Text

Environ Qualification of Safety-Related Electrical Equipment, Revision 2
	ML19350E269
Person / Time
Site:	Palisades
Issue date:	06/11/1981
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18046A721	List: ML18046A720; ML19350E269;
References
	NUDOCS 8106170222
	Download: ML19350E269 (226)
	v • d • e

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NJ Environmental Qualification of Safety-Related Electrical Equipment Table of Contents I. Introduction and Background II. Environments A. Hosti'e Areas

-B. Location of Hostile Areas C. Location of Equipment D. Details of the Environment III. Equipment A. Development of List of Equipment B. Time Needed Arguments C. Equipment Needed Ta Mitigate MSLB Outside Containment D. Equiment Used for Monitoring Only E. New Equipment Scheduled for Installation as a Result of TMI-Required Modifications Appendix I - Qualification Work Sheets and Summaries Appendix II - DOR Guideline Definitions Appendix III - Deleted i

Appendix IV - Computer Output Listing of Equipment Found in Hostile Areas 1

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i ) i SECTION I INTRODUCTION AND BACKGROUND Consumers Power Company (CP Co) was requested to address the Environmental Qualification of Safety-Related Electrical Equipment for Palisades Plant by NRC letter dated December 23, 1977. Information requested included identification cf electrical equipment required to perfore safety functions while subjected to design basis' accident environments, definitions of environmental service conditions a'. equipment locations and status of environmental qualification documentation. In response to this request, CP Co provided information via submittal litters dated February 24, 1978, April 6, 1978, April 12, 1978 and November 30, 1978.

A site visit to the Palisades Plant was conducted by representatives of the NRC and their contractor, Franklin Research Center, on January 21-25, 1980.

In this visit, Class lE systems and components were inspected, Plant operating procedures were discussed with Plant personnel and available qualification documentation was reviewed.

The NRC letter of February 15, 1980 formally transmitted to CP Co two sets of the NRC Guidelines referenced below and requested that a meeting be held with the SEP plant licensees on February 21 to discuss these guidelines. The NRC letters of March 6, 1980 and March 28, 1980 provided further direction -

('~g including schedules. Although the review of equipment environmental qualification for Palisades was initiated prior to the February 21, 1980

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meeting, it was the NRC intention that the review be conducted with the same

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guidelines and procedures established for the other SEP plants. (The NRC stated in the February 21 meeting and the March 6 a-d 28 letters that the Palisades information should be brought to the level of the other SEP plant submittals.)

Enclosure 2 of the NRC March 6, 1980 letter to all SEP licensees defined five categories of information that must be submitted under the SEP qualification program. CP Co was requested to submit (for the Palisades Plant) the information required in these categories:

1. Provide the list of safety-related systems addressed in Reference 2. The emergency procedures have already been provided and need not be I resubmitted.

2. Definitien of hostile service conditions is being addressed separately in accordance with our March 28, 1980 letter and need not be addressed in this submittal except as needed to complete Category 4

3. Provide the identification and justification of equipment considered qualified by experience in accordance with Reference 1, Section 4.3.3, Areas Normally Maintained at Room Conditions.

I 4 Provide the tabulation of safety-related equipment located in a hostile environment, with identification of the service conditions and 7-~

b nul080-0052a-43

2 qualification testing for each, in the format used for SEP Topic III-12 submittals.

5. Provide the list of equipment in the tabulation of Category 4 that is not qualified in accordance with the specific requirements of Reference 1 together with justification for the deviations from the guidelines.

For guidance in preparing the requested material, the NRC provided three enclosures reflecting reviews performed during the Palisades Plant site visit during January 21-25, 1980. The enclosures were entitled:

1. Palisades Nuclear Plant Systems Needed for ?!itigation of >!ain Steam Line or Feedwater Line Breaks Inside and Outside Containment t

Palisades Nuclear Plant Systems Needed for ?!itigation of Loss of Cooling 2.

Accidents

3. Specific Questions Concerning Equipment Qualification Documentation Based on the Palisades Site Visit, January 21-25, 1980 Enclosure 3 provided specific questions concerning equipment qualification test documentation that was reviewed at the site. The questions identify deficiencies in the documentation and requested that CP Co either provide additional qualification reports or justify the adequacy of the existing information.

At the NRC regional meeting to explain the Commission's tiay 23, 1980 O (transmitted by 6/25/80 letter) !!emorandu.n and Order and the implication to ongoing equipment qualification efforts, Category 3 was withdrawn from present consideration.

Categories 1, 2, 4 and 5 information is contained herein. Categories 1, 4 and 5 are addressed in Appandix I. Appendix I is a compilation of equipment q"alification packages. Each package contains a qualification work sheet using the IE 79-01B format; a description of the assumptions used to complete the work sheet; a listing demonstrating how the guidelines were met; and, direct responses to the questions raised in Er. closure 3. The listing demonstrating compliance with the guidelines has "DORGR" in the margin followed by statements of compliance. "DORGR" means D0R Guideline Requirement. These requirements are defined in Appendix II. The packages are made up for groups of identical equipment (same manufacturer and model) experiencing the same environment and are listed by system except that the cables, junction boxes, penetrations, terminal blocks and solenoid valves are grouped together.Section II of this report covers the definition, location and environment of the hostile areas. Sectiva III of this report addresses the development of the equipment list. Appendix IV presents two listings of safety-related equipment to be qualified sorted by system and sorted by type.

nul080-0052a-43 Rev 2 O

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Sheet 4 i

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! Component Amphenol Connectors (In Junction Boxes J320, J324, J325, J329, J326

and J321) i l This equipment was qualified in the original CP Ce submittal with no objection i by Franklin Research Center.

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EQUIPMENT OUALIFICATION REPORT Facility: Palisedes Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOO ITEMS Parameter Accident Quancaton Accident OJ System. Operstwig

" :3e tion Test and Service Water and 1 Hour h Hours 1, 2 Analysis III.B Reactor Protect Sys Plant I D. Number Temperature See Figures T & 8 286 (Peak) :3ection See Note 2 (* F)

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No 805h32 Hunety N loo 100 Test and

[I . D.1 1, 2 Analysis Purchese Order Number 3 -

Note 1 26h0 ppm boria lection Test and acid [I.D.2 1, 2 & h Analysis Function / Service. _.

- " *

3 . 8 x 10 5 x 10 lection Test and EI.D.5 3 Analysis

A0"'9 lection Test and D*"* 40 Years + LOCA 40 Years + IDCA

[I.D.8 1 Analysis InsiN*Yontainment Submergence Not Subject to sevanon: Vu r t oua Submergence

3ee Note 3 .

Fluod Level Elevation 596'-0" Above Flood Level.

Yes-. v No

$ DOCUMENTAflON REFERENCES l NOTES

1. Report on Terminal Block / Junction Box Environmental 1. 1750 to 2000 ppm boric acid with 50 to 100 ppm N li 2h*

Testing, by Northeast Utilities Service Company, dated 2. J-350, J-355 and J-521 with Westinghouse TB's March 27, 1978. No 305h32

2. Test Report on the effect of a LOCA on an electrical performance of four terminal blocks, by Westinghouse r oration dsted September 13, lo77. - -

_ _ J858 01 A

O m EOUIPMENT OUALIFICATION REPORT , ,g O

p g Facmty: Palisades Reh Date:

Docket: 50-255 DOCUMENTATION REFERENCES (cont) NOTES (cont)

3. Test report by A P Colaiaco of Westinghouse flote : Junction Boxes for Containment Air Coolers and PT-0102 14 Letter from C A St Onge of Bechtel to H Marusich of CP Co dated October 3. 1980. 3 Respective Elevations are:

601' 1",

6 602'-0", 625'-0" p s b

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Sheet 2 Component Junction Boxes J-350, -355 & -521 and Westinghouse TB's No 805432 2.0 The above components are Nema 4 enclosures and Westinghouse style tenninal blocks rated at 600 volts and 40 amperes.

The junction box and terminal blocks are used in Class 1E control and instrumentation circuits which are required to be functional for a maximum of one hour during an accident. The junction box with terminal blocks mounted inside is qualified for the given environment inside the containment as below: .

a. Per Document Reference 1 the same type of junction box with identical style number of terminal blocks as the one installed in Palisades was tested for aging using Arrhenius techniques at 1.70*C (302*F) for 171 hours0.00198 days 0.0475 hours 2.827381e-4 weeks 6.50655e-5 months . This simulates a life of 40-year for an ambient of 70*C (158'F).

After thermal aging the specimen was subjected to 5 x 'O' rads and a chemical spray test with 2640 ppm of boric acid at 236*F at 40 psig for 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months . The terminal block was kept energized at 525 volts during LOCA test.

b. Per Document Reference 2, a separate test on the terminal block (with no junction box as enclosure) was tested for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 340*F and 90 psig by spraying borated water while ;he terminal block terminals were energized at 600 V.

c. Document Reference 3 establishes by evaluation that the terminal block can withstand a radiation dose of 2 x 10 7 R. No credit has been taken for this.

d. Document Reference 4 establishes the negligible corrosive effect of chemical spray including hydrazine on the insulating mate rial and the junction box material (sheet steel) which shield the terminal blocks from direct spray and, in addition, hydrazine is highly unstable and will decompose rapidly when chemical spray is released into the contain.nent.

e. No credit has been taken to the following:

1. The test specimens in Document References 1 and 2 were energized at 525 volts and 600 volts, respectively, against the control circuit voltage of 125 V or less to which installed terminal blocks are ceanectad.

