None CTMT 116'-0" Mn. S tt:

Q2N11SV3976A-B/JB Terminal Block States Co. Type ZWM Room 137'-0" l

l 1

i l

GPD 1374 t/k)

C2 ASTER LIST Soction C.2.14 Joseph M. Farley Nuclest Plant Unit 2 Sheet i OCLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

, , .EM . AUXILIARY STEAM N-12 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUTACTURER EDEL LOCATION BLDG ELEV Q2N12SV3234A .

Mn. Stm (HV3234A) Solenoid Valve ASCO NP8320A186V Room 135'-0" Q2N12ZS3234A Mn. Stm (HV3434A) Lielt Switch NAwCO FA-180 Room i ' 134'-0" Q2N12SV3234B Mn. Stm (MV3234B) Solenoid Valve AECO NP R'490 A l p *W Room 135'-0" Q2N122S3234B Mn. Stm  ;

(MV3234?) Lielt Switch NAMCO EA-180 Room ~ 134'-0" Q2N12SV3235A Mn. Stm' (HV3235A) Solenoid Valve ASCO NP8321A2V _' Roon 135'-0" l Q2N12ZS3235A Mn. Stm (Hv3235A) Limit Switch NAMCO EA-180 Room 140'-0" Q2N12SV3235B Mn. Stm (HV3235B) Solenoid Valve ASCO _

NP8321A2V Rnom l '4 5 ' -0" Q2N12ZS3235B Mn. Stm (Hv3235B) Limit Switch NAMCO EA-180 Room 140'-0" Mn. Stm 135'-0" Q2N12SV3234A-A/JB Terminal Block States Co. Type ZWM Roon & above Mn. Stm 135'-0" Q2N12SV32343-B/JB Terminal Block States Co. Tvoe ZWM Roon & above i Mn. Stu 135'-0" Q2N12SV3235A-A/JB Terminal Block States Co. Tvoe ZWM Room & above Mn. Stm 135'-0" Q2N12SV3235B-B/JB Terminal Block States Co. Type ZVM Room & above Mn. Stm 135'-0" 2 VAL 5003B Control Cable Okonite None Roon & above Mn. Stm 135'-0" i 2VAQ5011A Control Cable Okonite None Room & nhnvn Mn. Stm 135'-0" 2VXR5007F Control Cable Okonite None Room A nhnen Mn Stm 135'-0" 2VBL5007B Control cable Okonite None Ronn & above Mn. Sto 135'-0" 2VB050135 . Control Cable Okonite None p n n., & nhnen un. Sto 135'-0" 2VTR5033E Control Cable Okonite Mene Room & nhnen Mn. Stm 135'-0" 2 VAL 5004C Control Cable Oksnite wnn. Roon & above Mn. Stm 135'-0" 2VAQ5010D Control Cable Okonite None Roon & nhnvo Soston Mn. Stm 135'-0" 2VNR5003A,B Instrument Cables Ins. Wire Nnne Room & nhnvn Mn. Stm 135'-0" <

275L5005C Control Cable Okonite None Room K ,hnen Mn. Stm 135'-0" 2VBQ50115 Control Cable Okonite None Room & above i i Mn. Stm 135'-0" 2VIKJ183C, D G. N Control Cables Okonite None Room & above _

GPD 13741m

~. _ - . .. .-.-.. ... . ..

~

MASTER LIST Secticn C.2.15 2 Sheet I cf Joseph M. Farley Nuclear PI:nt Unit (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT N-21 YSTEM.

MAIN FEEDWATER AND CONDENSATE COMPONENTS MANUFACTURER PODEL LOCATION PLANT ID NUMSER GENERIC NAME BLDG ELEY Mn. Sem Q2N21V001A-B 14" Motor Operated .

Room 140'-0" Limitoroue MMR-laT (MOV3232Ai StoD-Check Globe V1 Mn. Stm Q2N21V001B-B 14" Motor Operated Room 140'-0" Stop-Check Globe VI Limitoraue SMB-4T

__( Mov3212in Mn. Stm Q2N21V001C-B 14" Motor Operated 140'-0" Stop-Check Globe VI Limitorcue SMB-4T Room (MOV3232C) Mn. Stm Cems LS-36497 Room 133'-5" Q2N21LSH2828A Level Switch Mn. Stm LS-36497 Room 133'-5" Q2N21LSH2828B Level Switch Gems Mn. Stm LS-36497 Room 133'-5" Q2N21.LSH2828C Level Switch Gems Mn. Stm LS-36497 Room 133'-5" Q2N21LSH2829A Level Switch Gems Mn. Stm LS-36497 Room 133'-5" Q2N21LSH2829B Level Switch Gems Un. Stm LS-36497 Room 133'-5" Q2N21LSH2829C Level Switch Gems Mn. Stm Terminal Block States Co. Tvoe ZWM Room 135'-0" A2TB034 Mn. Stm 133'-0" Okonite None Room & abova 2 VAL 5120A,B,C,D Control Cable 133'-0" Mn. Stm None Room & above 2VBL5092A, B, C Control Cable Okonite Mn. Stm 133'-0" Okonite None Room & above 2VBFV-K2Q Power Cable Mn. Stm 133'-0" Okonite None Room & above 2VBFV-K3Q Power Cable .

Mn. Stm 133'-0" Okonite None Room & above 2VBFV-L2Q Fowar Cable Pn. St. 133'-0" Okonite None Rnnm & above 2VBFV-K2A Control Cable 133'-0" Mn. Stm Okonite None nnnm & above 2VBFV-K3A Control Cable 133'-0" Mn. Stm Nnne nnnm & above 2VBFV-L2A Control Cable Okonite a

'OPD 1374 IISo

MASTER LIST Ssetien C.2.16 Joseph M. ForI;y Nuclear Plant Unit 2 Sheet 1 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

ATEM. AUXILIARY FEEDWATER N-23 COMPONENTS PLANT ID NU12ER GENERIC NAME MANUFACTURER PODEL LOCATION BLDG ELEV Q2N23V011A 4" Motor Operated . Mn. Stm (MOV3350A) Stop-Check Globe VI Limitorcue SMB-1 Room 137'-5" Q2N23V001B 4" Motor Operated Mn. Stm (MOV3350B)- Stop-Check Globe VI Limitorcue SMB-1 Room 137'-5" Q2N23V001C 4" Motor Operated Mn. Stm

_,(MOV3350C) Stoo-Check Globe V1 Limitorcue SMB-1 Room 137' _5" Q2N23ZS3228A Mn. Stm

_(HV3228A) Limit Switch NAMCO EA 180 Room 135'-0" Q2N23SV3228AA Mn. Stm (HV3228A) Solenoid Valve ASCO. NP8320A186V Room 135'-0" Q2N23ZS3228B Mn. Stm

_(HV3228B) Limit Switch NAMCO EA 180 Room 135'-0" Q2N235V3228BA Mn. Stm (HV3228B) Solenoid Valve ASCO _ NP8320A186V Room 135'-0" Q2N23ZS3228C Mn. Stm (HV3228C) Limit Switch NAMCO EA 180 Room 135'-0" Q2N23SV3228CA Mn. Stm

_ (HV3228C) Solenoid Valve ASCO WP8320A168V Room 135'-0" Q2N23ZS3227A Mn. Stm (HV3227A) Limit Switch NAMCO EA 180 Room 135'-0" l Q2N23SV3227AA Mn. Stm (HV3227A) Solenoid Valve ASCO NP8320A168V Rocm 135'-0" Q2N23ZS3227B Mn. Stm .