2. The shielding effect of junction box on terminal block withstand capability due to radiation is not considered.

O nu0980-0589a-43 92 Rev 2

Sheet 2 (Contd)

f. ' The following is a summary of the qualification:

1. Paragraphs a, b and d provide evidence of qualification for aging . radiation, temperature, pressure and humidity.

2. Paragraphs b and c provide further evidence on spray, humidity and radiation. a 1

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Sheet 3 Componant Junction Boxes (J-350, -355 & -521) and Terminal Blocks (No 805432)

DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions The requirements of the D0R guidelines are complied with. The testi:r,was run at temperature and pressure steam conditions which exceed that given in FSAR and Section II.D.1. See Sheet 2.

DORGR 1B Radiation Gamma The requirements of the DOR guidelines are complied with as the JB and TB were tested to 5 x 10' R and need only withstand 1.8 x 10' R.

Beta The requirements of the D0R guidelines are complied with as beta radiation is not significant.

DORGR ID Containment Sprays The requirementr, of the DOR guidelines are complied with as the test included contalment sprays more harsh as the ones used at Palisades. Also see Sheet 2 for discussion.

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DOpGR 2A Temperature and Pressure Steam Conditions The requirements of DOR guidelines are complied with. Palisades

, utilizes redundant automatic containment spray systems.

Therefore, in accordance with DOR guidelines, Section 4.2, Paragraph 1, qualification for LOCA environment is adequate and additional qualification for main steam line break accident environment is not required.

Refer to DORGR 1A for details of LOCA qualification.

DORGR 2B Radiation The requirements of DOR guidelines are complied with. Refer to response in DORGR 1B.

DORGR 2D Chemical Sp.1/s The requirements of DOR guidelines are complied with. Refer to response in DORGR 1D.

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Sheet 3 (Contd)

DORGR S Qualification by a Combination of Methods (Test, Evaluation, Analysis)

DORGR SA Qualification by Evaluation and/or Analysis The requirements of the D0R guidelines are complied with:

a. Pressure, temperature, humidity, chemical spray, aging and radiation by test and analysis. See Sheet 2.

DORGR SB Qualification by Type Testing

1. Simulated Service Conditions and Test Duration The requirements of the DOR guidelines are complied with because the test duration was longer than the time the terminal blocks will be energized and the peak temperatures and pressure exceed the accident conditions.

2. Test Specimen The requirements of the DOR guidelines are complied with as

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\s , the test specimens were similar to the ones at Palisades.

3. Test Sequence The requirements of the D0R guidelines are complied with. See sheet. The sequence of test for test in Document Reference 1 is as follows:

a. Aging

b. Radiation

c. Chemical Spray

4. Test Specimen Aging The requirements of the DOR guidelines are complied with.

Aging was based on an Arrhenius technique. See Sheet 2.

5. Functional Testing and Failure Critieria The requirements of the DOR guidelines are complied with. The terminal blocks withstood continuous energization during test without fail proving dielectric integrity.

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Sheet 3 (Contd)

6. Installation Interfaces The requirements of DOR guidelines are complied with. See Sheet 2. The terminal blocks are mounted inside to junctica box as in the case of test specimen.

DORGR 6 Margin The guidelines of the DOR are complied with. See Sheet 2.

Radiation, pressure and aging withstand vale 1 for the terminal blocks exceed the requirements.

DORGR 7 Aging The requirements of DOR guidelines are complied with as the JB and TB were tested at 150*C for 171 hours0.00198 days 0.0475 hours 2.827381e-4 weeks 6.50655e-5 months to simulate 40-year life.

DORGR 8 Documentation The requirements of DOR guidelines are complied with. Refer to Sheet 1.

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Sheet 4 where the normal voltage is 125 volts or less, Also, these terminal blocks were installed under strict quality control and supervision.

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" " Component Sheet No:

Owner: Consumers Power Company flevision:

Facihty: Pahsades Date:

Docket: 50 255 ENVIRONMENT DOCtlMENTATlON DEFERENCES METHOD IIE MS Paramete, Accident Oualif. cation Accident Oual System. Operatirg Miscellaneous Time 30 Days 1 Year 1 Test and Analysis Electrical Sys

- P*85* See Figures 340 Section 1, 2 Test and Cabl Cod 3', Z62 g.

7 and 8 II.D.1 Analysis Component XLPE Insul Pvc Jack. Pressure Test and um,,ci,,,. (PSAi See Figure 9 117.7 Section 1, 2 II.D.1 Analysis General Electric Model Number Relative Humidity gM 100 100 Section 1, 2 Test and II.D.1 Analysis

s. O,d., _

ric Acid and Nacil Section 1, 3 Test and 5935-E-23A-AC Sp' 2ric dI tli 50-100 Ppm N II24

E ** " I*

% ,on, w ,

Transmit Electric nadianon 8 Signals (nad)

See Note 1 1 x 10 Section 1.2 Test and II.D.5 Analysis

""*## ^'" 40 Years 40 Years Section 1 Test and N

Plus IACA Plus LOCA II.D.8 Analys is l ocat.on- Inside Containment Submergence oe,.non Va rious Yes (Note 2) Yes Section 14 Test and II.D.3 Analysis flood teved Devation 590'-0" Above Flood ievel Yes No X NOTES w OOCUMENTATION REFEnENCES 0 L. General Electric "Quali.fication Test Summary - 100 1. Beta: 2x108~R @ surface, 2x107 R @ 0.03",

" Series Electric Penetration," February 28, 1975. 2x106 R @ 0.07" (See Sheet 2 for discussion.)

Capui: 2x107 R

2. FIRL Final Test Report, F-C45' 9-1, Apr 1978.

3. Letter from C A St Onge of Bechtel Corp to R Marusich

" Consumers Power Co dated 10/3/80. - _

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Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsades Reh Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUAUFCATM OUTSTANDING EOUIPMENT DESCRIPTION METHOO liEMS Parameter Accident ( OuaWcation Accident Oug System Operating Test & Anal-Miscellaneous Tun

ysis - See Electrical Sys 30 Days _

1 Year Sec ITT.R 1 Note 2 Plant I D Numbef Temperature Test & Anal-Cable Codes Z 3, 26( (*F) Various - See ysis - See component.

Z" Note 1 340 (Peak) Sec II.D.6 1. 2 Note 2 XLPE Insul Pressure Test & Anal-MNturer: IN^l ysis - See Atmospheric 117.7 (Peak) Sec II.D.6 1, 2 Note 2 General Electric RMive Test & Anal-Mode l Number Hurr*My t%) Various - See ysis - See Note 1 100 Sec II.D.6 1, 2 Note 2

$ 5935-E-23A-AC SP' None Funct6oniservice-Transmit Electric Rae non Signals (Rad) Negligible Accuracy: Spec: g g .g Test & Anal-Demo- 40 Years Plus MSLB 40 Years Plus LOCA II.D.8 1 ysis - See tocation: Various - Note 2 Outside Containment 8"D**'Q*"C* Not Subject

(%,I;B,,)n: See Note 1 -

Various to Submergence Flood Level Elevaton Above Flood Level.

Yes No

! NOTES DOCUMENTATION REFERENCES l u . - .

m 1. General Electric " Qualification Test Summary - 1. a) Rooci 123, MSLB conditions:

100 Series Electric Penetration" February 28, 1975.

212 F for one hour then linear decline to 110 F

2. FIRL Final Test Report, F-C4879-1, April 1978. at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 80% kil.

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O O EOUIPMENT GUALIFICATION REPORT O

. Owmer Consumers Power em Component M No...

Faceity: Pahsades Reh Docket: 50-255 Dak:

DOCUMENTATION REFERENCES (cont) NOTES (cont) b) Room 238, MSLB conditions:

) 275 F for one half hour then linear decline to ' ;

110 F at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 95% Ril.

I 1 Th( cables are considered to be qualified for outside containment applications ban ed on the qualifie.ation for the more severe "in-containment" use including 40-year

life and LOCA. Even though cable Code Z66 is not used inside containment, it has the same type of insulation material and Jacket as cable Codes Z63 and Z62 which are used inside the containment. Therefore, for Sheets 2, 3 l and 1, 4 refer to component sheets which cover the qualifica-i o tion of cable Codes Z63 and Z62, General Electric for use

" inside containment.

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EQUIPMENT OUALIFICATION REPORT ,

Revison I Fackty: Paksades

' Date:

Docket: 50-255 I

ENVIRONMENT DOCUMENTATION ftEFERENCES OUALIFICATION OUTSTANDING w THOO HEuS Parameter Accident Ouawcation Accident Oual System. Operetno Test & Anal-Miscellaneous I'** ysis - See Electrical Sys 30 Days 1 Year Sec III.B 1 Nnre ?

Plant I D. Number Temperature Test & Anal-le Codes Z63, 266 (*F) Various - ysis - See C.g'C A

omponent See Note 1 340 (Peak) Sec II.D.8 1, 2 Note 2 XLPE Insul p,enu,e Test & Anal-b MVa.turec W^l 14.7 117.7 Sec II.D.8 1, 2 YSIS - See General Electric Note 2 psei,,e Test & Anal-m% ysis - See Humioty (%) Various -

See Note 1 100 Sec II.D.8 1, 2 Note 2 Purchase Order Number Chemical 5935-E-23A-AC Spray None

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$ Functiont Service Raieten fest & Anal-Transmit Electric Signals (Rad) Various - vsis See g

See Note 1 1 x 10 [I.D.7 1 2 Note 2

curacy: Spec: Ag,ng fest & Anal-D*"* 40 Years 40 Years Plus LOCA II.D.8 1 vsis - See tocaten Various - late 2 itside Containment LOCA) See Note 1 8"'"'0*"

Elevemn Not Subject us to Submergence f tood Level Elevatun Above Flood Level Yes No DOCUMENTATION REFERENCFS NOTES

'S 4 1. General Electric " Qualification Test Summary - 1. a) Engineered Safeguard Room:

ro 100 Series Electric Penetration," February 28, 1975.

135 F, 1 x 10 RAD gamma and 100% Ril.

2. FIRL Final Test Report, R-C4879-1, April 1978.

085tl 01 A t

EQUIPMENT OUALIFICATION REPORT Component Sheet No.:

Owner: Consumers Power Company FacElty: Pahsades Revision:

l Dcchet: 50-255 , ' Date:

DOCUMENTATION REFERENCES (cent) NOTES (cont) b) Penetration Areas other than Rooms 123, 238 and 338:

104 *F, 5 x 10 RAD gamma and 100% Ril.

t

+ c) Room 338:

120*F, 6 x 10 RAD gamma and 95% Ril.

l d) Hoom 123:

104*F, 1 x 10 RAD gamua and 80% Ril.

' e) Room 238:

i 55 I " 110*F, 5 x 10 RAD gamma and 95% Ril.

I 2. These cables are considered to be qualified for outside containment applications based on the qualification for the more severe "in-containment" use including 40 year life and LOCA. Even though cable Code Z66 is not used inside containment, it has the same type of insulation material and jacket as cab 1? Codes 263 and Z62 which

' are used inside the contaitsent. Therefore, for Sheets 2, 3 and 1, refer to component sheets which 4

cover the qualification of cable Codes Z63 and Z6r ,

General Electric for use inside containment.

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G 0858 02A

Sheet 2 Component General Electric Cable _

Cross-L;nked Polyathylene (Vulkene) Insulation PVC Jacket 3/C, 2/C #16 Awg (Codes Z63, 262)

A. The above cables are used in Class IE circuits inside the containment.

263 is above the flood level, while 262 may become submerged.

B. Document reference 1 is a General Electric Test Summary on 100 series electrical penetrations which includes Vulkene SIS wire (without jacket) in some of the test assemblies. The test demonstrates that the cable is qualified for use inside the containment based on 40-year life and LOCA.

The test cycle included the following:

1. Thermal cycling from 50*F to 150*F to 50*F four times a day for thirty days.

2. Gcmma radiation exposure of 1 x 10' rad total integrated dose.

3. LOCA simulation test at a peak temperature of 340*F, 100*. RH, a peak pressure of 103 psig and with an alkaline environment at a maximum pH value of 8.4 including boric acid and sodium hydroxide.

4. Post-LOCA environmental test of 225*F, 20 psig'and 100*. RH for one year.

C. Document reference 2 is a Franklin Institute Research Laboratories test report on penetration connector assemblies which included GE cables with cross-linked polyethylene insulation and PVC jackets. This provides further evidence for qualificatio- of cables with materials similar to the supplied cables. The test cycle included the following:

Gamma radiation exposure of 2.6 x 10' rad total integrated dose from a cobalt-60 source.

LOCA simulation test at a ;'eak temperature of 300*F and a peak pressure of 52 psig.

D. Document reference 4 indicates that the cable has passed a moisture resistance test (IPCEA Project 294) which includes immersion in 50*C water for 16 weeks.

E. The following is a qualification summary:

1. Tests under Paragraph B and C provide evidence of temperature, pressure and humidity qualification.

2. The cables are qualified for chemical spray based on the folicwing:

nu0980-0582a-43 104 Rev 2

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Sheet 2 (Contd) 7-4

a. Chemical spray content was not defined in the test described in Paragraph B but the test environment included boric acid and Sodium Hydroxide and was alkaline for over 8 days starting with a pH of 8.4 and eventually dropping to a pH of 7.5.

b. Although the operating time requirement is 30 days, analysis of containment parameters shows that, following a LOCA, temperature 4

and pressure conditions return to ambient in about 11 days.

Therefore, following an accident, the containment spray is not likely to continue beyond 11 days,

c. Even though the pH range of 7-8.3 was maintained for 8 days only (against the requirement of 11 days), it is concluded that the spray requirements have been fully met, based on t'ae following factors:

(1) Other parameters, such as peak pressure and temperature, were l excecded by wide margins.

(2) Post-LOCA environmental test at 225'F, 20 psig and 100?. RH was continued for 370 days against the maximum requirement of 30 days.

d. Analysis, document ref (3), indicates that' spray chemicals, including hydrazine in low concentrations have no corrosive effect on cable insulation material. In addition, hydrazine is highly unstable and will decompose rapidly when chemical spray is released into containment.

, 3. The cables have been qualified to 1 x 10' rad gamma per testing under

?tragraph B compared to the requirement of 2 x 10 rad 7 gamma and 2 x 10' rad beta at the outer surface. It is concluded that the cables are qua!.ified to Palisades requirements based on the following evaluation:

a. The test radiation dose of 1 x 10' rad gamma exceeds the requirements of 2 x 107 rad gamma.

b. Almost all cable installations inside containment are enclosed in cable trays or condait which shield the cables from beta radia.-

tion. In addition, cable jackets also provide further shielding from beta radiation. The conductor insulation will, therefore, be exposed to reduced beta doses only.

4. The cables are qualified for 40-year life based on the following evaluation:

m nu0980-0582a-43 105 Rev 2 i

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Sheet 2 (Contd)

a. The initial step of the test under Paragraph B is a thermal cycle from 50*F to 150'F to 50*F four times a day for thirty days.

b. The LOCA test under Paragraph B included high temperature, pressure and humidity conditions lasting for more than 370 days compared to the 30-day requirement. This far exceeded the required LOCA test so that this test contributed to aging the cable specimen. The aging process on the cables would have continued (while the LOCA test was in progress) for 370 days.

Analysis indicates that the combined effect of aging and LOCA test at 225'F under steam conditions for 370 days is not less severe than the effect of normal thermal aging and LOCA done in sequen i.

Further, it is an established fact that the sr.me type of insu-lation, cross-linked polyethylene, has been fully qualified by several major cable vendors per IEEE-383, including 40-year life and LOCA.

5. At certain locations inside containment, Cable 262 is routed at elevations below flood level and, therefore, may become submerged.

Based on the following evaluation, it is concluded tha; the cable is qualified for submerged applications:

e. The cable has passed a moisture resistance test which includes immersion in 50*C water for 16 weeka as deceribed in Paragraph D.

b. During LOCA tests under Paragraphs B and C, chemical spray was included in the test cycle. The surface of the cable is almost fully covered by fluid for the duration of the spray and this is generally equivalent to submergence. Coincidental high pressures (up to 103 psig) and high temperatures (up to 340*F) in the LOCA test chamber give rise tu a situation which is analogous to submergence under high pressure and temperature.

F. The similarity between the supplied cables and the tested cables (see Paragraphs B, C and D for test referer_;es) is based on the following:

1. General Electric is the cable manufacturer in both cases.

2. Cross-linked polyethylene (Vulkene) is the insulating material in both Cases.

O nu0980-0582a-43 106 Rev 2

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'J Sheet 3 Component General Electric Cables (Codes Z63, 262)

DORGR 1 Service Conditions Inside Conrainment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions The test was run at temperature and pressure steam conditions which exceed those given in the FSAR and Section II.D.1. This complies with the requirements.

DORGR 1B Radiation Gamma The cables were tested to 1 x 10' rads which is much greater than the dose at the insulation surf.:e which is about 2 x 10' rads.

DORGR IC Submergence The requirements of the DOR Guidelines are met based on the moisture resistance test and LOCA test discussed in Sheet 2.

[\ DORGR ID Containment Sprays

\m-The chemical spray used has a pH greater than that at Palisades and, as such, complies with the requirements (discussed in Sheet 2).

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure steam Conditions Palisades utilizes redundant automatic containment spray systems.

Therefore, in accordance with DOR Guidelines, Section 4.2,

, Paragraph 1, qualifications for LOCA environment is adequate and additional qualification for main steam line break accident environment is not required. Refer to DORGR 1A for details of LOCA qualification.

DORGR 2B Radiation Refer to response in DORGR 1B.

DORGR 2C Submergence Refer to response in DORGR 1C.

0'

'J nu0980-0582a-43 107 Rev 2

Sheet 3 (Contd) 00RGR 2D Chemical Sprays Refer to response in DORGR 1D.

DORGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Qualification is by evaluation of type test and analysis. This complies with the requirements.

DDRGR 5 Qualification by u Comb,f..ation of Methods (Test, Evaluation2 Analysis)

This guideline is complied with as follows:

DOROP SA Qualification by Evaluation and/or Analysis Requirements complied with as follows:

1. Temperature, pressure, humidity, spray qualification (except hydrazine), aging and radiation by evaluation of type test results on similar cables as shown in Sheet 2.

2. Hydrazine withstand capability by analysis as given in Sheet 2.

DORGR 5B Qualification by Type Testing

1. Simulated Service Conditions and Test Duration The test lasted over one year for the LOCA events. This complies with the requirements except for chemical spray duration (justification in Sheet 2).

2. Test Specimen Refarence document 1 and the discussion on similarity in Shaet 2 (including reference document 2) shows the similarity between the test specimen and the installed cables.

3. Test Sequence

a. Thermal Cycle

b. Radiation Exposure O

nu0980-0582a-43 108

O Sheet 3 Cetpenent 600 Volts Instrumentation Cable (Code Z-62)

DORGR 1 Service Conditions Inside Containment for LOCA conditions DORGR 1A Temperature and Pressure Steam Conditions The requirements of DOR guidelines are complied with. See Sheet

2. The test was run at temperature and pressure steam conditions which exceed that given in FSAR and Section II.D.1. This complies with the requirements of the guidelines.

DORGR 1B Radiation Gamma The cable specimens were subjected to a total radiation dose of 5 x 10' R which exceeds the combined gamma and beta radiation dose requirement of 2.2 x 10'. The requirements of the guidelines are complied with. See Sheet 2.

Beta The requirements of the DOR guidelines are complied with. See Sheet 2.

-~ DORGR 1C Submergence V At certain locations inside the containment, portions of these cables could get submerged during LOCA conditions. This complies with the requirements of the guidelines as explained in Sheet 2.

DORGR 1D Containment Sprays The chemical sprays used during LOCA testing meet all the requirements except that hydrazine was not present. This cemplies with the requirements of the guidelines as explained in Sheet 2.

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions The requirements of D0R guidelines are complied with.

Palist. des Plant utilizes redw$ ant automatic containment spray systems. Therefore, in accordance with DOR Guidelines, Section l

4.2, Paragraph 1, qualification for LOCA environment is adequate i and additional qualification for main steam line break accident environment is not required. Refer to DORGR 1A for details of LOCA qualification.

, b>

\--

l l

nu0980-0546b-43 215

Sheet 3 (Contd)

DORGR 2B Radiation The requirements of DOR guidelines are complied with. Refer to response in DORGR 1B.

DORGR 2C Submergence The requirements of DOR guidelines are complied with. Refer to response in DORGR 1C.

DORGR 2D Chemical Sprays The requirements of D0R guidelines are complied with. Refer to response in DORGR 1D.

DORGR S Qualification by a Combination of Mechods (Test, Evaluation, Analysis)

DORGR SA Qualification by Evaluation and/or Analysis Requirements of DOR guidelines are complied with as follews:

1. Temperature, pressure, aging, chemical spray (except hydrazine), humidity and submergence be evaluation of type tests results on cables with same type of insulation. This is discussed in Sheet 2.

2. Hydrazine withstand capability of cable by analys:s as discussed in Sheet 2.

DORGR SB Qualification by Type Testing

1. Simulated Service Conditions and Test Duration i The test duration of 30 days covers the entire time until the conditions in the containment return to essentially ambient.

The test profile is that required by IEEE 383 (1974). This complies with the guidelines and is explained in Sheet 2.

2. Test Specimen This complies with the D0R guidelines. The test specimens have same type of insulation (XLP) as the installed cable.

See Sheet 2.

3. Test Sequence The requirements of DOR guidelines are complied with. Also the test sequence meets IEEE-383 (1974) requirements as below:

nu0980-0546b-43 216 Rev 2

(3 v

Sheet 3 (Contd)

a. Thermal aging

b. Radiation

c. LOCA & chemical spray

d. Post LOCA Test (dielectrics)

4. Test Specimen Aging The cables have undergone aging tests as explained in Sheet 2.

Therefore, the requirements of the D0R guidelines are met.

5. Functional Testing and Failure Criteria The requirements of the D0R guidelines are complied with.

Passed dielectric tests at 80 V ac/ mil (with a minimum of 2.2 kV for 1 minute) after aging, LOCA and long-term moisture absorption tests.

I

6. Installation Interfaces Mounting arrangement of the test specimen during qualification testing was similar to the installed equipment at the Palisades Plant. This complies with the requirements of the guidelines.

DORGR 6 Margin The requirements of D0R guidelines are complied with. Test parameters exceed the Palisades environment.

DORGR 7 Aging

. The requirements of DOR guidelines are complied with as explained in DOKGR 5.B.4.

DORGR 8 Documentation The requirements of DOR guidelines are complied with. Refer to Sheet 1.

i nu0980-0546b-43 217 Rev 2 i

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EQUIPMENT OUALIFICATION REPORT Owner. Consumers Power Company Mh Facility: Palisades N Docket: 50-255 N' ENVIRONMENT DOCUMENTATION FiEFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Ouenceton Accident Oual systent eW Section Test and Miscellaneous 30 Days 30 Days I '"

Analysis III.B Electrical System Plant i D. Number Temperefore I.py Section Test and Cable Code Z-62 See Figures 7 & 8 346 (Peak) 1 Thru 7 Analysis II.D.1 Component.

Electrical Cables pr .

E tEdh:bJ [ et (PSIA) See Figure 9 127.7 (Peak) aly See Note 3. -

l Model Number Reicsve Seetion Test and HumkMy(%I 100 100 '"

g 11.D.1 Analysis

$ Purchase Order Number lk p -

chamaces sprey 1750 to 2000 ppm O g gc d 3 00 S lSection Test and 5935-E23A-DC boric acid with Naciltomaintafn' I" Analysis Function / Service: 50 to 100 ppm pil 9 to 11 l II.D.2 Transmit Electrical Redet6on S igr.a ls / I ns t rumen ta- (Red) Note 1 2 x 10 (Camma) 5 1 Thru 7 na y tion

- - "'" ^9'"O D"

Test and 40 Years 40 Years & IDCA II.D.8 1 Thru 7 Analysis toceton: Various Inside Containment submergence Test and Elevanon: Yes (See Note 2) Yes II.D.3 1 Thru 9 Analysis Various Flood tevel Elevelion a Above Flood tevel:

Yes: bee No:

Note 1 DCCUMENTATION REFERENCES NOTES l

7 8 R 0 Suriace, 2 x 10 R 0

@ 1. Prototype test report for qualification of Frewall III 1. Gannua : 2 x 10 R; Beta 2 x 10 m Class lE electric cables by the Rockbestos Co, 7/77. 0.03," 2 x 10 6 R 0 .07".

2. Franklin Institute Research Lab Final Report F-C3016, 2. Portions of cables on submerged. See Sh 2 for discus-June 1971 and addendum dated August 4, 1971. sion.

3. GE " Qualification Test Summary - 100 Series Electric P -

ration," Feb 28, 1975. em -

38 Ot A I

/

%.}

\

h)

% h)

%a EQUIPMENT QUAUFICATION REPORT Component 9*eet No..

w Consumers Power Company .

Faculty: Pahsades Reh Date:

Docket: 50-255 l DOCUMENTATION REFERENCES (cont) NOTES (cont) 4 4. Qualification test report by Okonite dated Aug 9, 3. At this time the cable manufacturer has not been l 1978 on " Aging, Radiation and LOCA Testing of Cross- identi fied. The distributor for this cable was

, Linked Polyethylene Insulated Cables for Nuclear ANIXTER IIARBOR INC. Field inspection indicates that Power Generating Stations. the cable insulation and jacket materials (XLP and PVC) agree with the information supplied at the time

5. Letter from D D Sand of Rome Cable Corp to C A St On> e of procurement. Consumers Power Company will continue j of Bechtel Power Corp, dated S e t 17, 1980. to pursue identification of the cable manufacturer.

6. Letter from A A Littlehaler of Rockbestos Company to C A St Onge of Bechtel dated Sept 19, 1980.

7. Letter from C A St onge of Bechtel Corp to I

R Marusich of Consumers Power Co dated 10/3/80.

8. Iong Term 90 C water immersion test. Okonite dated March 5, 1975.

l 9. Special moisture absorption test report from Rockbestos Company.

1 4

E fu i

G-0858-02A i

EQUlPMENT OUAUFICATION REPORT ,

Revision Facinty: Palisades Date:

D0cket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOD ITEMS Parame.a Accident Quahncaton Acc ident oual 8**'" Section Test and N'" 30 Days 30 Days III.B 1 Thru 7 Analysis g=;, Electrical T m Mure Various Cab CSd 2

(*F) See Note 1 346 (Peak) Section Test and Component: Elec 275 F (Feak) II.D.8 1 Thru 7 Analysis Cables XLP Insulated Test and

PVC g g (ShieldedI fp(* M.7 127.7 (Ped)

Section II.D.8 1 Thru 7 Analysis See Note 3 Test and hoodel Numt>er Istat6ve Various Section Hum 6d"Y (N See Note 1 100 II.D.8 1 Thru 7 Analysis

$ Purchase % Numt>er 95 (tiax) 5935-E23A-DC None Function / Service.