(HV32278) Lie:it Suitch NAMCO EA- 180 Room 135'-0" Q2N23SV3227BA Mn. Stn (HV3227B) Solenoid Valve ASCO NP8320A168V Room 135'-0" Q2N23ZS3227C Mn. Stm (HV3227C) Limit Switch NAMCO EA.180 Room 135'-0" Q2N23SV3227CA Mn. Stm (HV3227C) Solenoid Valve ASCO NP8320A168V Room 135'-0" Mn. Stm Q2N23SV3228AA-A /JB Terminal Block States Co. Tyne ZWM Room 144'-0" Mn. Stm Q2N23SV3228BA-A/JB Terminal Block States Co. Tvne 7vu Room 144'-0" Mn. Stm l Q2N23SV3228CA-A/JB Terminal Block States Co. Type ZWM Room 144'-0" Mn. Stm 1 07N23Sv3227AA-A /JB Terminal Block States Co. Tvoe ZWM Room 144'-0" Mn. Stm 02N23Sv3227BA-A/JB Terminal Block States Co. Tvoe ZWM Room 144'-0" Mn. Stm 02N235V322 7CA-A/JB Terminal Block States Co. Tvoe ZWM Room 144'-0" Mn. Ste 135'-0" 2VAFU-U40 Power Cable Okonite None Room & above Mn. Ste 135'-0" 2VATU-U50 Fever Cable Okonite None Room & above s Mn. Stm 135'-0" 2VAFU-120 Power Cable Okontre won, Room & above iMn. Str 135'-0" 2VAFU-U4A, D Control Cables Okonite None IRoom & above l aro. san stao l

MASTER LIST Ssetion C.'.16 Joseph M. Farl;y Nuclear Plant Unit 2 Sheet 2 cf (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)

AUXILIARY FEEDWATER N-23

'YSTEM:

COMPONENTS PLANT ID NUMBER GENERIC NAME MANUTACTURER 10 DEL LOCATION BLDG ELEY Mn. Stm 135'-0" 2VAFU-USA, D Control Cables Ok'onite None Room & above Mn. Stm 135'-0" ,

2VAF -12A, D Control Cables Okonite None Room & above l Mn. Stm 135'-0" 2 VAL 5007B Control Cable Okonite None Roon & above Mn. Stm 135'-0" 2 VAL 5008B Control Cable Okonite None Roon & above Mn. Stm 135'-0" 2 VAL 5009B Control Cable Okonite None Ronn & above Boston :in. Stm 135'-0" 2 VAL 5007C Instrument Cab 1w Ins. Wire None Ronn & above Boston  !!n. Stm 135'-0" 2 VAL 5008C Instrument Cable Ins. Wire None tonn & above Boston Mn. Stm 135'-0" l 2 VAL 5009C Instrument Cables Ins. Wire None Ronm & above Mn. Stm 135'-0" 2VAQ5010E, K Control Cables Okonite None Re m & above Ma. Sta 135'-0" 2VAQ5012E, K Control Cables Okonite None n n n,, & above Mn. Stm 135'-0" 2VAQ5014E, K Control Cables Okonite None Ronn & above Mn. Stm 135'-0" 2VXR5007K, L, M Control Cables Okonite None Room & above Mn. Stm 135'-0" 2 VAL 5013C Control Cable Okonite None Room & above Mn. Stm 135'-0" 2 VAL 5014C Control Cable Okonite None Roon & above Mn. Stm 135'-0" 2 VAL 5015C Control Cable Okonite None Foom & above Baston Sin. Stm 135'-0" 2 VAL 5013D Instrument Cable Ins. Wire Nnne Room & above Boston 'in. Stm 135'-0" 2 VAL 5014D Instrument Cable Ins. Wire None Roon 6 above Boston Mn. Stm 135'-0" 2 VAL 5011D Instrument Cable Ins. Wire None ___ Roon & above fin. Stm 135'-0" 2VAQ5048H. K Control Cables Okonite Nnne Rnnn & nhnvn fin. Stm 135'-0" i 2VAQ5006C, H Control Cables Okonite None a n n.,, & nhnun fin. Stm 135'-0" 2VAQ5008C, H Control Cables Okonite None ann, x nhnyn l 'in. Stm 135'-0" i 2VKR5007G, H, J Control Cables Okonite None Room & above l

(

GPD.1374 1/00

- - ._..___-____._____l

....a~ .