Transmit Elec Signal ,

-Instrumentation (Rad) Negligible ACC"'*CY SP** Aoino Section Test and U**

40 Years + MSLB 40 Years + LOCA II.D.8 1 Thru 1 Analysis Locaton: Various -

Outside Containment "

Elevation: (MSLB) Not Subject Various to Submergence

. Flood Level Elevaton Above Flood Level:

Yes: No:

DOCUMENTATION REFERENCES NOTES to Q l. Qualification of Firewall T.II Class IE Electric Cables 1(a) Room 123 - 2120F for One llour Then Linear Decline to 1100F at 24 llours; Ril 80%

m by Rockbestos Company, July 1977

2. Franklin Institute Research Laboratories Final Report ,

1(b) Room 238 - 275 F for 1/2 Ilour Then Linear Decline F-C3016, June 1977 and Addendum Dated August 4, 1971 to 110 F at 24 Ilours; Ril 95%

3858 01 A

o m m Owner: Consumers Powor Company Component Sheet No.:

Faclhty: Pahandas Revision Docket: 50-255 Date:

DOCUMENTATION REFERENCES (cont) NOTES (cont)

2. These cables are cor.sidered to be qualified for out-

3. Generei Electric " Qualification Test Sumraary -

100 Series Electric Penetration," Feb 28, 1975 side containment applications based on the qualifi-cation for the more severe "in-containment ** use

4. Qualification test report by Okonite dated August 9, including 40-year life and LOCA. Therefore, for 1978 on " Aging, Radiation and LOCA Testing of Cross- Sheets 2, 3 and 4, refer to component sheets which T. inked Polyethylene Insulated Cables for Muclear cover the qualification of cable code Z-62 (Universal Power Generating Stations." Wire & Cable Co - Collyer Cable) for use inside

)

containment.

5. Letter from D D Sand of Rome Cable Corp to C A St Onge of Bechtel Power Corp dated Sept 17, 1980. 3. At this time the cable manufacturer has not been identified. The cable distributer was ANIXTER

6. Letter from G G Littlehales of Rockbestos Company to IIARBOR INC. Field inspection indicates that the r0

. I$ C A St Onge of Pechtel dated Sept 19, 1980. cable insulation and Jacket materials (XLP and PVC) 4 agree with the information supplied at the time of procorement. Consumers Power ompany will continue

7. Letter from C A St onge of Bechtel to R Marusich of Consumers Power Company dated October 3, 1980. to pursue identification of the cable manufacturer.

4 TO 2

G-0858 02A

EQUIPMENT OUALIFICATION REPORT Owner. Consumers Power Company M*

Facety- Paksades Docket: 50-255 N' FNv1RONMENT DOCUMENTATION PEFEREfCES STN ENNT DENM MEmOO ITEMS Parameter Accident Ouawcanon Accident Oua, Oswra6 e Section Test and Hisc SyI.$:ctrical Time 30 Days 30 Days iII. B 1 Thru 7 Analysic System T ature Cab '"

Co h I.7I Various See Note 1 346 (Feak)

Section II.D.8 1 Thru 7 Test and Analysis Component: Elec Cabl es 1 gso F (Ponki

{LP Insulated, PVC Pressure Section Test and fac 4 g lded) (psia 3 14.7 127.7 (Peak) II.D.8 1 Thru 7 Analysis See Note 3

'*"nber Reimeve Various to

'W OI Section Test and g See Note 1 100 II.D.8 1 Thru 7 Analysis

Purm m m 100 (Max)

Chemical 5935-E23A-DC Spray None Function / Service-fransmit Elec . Radhahon Various Sec i n es and Signals - Instrumenta- (Rad) See Note 1 2x10 8R (Camma) " ^" Y' tion 7 *

lx10 R Camma (Max)

Accuracy: Spec; Aging Duno: 40 Years + LOCA 40 Years + LOCA Section Test and

t. yg9 _

II.D.8 1 Thru 7 Analysis Jutside Containment Not Subject to Submergence O'**"; Submergence Various Flood tevel Elevahon Above Flood Level.

Yes: No DOCUMENT ATION REFERENCES NOTES l

' I E'

l. Qualification of Firewall 111 Class IE Electric Cables 1(a) ESF Rooms 135 F- lx10 R (Gamma)

RH 100%

by the Rockbestes Company, July 1977 1(b) Penetration Areas Other 1040F; 5x10 5F (Camma)

2. Franklin Institute Research Laboratories Final Report Than Room 338 RH 100%

F-C 3016, June 1977 and Addendte Dated August 4,1971 1858 01 A

A A m Ownu: Consumers Power Company Component Sheet No.:

Facety: Paha<tas Revision Date:

Docket: 50-255 DOCUMENTATF)N r.EFERENCES (cont) NOTES (cont)

3. General Electric " Qualification Test Summary - 1(c) Room 338 120oF; 6x105R (Cama) 100 Series Electric Penetration," Feb 28, 1975. RH 95%

4. Qualification test report by Okonite dated Aug 9,1978 1(d) Room 123 1040F; 1x10 6R (Camma) 2 on " Aging, Radiation and LOCA Testing of Cross-Linked RH 80%

Polyethylene Insulated Cables for Nuclear Power 5 Generating Stations." 1(e) Room 238 120 F; 5x10 R (Camma)

RH 95%

]

5. Letter from D D Sand of Rome Cable Corp to 1 C A St onge of Bechtel Power Corp deced Sept 17, 1980, 2. These cables are considered to be qualified for outside containmant applications based on the qualification for

6. Letter from G G Littlehales of Rockbestos Company the more severe "in-containment" use including 40-year to C A St Onge of Bechtel dated September 19, 1980. life and LOCA. Therefore, for Sheets 2, 3 and 4, refer

$ to component sheets which cover the qualification of Q 7. Latter from C A St onge of Bechtel Corp to R Marusich Cable Code 262 (Universal ~ wire and Cable Co) for use of Consumers Powe:- Company dated October 3,1980. Inside containment.

3 At this time the cable manufacturer has not been iden-tified. The cable distributor was ANIXTER HARBOR INC.

Field inspection indicates that the cable insulation and )acket materials (XLP and PVC) agree with the in-formation supplied at the time of procurenent.

Consumers Power Company will continue to purst: 3 iden-tification of the cable manufacturer.

o 1

G-0858-02A

Sheet 2 Component 600 Volts Instrumentation Cable (Code Z-62)

Z-62: 600 Volts 2/C #16 AWG 7 Strand, Twisted Pair Cable With Cross-Linked Polyethylene Insulation - XLP (30 Mils) and Polyvinyl Chloride - PVC (45 Mils) Jacket Distributed Through Anixter Harbor Inc.

These cables are used in Class 1E circuits inside the containment where, at equipment locations, these are routed below the flood level elevaion of 596'-0" and could get submerged during a LOCA.

The qualification of the subject cable is based on the following:

1. By taking credit for qualification testa done by various vendors that have proved the generic capability of tLa cables (with cross-linked polyethelene insulation) to meet the severe envirenments postulated incide the containment of nuclear power plants, both PWR and BWR.

Fer document References 1, 2, 3 and 4, the following are the parameters to which various vendors hava tested the cables with cross linked polyethylene insulation. All these cables meet the IEEE-383 (1974) requirements for use inside the containment based on 40-year life and LOCA.

Environment Parameter Rockbestos Okonite Rome Cable General Electric Aging 40 Years 40 Years 40 Years 40 Years

+ LOCA + LOCA + LOCA + LOCA Radiation Gamma 2 x 10' R 2 x 10' R 5 x 10' R 1 x 108 R (Cobalt 60 Source)

LOCA (See Note 1) .

Temperatu:e (Peak) 346*F 346*F 303*F 340*F Pressure (Peak) 113 113 56 103

- Psig Relative Humidity 100% 100% 100% 100%

Chemical Spray pH Value (All 9 to 11 9 9 7.5 to 8.4 With boric Con- (Minimum) centration not less than 2000 ppm.)

nu0481-02844-43 O

2183 Rev 2

o (G

I Sheet 2 (Contd)

After aging, radiation and LOCA + chemical spray tests, the cable, while still immersed in water (mandrel test), successfully passed dielectric test of 80 VAC/ mil, with a minimum of 2.2 kV for one minute.

Note 1 - LOCA test duration is minimum 30 days for all cases except for Rome which is 12 days. However, an analysis of containment parameters shows that following a LOCA, temperature and pressure conaitions return to ambient in about 10 days. Therefore, containment spray is not likely to continue beyond 11 days.

Note 2 - Even though this is not a requirement per IEEE-383 (1974), certain vendors such as Rockbestos and Okonite have performed additional testing on their cables after the completion of 30-day LOCA and chemical spray tests. The additional testing involves subjecting these cables to a temperature of 212* for 100 days at 100*. RH prior to final dielectric tests.

It is concluded that the temperature, pressure, humidity, radiation and aging requirements have been met and exceeded by substantial margins.

2. Industry standards, such as ICEA (formerly IPCEA), stipulate minimum insulation thickness for a particular voltage class, and sample test at frequent intervals to prove that uniform quality is maintained at all times. This ensures that different cables with the same type of (V) insulation material will qualify on a generic basis to set standards and exhibit consistent performance characteristics regardless of the time period in which they were manufactured. This has been confirmed by many vendors (see document re'erences 5 and 6).

3. Per documents references 1, 3 and 4, bas'ic single conductor wires with conductor insulation only (without jackets) were qualified by type tests.

Therefore, no credit has been taken for cable jackets.

Cable jackets are required for mechanical protection during initial installation only. Jacket failure is not likely to lead to cable failure

because the individual conductor insulation is fully qualified to meet the environmental requirements.

4. Analysis (document reference 7) indicates that spray chemicals including hydrazine, in low concentrations, have no corrosive effect on cable insulation material. In addition, hydrazine is highly unstable and will l

decocpose rapidly when chemical spray is released into containment.

5. At certain locations inside the containment, the subject cables are routed at elevations below 596'-0" and, therefore, may become submerged. Based l

on the following evaluation, it is concluded that the cables are qualified l for submerged applications,

a. The installed cables meet the ICEA (formerly IPCEA) standard water

! Ci absorption test requirements. Some vendors have tested cables with V 11milar type of insulation for imirersion in 90*C water for 26 to 52 l

l l nu0481-0284a-43 218h Rev 2

- - - - w+. , - , , , . , , , - - - ~ ,- - - - - , - , . , - - - ,-- am-r- -

Sheet 2 (Contd)

O weeks (see document references 8 and 9) and also successfully tested for dielectric withstand voltage of not less than 80 V ac/ mil.

b. During LOCA test, chemical spray was included in the test cycle. The surface of the cable is almost fully covered by fluid for the duration of the spray and this is generally equivalent to submergence.

Coincident high pressures (more than 62 prig) and high temperatures (more than 305'F) in the LOCA test chamber give rise to a situation which is analogous to submergence under high pressure and tec:perature.

c. After the LOCA test, the cables have passed dielectric test (mandrel test) at 80 V ac/ mil while atill submerged in water.

6. Cables with the same type of insulation have been qualified 2 x 10' R gamma by many vendors (some cables have qualified for 5 x 10' R gamma and General Electric to 1 x 10' gamma) against the requirement of 2 x 10' gamma and 2 x 10' R beta at the outer surface. It is concluded that the cables are qualified to Palisades requirements based on the following evaluation:

a. Test radiation dose of even 1 x 10' R gamma (by GE) exceeds the requirement of 2 x 10' R.

b. Almost all of cable installations inside the containment are enclosed in cable trays or in conduits which shield the cables from beta radiation. In Addition, cable jackccs provide shielding from beta radiation. Therefore, conductor insulation will be exposed to significantly lower beta doses.

The following is the summary for qualification of the installed cable:

Aging: Per Paragraphs 1, 2 and 3 aging requirements are complied with or esceeded.

9 Radiation: Per Paragraphs 1, 2, 3 and 6 radiation requirements are complied with or exceeded.

LOCA: Per Paragraphs 1, 2, 3 and 4 LOCA with chemical spray, With Temperature temperature, pressure and relative humidity requirements Pressure and are complied with or exceeded.

Humidity Submergence Submergence requirements are complied with or exceeded.

O nu0481-0284a-43 2181 Rev 2

g Sheet 3 Component 600 Volts Instrume..tation Cable (Code Z-62)

DORGR 1 Service Conditions Inside Containment for LOCA conditions DORGR 1A Temperature and Pressure Steam Conditions The requirements of DOR guidelines are complied eith. See Sheet

2. The test was run at temperature and pressure steam conditions which exceed that given in FSAR and Section II.D.1. This complies with the requirements of the guidelines.

DORGR IB Radiation Gamma The cable specimens were subjected to a total radiation dose of 5 x 10' R which exceeds the combined gamma and beta radiation dose requirement of 2.2 x 10'. The requirements of the guidelines are complied with. See Sheet 2.

Beta The requirements of the DOR guidelines are complied with. See i Sheet 2.

(, qj DORGR IC Submergence V

At certain locations inside the containment, portions of these cables could get submerged during LOCA conditions. This complies with the requirements of the guidelines as explained in Sheet 2.

DORGR 1D Containment Sprays i

The chemical sprays used during LOCA tasting meet all the requirements except that hydrazine was not present. This complies with the requirements of the guidelines as explained in Sheet 2.

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions l

The requirements of DOR guidelines are complieQ with.

Palisades Plant utilizes redundant automatic containment spray j systems. Therefore, in accordance with DOR Guidelines, Section l

4.2, Paragraph 1, qualification for LOCA environment is adequate and additional qualification for main steam line break accident environment is not required. Refer to DORGR 1A for details of LOCA qualification.

O

\

nu0481-0284b-43 218j Rev 2 1

i l

I h

Sheet 3 (Contd)

DORGR 2B Radiation The requirements of DOR guidelines are complied with. Refer to response in DORGR 13.

DORGR 2C Submergence The requirements of DOR guioelines are complied with. Refer to response in DORGR 1C.

DORGR 2D Chemical Sprays The requirements of D0R guidelines r.'.; complied with. Refer to response in DORGR 1D.

DORGR 5 Qualification by a Combination of Methods (Test, Evaluation, Analysis)

DORGR SA Qualification by Evaluation and/or Analysis Requirements of DOR guidelines are complied with as follows:

1. Temperature, pressure, aging, chemical spray (except hydrazine), humidity and submergence by evaluation of type tests results on cables with same type of insulation. This is discussed in Sheet 2.

2. Hydrazine withstand capability of cable by analysis as discussed in Sheet 2.

DORGR SB Qualification by Type Testing

1. Simula+ed Service Conditions and Test Duration The test duration of 30 days covers the entire time until the conditions in the containment return to essentially ambient.

The test profile is that required by IEEE 383 (1974). This complies with the guidelines and is explained in Sheet 2.

2. Test Specimen This complies with the D0R guidelines. The test specimens have same type of insulation (XLP) as the installed cable.

See Sheet 2.

3. Test Sequence The requirements of DDR guidelines are complied with. Also the test sequence meets IEEE-383 (1974) requi-ements as below:

nu0481-0284b-43 218k Rev 2

O G

Sheet 3 (Contd)

a. Thermal aging

b. Radiation

c. LOCA & chemical spray

d. Post LOCA Test (dielectrics)

4. Test Specimen Aging The cables have undergone aging tests as explained in Sheet 2.

Therefore, the requirements of the DOR guidelines are met.

5. Functional Testing and Failura Criteria The requirements of the DOR guidelines are complied with.

Passed dielectric tests at 80 V ac/ mil (with a minimum of 2.2 kV for 1 minute) after aging, LOCA and long-term moisture absorption tests.

6. Installation Interfaces Mounting arrangemen, i the test speci~en during qualification testing was similar to the installed equipment at the

, Palisades Plant. This complies with the requirements of the guidelines.

I DORGR 6 Margin The requirements of DOR guidelines are complied with. Test parameters exceed the Palisades environment.

tORGR 7 Aging l

The requirements of DOR guidelines are complied with as explained in DORGR 5.B.4.

DORGR 8 Documentation The requiremer.cs of DOR guidelines are complied with. Refer to Sheet 1.

L O

i nuo481-0284b-43 2181 Rev 2

Sheet 4 O

Component 600 Volt Instrumentation Cable (Code 262)

Franklin Research Center had no comments concerning this cable.

O I

l l

I l

O l

nu0481-0284b-43 218m Rev 2 l

[

EQUIPMENT QUALIFICATION REPORT

%, %g p, y Component Sheet No:

FacNty: Palisades %

g,.

Docket: 50-255 U

ENVIRONMENT DOCUMENTATION REFERENCES OUALFICADON OUTSTANDING ENNT DESCM DON MET W ITEMS Parametw Accident Quaimcanon Accident Oues System: Operatng Miscellaneous Tkne 30 Days 12 Days Section 2, 3 Vest &

Electrical System See Sheet 2 III.B Analysis Plant 1 D Number. Tempersture Cable Codes X21 g.F) See Figures 7, 8 303*F Sec.t ion 2, 3 Test &

Thr II.D.1 Analysis Electtical Cables XLP PVC Jkt fpg*y* See Figure 9 80 Section 1, 2, 3 Test &

Rome Cable Corp II.D.1 Analysis

"""'D"~

y ggy 100 100 Section 1, 2, 3 Test &

w II.D.1 Analysis Purchase Order Number Chemical 1750 to 2000 Ppm Boric Acid 2000 Ppm, 5935-E-22-B 8PY NaOH Solution To Section 2,3,4 Test &

Boric Acid With Function 1 Service. 50 - 100 ppm N9114 Maintain nll of 9 II.D.? innivste Transmit Electrical Rademon Signals / Power & [ Rad) Note 1 5 x 10 Section 2, 3 Test &

Control II.D.5 Analysis Accuracy: Spec; Aging

40 Years Plus LOCA 40 Years Plus LOCA Section 2, 3 Test &

Locaton: II.D.8 Analysis Inside Containment %

Elevanon-. Yes Yes Section 2, 3 Test &

Various II.D.3 Analysis Flood Level Elevanon 596'-0" Above Flood 1_ewel: *Se ' Note 2 Yes: No.