.e ...n M ASTER UST S2etion C.2.17 ~

Sheet I 2

5owph M. Farley Nuclear Plant Unit _

T O $1 N: LASS lE ELECTRICAL EOUIPMENT REQUIREDW-25 TO FUNCTION U

( CHEMICAL IN.T.ECTION SYSTD1 '

, SYSTEM. _

(.

COMPOhTNTS IODEL .. LOCATION MANUFACTURER -

BLDG l ELEV GENERIC NAME PLANT ID NU)SER Mn, Stm t

Room 141'-6"

~

Q 2N25SV3772A ASCO NP8316A74V Solenoid Valve . Mn. Stm , ,

(HV3772A) Room

~ Q2N25?.S3772A WAvo FA.180 13mit softeh Mn. Stm (HV3772A) Room 141'-6"

%2h45SVJ772B ASCO NP8316A74V (HV3772B)

Solenoid Valve Mn. Stm Room 141'-6"

-Q2N25ZS3772B NAMCO EA-180 (HV3772B)

Limit Switch Mn. Stm Room 141'-6" Q2N25SV3772C ASCO NP8316A74V (HV3772C)

Solenoid Valve Mn Stm Room 141'-6" Q2h45ZS37/4C NAMCO EA-180 (HV3772C)

Limit Switch Mn. Stm

^

Type ZWM Room 139'-0" Terminal Block States Co. 11n. Sto Q2N25S ..~ 7'L772A-A/JB 139'-0" Type ZWM Room Terminal Block States Co. Mn. Stm Q2N25SV3772B-A/JB

~~ 139'-0"

~

Type ZWM Room Terminal Block States Co.

Q2F'!55V3772C-A/JB Pn. Str t w -o

Room & above Okonite None 2 VAL 5076A Control Cable Mn. Str 139'-0" None Room & above Control Cable Okonite Mn, Str 139'-O" l 2 VAL 5077A None Room & above Control Cable Okonite 2 VAL 5078A Mn. Str 139'-0" None Room & above Control Cable Okonite 2VAQ5030E Mn. Str 139'-0" Okonite None Room _ & above _

2VAQ5031E Control Cable Mn. Str 139'-0" Room '& above None

~

$ control cable Okonite ,j

  • 2VAQ5032E Mn. Str 139'-0" Room & above t None Control Cable Okonite

- 2VXR50083, N, J i

-l

} .

J _

t' s N c<(

~

RIASTER UST Saetion C.2.18 2 Sheet 1 Joseph M. Farley Nuclear Plant Unit 8P'

( JYSTEM: ( ASE lE ELECTRICAL SAMPLDIG SYS1EM EQUlPMENT REQUIRED y-15 TO PUN

  • COMPONENTS GENERIC MAME MANUTACTURER EDEL LOCATION Pl. ANT. ID NUMBER
  • BLDG Ela' 129'-0" Q2P155V3103 NP8320A184V Cntr (HV3103)' Solenoid valve ASCO Q2P15253103 EA-180 crrr 129'-0" (HV3103) Limit Switch NAMCO Q2P155V3765 ' '

NP8320A184V cT v r' 129'-0" (HV3765) Solenoid Valve ASCO 65 Limit Switch MAMCO EA-180 rM 129'-0" Q2P155V3766 ASCO MPRMO A1 Rav CTMT 129'-0" (HV3766) Solenoid Valve Q2P15ZS3766 CntT 129'-0" Licit Switch NAMCO EA-180 (MV3766)