DOCUMENTATION REFERENCES NOTES l

1. Franklin Institute Research LaboratorJes Final Report 1. Camma: 2 x 10 R; beta: 2 x 10 R at surface, F-C2870 September, 1970. 2 x 107 R at 0.03", 2 x 106 R at 0.07".

2. Franklin Institute Research Laboratories Final Report 2. Portions of cables are submerged. See Sheet 2 for F-23016 June, 1971 and Addendum dated August 4, 1971._ discussion. _

I J858 Of A

O U)

I Sheet 2 (Contd)

In the case of a small break LOCA or MSLB, analysis indicates that the containment temperature may attain a value up to 190*F at a pressure of 5 psig for a duration not exceeding 36 seconds prior to the initiation of contsinment high-pressure trip. The coaxial cables will be required to remain functional for the above duration only under the above stated environmental parameters.

It is concluded that the coaxial cables are qualified to function satisfactorily in the excore flux detector applications based on the following reasons:

a. The total radiation exposure for the coaxial cables will not exceed 1.8 x 10' rads over a 40-year period including post-accident exposure for one hour. Discussion under Paragraphs 2.1.1 and 2.1.2 indicates that the cable can withstand up to at least 1 x 10' rads.

b. Discussion under Paragraph 2.1.2 indicates that the cable is suitable for continuous operation at 212*F. Even though this does not provide conclusive evidence of 40-year life qualification, it

. is obvious that normal operation at 104*F is not likely to lead to s degradation of insulation.

ImI O c. Since submergence is preceded by containment spray which, in turn, i is preceded by containment high-pressure trip, the requirement for functional capability of the coaxial cables would have terminated before submergence occurs. Therefore, submergence qualification is not required.

d. These cables a p required to be functional for a very short duration only,'io11owing a LOCA and it is extremely unlikely that

! catastrophic failure can occur within a short time due to peak i pressure of 51 psig or pe:9 temperature of 278'F. The heat sink effect of the containment, combined with the thermal time l

(

constants, will protect the cable from immediate failure due to peak temperatures.

l

e. Discussion under 2.1.4 concludes that the cable is qualified for the chemical spray environment. However, as discussed under Paragraph c earlier, the cables will be required to remain

! operational for a short duration only, fol. lowing the spray i

initiation.

f. Even if it is assumed that some degree of aging degradation might occur, analysis indicates that the result is likely to be a decline l in mechanical strength. Such decline cannot be directly correlated with electrical properties and the insulation is likely to remain serviceable with relatively minor changes in electrical properties during periods of declining mechanical strength. Reducing

%/

nul080-0010a-43 263 Rev 2

Sheet 2 (Contd) mechanical strength is not a concern since these cables are already in service and not subject to cable pull operations, etc.

The power range control channels may be required to remain functional for a slightly longer duration compared to safety channels. However, the service voltage on the control channels is about five volts only and under these conditions, since the elec-trical stresses on the insulation are reduced to insignificant levels, dielectric failure is highly unlikely.

O nul080-0010a-43 64 Rev 2 9

2.

k t

i Sheet 4 4

4

Component Cable ZCX i~

This cable was not included in the November 1978 CP Co submittal and, '

l therefore, was not addressed in the Franklin Research Center report.

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i ,

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nul080-0010a-43 267 h

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

Owner: Consumers Pc ver Company Component Sheet No:

Revision Facility: Pa'sadest a

Date:

Decket: 50 255 ENVIRONMENT DOCtWENTATION REFERENCES EQUIPMENT DESCRIPTON METHOO ITEMS Parameter Accident Quaktcaton Accident Qual System: Operating Primary Coolant Time System 30 Days See Sheet 2 ,

Sec III.B See Sh 2 Evaluation Plant i D. Nurr.ber; Temperature SV-1910-1911 (*F) 92 See Sheet 2 Sec II.D.8 See Sh 2 Evaluation

' Component:

Solenoid Valve Pressure 14.7 14.7 Se II.D.8 See Sh 2 Evaluation SC0 Model Numbe<: Relative itT8320A22 H* *) 80 g See Sheet 2 Sec II.D.8 See Sh 2 Evaluation

, CD Purchase Order Number:

Chemical

! spray None Fur:ctioniservice.

NSSS Saiaple Rad.ation Containment sRad) 14 E0h 4.4E06 Sec II.D.7 1 Evaluation Isolation Valves Accuracy: Spec: Aggg Demo:

,, , 40 Years Plus LOCA See Sheet 2 Sec II.D.8 f'ee Sh 2 Evaluation Room 150 submergence Elevation: Not Subject 60h ' -3 to Submergence f toud tevel Devation Above Flood Level.

Yes No DOCUMENI ATION REFERENCES NOTES

< The Effects of Nuclear Radiation on Elastomeric and l.

to Plastic Components and Materials, et al, REIC Report #21.

085R Of A

_m t

Sheet 2 Componene ASCO Solenoid Valves SV-1910, -1911 These valves provide the containment isolation function for the NSSS sample line. The isolation signal is either CHP or CHR and occur prior to the room becoming a hostile area. The solenoids de-energize to their on-the-shelf state on the isolation signal, closing the control valves.

Another function to provide sampling has been imposed on these valves. This would require the valves to operate in the higher temperature and radiation environment on a periodic basis. The sample valves inside containment. are not qualifiable in the post-accident containment environment; therefore, the.a isolation valves need not function for sampling until qualified replacements are obtained for the sample valves. The valves will be replaced before June, 1982 to meet the post-TMI act. ion plan requirements.

i fn (J) i i

s nul080-0002a-43 269 x

-c.

Sheet 3 Comporent ASCO Solenoid Valves SV-1910, 1911 DORGR 3 Service Conditions Outside of Containment DORGR 3C Areas Normally Maintained at Room Conditions The servica :onditions for the 30-day post-accident period are T = 92*F F = 14.7 psia, RH = 80%, radiation = 4E0' rads and lifetime 40 years lus LOCA. The present required function of the valves to operate mn CHP or CHR occurs prior to the higher temperatures and radiation occurs.

Radiation is discussed in DORGR 5 and aging is discussed in DORGR 7.

DORGR 5 Qualification by a Combination of Methods (Test, Evaluation, Analysis)

DORGR SA Qualification by Evaluation and/or Analysis The methodology for calculatics the radiation dose is discussed in Section II.D.S. The dose is assumed to result fram pipes in the area carrying liquid from the containment sump. Peference 1 provides the basis for the radiation qualification to a 25%

compression set. Although the TID exceeds the qualification dose,

he valve only is presently required to operate on CHP or CHR and is not requirad thereafter.

DORGR 7 Aging V The effects of acceleratad aging due to elevated temperatures and higher than normal radiation will be experienced by the valves.

They, however, will operate (on CHP or CHR) prior to the area becoming harsh. No subseouent operating of the valve is presently required and it will remain in its de-energized on-the-shelf position. Requirements of NUREG 0588 and the post TMI action plan require a sampling system for which these valves will be required to operate. To satisfy these requirements, the valves will be replaced before June 1982.

g DORGR 8 Documentation References 1 proves the documentation.

O nul080-0002b-43 270 Rev 2

CN ['

Y %J O)

Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision Date:

Docket: 50 255 EtNIEONMENT DO':UMENTATION REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOO ITEMS Parameter Accident OuaWicahon Accident Oual System: Operating Service Pater T* Section See System 39 Davs 30 Days III.B Sheet 2 Evaluation Plant 1 D. Numbe' Tempwature

SV-0825 (* F) Section See

component: 104 104 II.D.8 Sheet 2 Evaluation Prnme Solenoid Valve Mwacturw: (PSIA)

Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation i Model Number: Relative H ' @I Section See

.u WPIIT-8300B61-RF 80 80 LI.D.8 Sheet 2 Evaluation Cl Purchase Order h Chem 6 cal J Spray Funcia/ Service: None Ser/ ice Uater Radiation to ESS Room Cooler (Red) Section 6 II.D.7 1 Evaluation 3.0 x 10 7.0 x 10 Accuracy: Spec: Agg I

U*"* Section See tocate: 1 40 Years + LOCA 40 Years + LOCA LI.D.8 Sheet 2 Eva?uation Room 123 - See Note Submwoence Not Suoject to Elevation: 1 " #8 "

1 597'-6" i

flood Level Elevate Above Flood Levet.

Yes- No:

DOCUMENTATION RLFERENCES NOTES y 1. The effect of nuclear radiation on elastomeric and 1. This component is required for a LOCA and/or MSLB

< plastic components and materials, R U King, et al, inside containment only; although Room 123 will ex-ru REIC Report #21. perience harsh environmental ccnditions in the event o f en hSLP , this equipment is not required for this

..ccident (see Section II.D.6). The valve is located 30 feet from the enntnirment un11.