I Q2P155V3179A NP8320 A184V CD1T 129'-n" (HV3179A) Solen'oid Valwe ASCO

'Q2P15ZS3179A CUfT Limit Switch NAMCO EA-180 129'_o" (HV3179A)

Q2P155V3179B

  • NP8320A184V CUrr 129'-0" l i (HV3179B) Solenoid Valve ASCO Q2P15ZS3179B EA-180 CDrr 129'-0" r I I iRV3179B) Limit Switch NAMC0 I l Q2P155V3179C NP8320A184V Cntr 129'-0" '

(HV3179C) Solenoid valve ASCO Q2P15ZS3179C CntT 129'-0" (uv3179C) Limit Switch RANCO EA-180 l

-Q2P15Sv3180A 'wpRu nA1R&V cUrr 129'-0"

- -e (BV3180A) Solenoid valve ASCO l 12P15ZS3180A 129'-0" (EV3180A) Limit Switch RANCO -

EA-180 Cntr Q2P155V31805

  • NP8320A184V CRIT 129'-0" tuv31805) Solenoid Valve ASCO Q2P15ZS3180B CD'T 129'_cu tuv31805) Limit Switch NAMCO EA-180 ,

Q2P15SV3180C CTMT 129'-0" l Selenoid valve ASCO '

NP8320A184V t (Rv3180C) 5 Q2P15ZS3180C '

EA-180 Cntr 190'_n" (nv3180C) Limit Switch RANCO k Q2P15SV3181A ASCO '

NP8MOA1 R4v Cntr 129'-0" tuv3181A) Solenoid valve

) Q2715ES3181A 129'-0" Limit Switch NAMCO EA-180 Cntr inv3181A)

Q2P158V31813 NP8320A184V Cntr 129'-0" tav3181B) Solenoid Valve * *NJ Q2715ZS31813 enrr 129'-0" (B73181B) Li=it Switch RANCO EA-180

(%

Q2P155V3181C 129'-9" inv3181C) Solenoid Valve ASCO -- '

NP8320A184V \ cnfr Q2P15ES3181C 129'-0" Limit Switch RAE0 EA-180 CTMT tuv3181C)

Q2P15sV3106 '

129,-0,,

(EV3106) Solenoid Talve ASCO 1rP8320A184V hT .

9 0 1374 1 m

MASTER LIST Saction C. 2.18 Joseph M. Farley Nucinr Plant Unit 2 Sheet 2 _of (class IE ELECTRICAL EOUiPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDIT80NS)

SYSTEM: SAMPLING SYSTEM p.13 COMPONENTS PLANT ID NUMBER GENERIC NAME M/W/ACTURER }0 DEL LOCATION

~

BLDG ELEV Q2P15ZS3104 (HV3104) Limit Switch NAMCo EA-180 CTMT 129'-0" General Q2T52B019 -

Penetration Electeic 100 Series CTMT 143'-0" Q2P15SV3103-A/JB Terminal Block States CA Type ZWM CTMT 135'-9" Q2P15SV3765-A/JB Junction Box _,_. Ctate. T. Tyree ZW CTMT 135'-0" Ganeri; Q2T52B007 Penetration _ Electrs,. 103 Series CTMT 143'-0" Q2P15SV3766-A/JB Terminal Block ,

States Co. Type ZWM CTMT 135'-9" Q2P15SV3179A-A/JB Terminal Block States Co. Type ZW CTMT 135'-9" Q2P15SV3179B-A/JB Terminal Block States Co. Type ZW.n CTMT 135'-9" Q2P15SV3179C-B/JB Terminal Block States Co. Type ZWM CTMT 135'-9" General Q2T52B020 Penetration Electric 100 Series CTMT 143'-0" Q2P155V3180A-A /JB Terminal Block States Co. Type ZWM CTMT 135'-9" Q2P15SV3180B-A/JB Terminal Block States Co. Type ZWM CTMT 135'-9" Q2P15SV3180C-B/JB Terminal Block States Co. Type ZWM Cn!T 135'-9" Q2P15SV3181A-A/JB Terminal Block States Co. Type ZWM CTMT 135'-9" Q2P15SV3181B-A/JB Terminal Block States Co. Type ZWM CTMT 135'-9" Q2P15SV3181C-A/JB Terminal Block States Cc. Type ZWM CTMT 135'-9" Q2P15SV3104-A/JJ Terminal Block States Co. Tvoe ZWM CTMT 135'-9" 129'-0" 2 VAL 5063B Control Cable Okonite None CTMT & above 129'-0" 2VA05049H Control Cable Okonite None CTMT & above 129'-0" 2VXR5010B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5065B Control Cable Okonite None CTMT & above 129'-0" 2VA05032J Control Cable Okonite None CTMT & above 129'-0" 2VXR5010F Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5066A Control Cable Okonite None CTMT & above 129'-0" Control Cable Okonite None CTMT & above 2VAQ5033J oro.tna trao ,

' \

l MASTER LIST Ssetien C.2.18 I Joseph M. Farley Nucl;ar Pl;nt Unit 2 Sheet 3 cf (CLASS lE ELECTRICAL EQUIPMENT REQUIREis TO FUNCTION UNDER POSTULATED ACCIDENT CSNDITIONS)

SAMPLING SYSTEM P-15 SYSTEM:

COMPONENTS GENERIC NAME MANUFACTURER 10 DEL LOCATION PLANT ID NUMBER BLDG ELEV 129'-0" 2VXR5010H Control Cable Oko' nite None CTMT & above 129'-0" 2 VAL 5034B . Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5085B Control Cable Okonite None CTMT & above 129'-0" 2VBL5074B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5086B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5087B Control Cable Okonite None CTMT & above 129'-0" 2VBL5075B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5088B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5089B Control Cable Okonite None CTMT & above 129'-0" 2VBL5076B Control Cable Okonite None CTMT & above 129'-0" 2 VAL 5064B Control Cable Okonite None CTMT & above 129'-0" Control Cable Okonite None CTMT & above 2VAQ5047H 129'-0" 2VXR5010D Control Cable Okonite None CTMT & above l

l l

l l

l 4

4 GPD 1374 IISO

MASTER LIST Joseph M. Farl;y Nuclear PI:nt Unit 2 Sseticn C.2.19 Sheet I cf ICLASS IE ELECTRICAL EQUlPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) iYSTEM. SERVICE WATER P-16 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER }ODEL LOCATION BLDG ELEV Q2P16V207A 10" Motor Operated ,

(MOV3441A) Cate Valve Limitorque SMB-00 CTMT 130'-0" Q2P16V207B 10" Notcr Operated (Mov3441B) Cate Valve Limitorque SMB-00 CTMT 130'-0" Q2P16V207C 10" Motor Operated (MOV3441C) Cate Valve Limitorque SMB-00 CTMT 130'-0" Q2P16V207D 10" Motor Operated (MOV3441D) Cate Valve Limitorque SMB-00 CTMT 130'-0" Q2P16V081 6" Motor Operated e (MOV3131) Gate Valve Limitorque SMB-00 CTMT 130'-0" General Q2T52B005 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B015 Penetration Electric 100 Series CTMT 143'-0" General Q2TS2B007 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B020 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B014 Penetration Electric 100 Series CTMT 143'-0" General Q2T52B019 Penetration Electric 100 Series CTMT 143'-0" 130'-0" 2VBFV-J4Q Power Cable Okonite None CT}E & above 130'-0" 2VBFV-J4D Control Cable Okonite None CTMT & above 130'-0" 2VBQ5007D Control Cable Okonite None CTMT & above 2VYR4006B, D 130'-0" Control Cables Okonite None CTMT & above 130'-0" 2VYKB164B, C Control Cables Okonite None CTMT & above 130'-0" 2VBFV-J5Q Power Cable Okonite None CTMT & nhnve 130'-0" 2VBFV-JSD Control Cable Okonite None CTSn' A nhnun 130'-0" 2VBQ5009D Control Cable Okonite None CT?n' & above 130'-0"

, 2 VAFU-K6Q Power Cable Okonite None CTMT & above 130'-0" l 2VAFU-K6D Control Cable Okonite None CTMT & above 130'-U" 2VA05007D control Cable Okonite None cTMT & above 130'-0" 2VKR5005B, D, F Control Cables Okonite None cTMT & above 130'-0" 2VXKB164B, C Control Cables Okonite None CTMT & above 130'-0" 2VAPG-W2Q Power Cable Okonite None CTMT & above 1

GFD.1374 Hao '

MASTER LIST ssetien C.2.19 Joseph M. Farl;y Nuclear PI:nt Unit 2 Sheet 2 Cf (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) iYSTEM, SERVICE WATER p.16 COMPONENTS PLANT ID NUMLER GENERIC NAME MANUFACTURER }0 DEL LOCATION BLDG ELEV

. 130'-0" 2VAFU-W2D Control Cable Okonite None CTMT & above 130'-0" 2VAFU-H4Q - Power Cable Okonite None CTMT & above 130'-0" 2VAFU-H4A Control Cable Okonite None CTMT & above 130'-0" 2VAQ5002F Control Cable Okonite None CTMT & above m

l l GFD.1374 1/So

w s -

Joseph M. Farley Nuclear Plant Unit 2 ,

$heet m uuturw.

1 me tcLAS$ IE ELECT.7tCAL EQUIPMENT (!EQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITl3NS)

SYSTEM: COMPONENT C00LINC WATER P-17 COMPONENTS PLANT ID NUMBER GENERIC NAME MANUFACTURER PODEL LOCATION BLDG ELEY Q2P17V097 6" Motor operated ,

(MOV3046) Gate Valve Limitorque SMB-00 CTMY 130'-6" Q2P175V3184 ,

(HV3184) Solenoid Valve ASCO NP8316A77V CTMT 11R'-0" Q2P17ZS3184 (HV3184) Limit Switch NAMCO EA-180 CTMT 118'-0" Q2P175V3443

__(HV3443) Solenoid Valve ASCO NP8316A74V CTMT 129'-0"

'Q2P17ZS3443 (HV3443) Lir.it Switch NAMCO EA-180 CTMT 129'-0" General Q2T523016 Penetration Electric 100 Series CTMT 143'-0" General Q2T525038 Penetration Electric 100 Series CTMT 143'-0" General Q2T525020 Penetration. Electric 100 Series CTMT 143'-0" Q2P175V3184-B/JB Terminal Block States Co. Type ZWM CTMT 118'-0" General Q2752B019 Penetration Electrie 100 Series CTMT 143'-0" General

_Q2T52B041 Penetration Electric 100 Series CTMT 143'-0" .

Q2P17SV3443-A /JB Terminal Block States Co. Type ZWM CTMT 129'-0" 118'-0" 1 2VBFV-C3Q Power Cable Okonite None CTMT & above 118'-0" ,

2VBFV-C3D Control Cable Okonite None CTMT & above 118'-o" 2VB05017C Control cable Okonite None CTMT & above 118'-0" 2VYR5006T Control Cable Okonite None CTMT & above 118'-0" 2VBL5009C.D.E F Control Cables Okonite None CD1T & above 118'-0" 2VB05017H Control Cable Okonite None CntT & above 118'-0" 2VYR5035B Control Cable Okonite None CTMT & above _

118'-0" 2VA13055C Control Cable Okonite None CTMT & above 118'-0" 2VA05020H control cable Okonite None CTMT & above 118'-0" <

2VY15064F r'ae rn1 Cable Okonite None CTMT & above i

ibPD 13?a tm L__ _ . ..

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