G 0858 OI A

EQUIPMENT OUALIFICATION REPORT p

Facaity: Palisades RevWon:

Docket: 50 255 Date:

ENVIRONMENT l DOCUMENT ATION REFERENCES OUTSTANDING OUAUFICATION EQUIPMENT DESCRIPTION METHOO liEMS Parameta Accident Quaw a hon Accident Que System: Opsenemo Service Water

- Section See 30 Days 30 Days III.B Sheet 2 Evaluation System Plant i D. Numbo' Tempwature SV-0878 (* F) Section See C.enpornml. 104 104 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Manufacturer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Modd Number: Relative ection he fu WPitT-8300B61-RF 80 80 II.D.8 Sheet 2 Evaluation j gc% g ;

Chemical Spray Functionf Serv 6ce. None Service Water to Rwhen ESS Room Cooler (Rad) Section 4 6 II.D.7 1 Evaluation

> 4.0 x 10 7.0 x 10 Accuracy: Spec: gggg Derno: - Section See t caten: 40 Years + LOCA 40 Years F LOCA II.D.8 Sheet 2 Evaluation Room 123 - See Note Submergence Elevation: 1 Not Subject 596'-11" to Submergence Flood Level Elevahon Above Flood Level.

Yes No-DCCUMENTATIOr4 REF7RENCES NOTES l

1. The ef fect of nuclear radiation on clastomeric and L. This component is required for a LOCA and/or MSLB plastic components and materials, R W King, et al, inside containment only; although Room 123 will ex-REIC Report #21. perience harsh environmental conditions in the event of an MSLB, this equipment is not required for this accident (see Section II.D.6). The valve is located 20 feet from the containment wall. _

1 0858 01 A

/~ r n

(

EQUIPMENT QUALIFICATION REPORT p

Facety: Palisades Revision Docket: 50 255 Date:

ENVIRONMENT DOCUMENT ATION REFERENCES OUAUFICATION OUTSTANDING EOueMENT DESCRFTION METHOO ITEMS rarameler Accident Quawceton Accident Ouas Systerm Operahng

Section See Service Water System 30 Days 30 Days III.B Sheat 2 Evaluation i Plant i D. Number Temperalwe SV-0847 (*F) Section See Component. 110 110 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Manutecturer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number i Relahve Humiety (%) Seetion See m LB-831614 95 95 11.D.8 Sheet 2 Evaluation N Purchase Order Number

" Chemical y Spray l FunctmlService: None Service Water for Radet6on Containment Air (Rad) Section 5 Evaluation Coolers 4.0 x 10' 7.0 x 10 II.D.7 1 Accuracy- Spec: Aging D'** : Section See 4 Locat.on: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation i Room 238 Submergence Elevation: Not Subject

, 607'-6" to Submergence I

Flood Level j Elevatm Above Flood Level.

I Yes. No:

DOCUMENTATION REFERENCES NOTES m

$ 1. The effect of nuclear radiation on elastomeric and y plastic components and materials, R W King, et al, REIC Report #21.

l t G 0858 01 A

9 EQUIPMENT QUAllFICATION REPORT p

Redsion:

FacRity: Palisades Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANOfMG EOUIPMENT DESCRIPTION METHOO ITEMS Parameter Accident OuaWication Accident Ouas Sy> tem: Opersing Component Cooling Tw* Section See System 30 Days 30 Days III.B Sheet 2 Evaluation Plant i D Number- Temperature SV-0910,-0011,-0940 (* F) Section See Component. 104 104 II.D.6 Sheet 2 Evaluation Solenoid Valve Pressure Manufacturer: (WA) Section See ASCO 14.7 14.7 II.D.6 Sheet 2 Lvaluation M Nurnber Relatnre Section Sce HurrJdity (%)

to LB-831614 80 80 II.D.6 Sheet 2 Evaluation 7d Purchase Order Number Chemical Spray FunctiontService: None Isolation Valves on m on Compor,' ' t Cooling (Rad) Section 6 6 II.D.7 1 Evaluation Water System 1,0 x 10 7.0 x 10 Accuracy: Spec: 3 9 ,9 Demo. Section See Locaton: 40 Years 4 LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 123 - See Note % g,nc, Elevanon: 1 Not Subject 604'-3" to Submergence Flood Level Elevation Above Flood Level Yes- No.

DOCUMENTATION REFERENCES NOTES l

1. 'Ihe ef fect of nuclear radiation on elastomeric and 1. These components are required for a LOCA and/or MSLB plastic components and materials, R W King, et al, inside containment only; although Room 123 will ex-REIC Report #21. perience harsh environmental conditions in the event of an MSLB, this equipment is not required for this accident (see Section II.D.6). These valves are

^

located 2 to 5 feet from the containment wal k 0858 OI A

p

) ['\ k,.

N OM Component Sheet No:

Owner: Consumers Power Company Revision:

Facility: P$,1 des Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATON OUTSTANDING EQUIPMENT DESCRIPTON METHOD IT~ J-Parameter Accident Quai f. cation Accident Oua,

~*

{

l System: Operaung Componen t Cooling ** Section See 30 Days 30 Days III.B Sheet 2 Evaluation 1 System Plant i D. W Tornperature SV-0937,-0938 t* F) Section See Component. 104 104 II.D.6 Sheet 2 Evaluation l Solenoid Valves Pressure Section See M'enufacturer (PSIA) 14.7 14.7 II.D.6 Sheet 2 Evaluation AS CO Model Number: Relative

"I " ""

I Evaluation ro LB-831614 80 80 II.D.6 Sheet 2 y

y Purchase Order Number Chem 6 cal Spray None Function / Service.

Component Cooling Radenon IR*d) Section Water to Shutdown 6 II.D.7 1 Evaluation l.0 x 10 7,0 x 10 llX Accuracy: Spec. Ag.ng Derno 3ection See Location: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Svaluation Room 123 - See Note Submergence Elevotton: 1 Not Subject

'397'-2", 602'-2" to Submergence Flood Level Elevation Above Flood Level:

Yes No.

I NOTES I DOCUMENTATON REFERENCES l w 1. These components are required for a LOCA and/or MSLB )

@ 1. The effect of nuclear radiation on clastomeric and inside containment only; although Room 123 will ex-

,o plastic components and materials, R U King, et al, perience harsh environmental conditions in the event REIC Report #21, o f an MSLB , this equipment is not required for this accident (see Section II.D.6). i heso. valves are lo-c.ated 25 feet from the containment wall . j G 0858 01 A

' Component Sheet No:

Owner: Consumers Power Company Revision:

Fauhty: Pahsades Date:

Docket: 50-255

' ENVIRONMENT DOCUMENTAflON REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METH T ITEMS Parameter Accident OuaWicaton Accident Oua, System: Operatwig T* Section See Shield Cooling Evaluation 30 Days 30 Days III.B Sheet 2 Plant i D. Numbe' Temperature t* F) Section See SV-0939 component: 104 104 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Section See Manufacturer: (PStA) 14.7 14.7 II.D.8 Sheet 2 Evaluation ASCO Model Number Relanve

" "U " ""

m WPliT-8300B61-RF 80 80 II . D. 8 Sheet 2 Evaluation g Chemical Spray Funct6on/ Service.

None Shield Cooling Redeuon Makeup Containment (Rad) Section 6 II.D.7 1 Evaluation Isolation 4.0 x 10 7.0 x 10 Accuracy: Spec: Aging

"' Section See

' C*": 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 123 - See Note Elevation: 1 Not Subject 602'-9" to Submergence Flood Level Elevatm Above Flood Level:

Yes No .

DOCUMENTATION REFERENCES NOTES

1. This component is required for a LOCA and/or an MSLB

1. The ef fect of nuclear radiation on clastomeric at.d inside containment only; although Room 123 will ex-plastic components and materials, R W King, et al, REIC Keport #21. perience harsh environmental conditions in the event of an MSLB, this equipment is not required for this accident (see Section II.D.6). The valve is located 20 feet f rom the containment wall. _

0858 oI A

R I .D (G )

\ (G Owner: Consumers Power Company Component Sheet No:

Facihty: PaEsades Revision:

Dociret: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRtPTION METHOO ITEMS Parameter Accident Ouahncanon Accident Oual System: Operahng Component Coolit.. Time Section See System 30 Days 30 Days III.B Sheet 2 Evaluation Plant I D. Numbe' Temperature SV-0944 A ('FI Section See Component: 104 104 II.D.6 Sheet 2 Evaluation Solenoid Valves Preuure Manutecturer: (PSIA) Section See ASCO 14.7 14.7 II.D.6 Sheet 2 Evaluation Model Number Relahve Hum my(%I Section See ThT-63 +1 1 4 - Al Sheet 2 Evaluation 80 80 Il.D 6 Chemical Spray

- Functm/ Service. None Radunon CCW to Radwaste and '"

I"*dI Fuel Pool CLG 4 6 LI.D.7 1 Evaluation 4.0 x 10 7.0 x 10 Accuracy: Spec: gg

- Section See L C8 a: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 123 - See Note ; ubmergence i Elevanon. 1 Mot Subject l

592'-1" to Submergence flood Level Elevahon Above Flood L:, vel-Yes- No

~

DOCUMENTATK)N REFERENCES NOTES m 'these components are required for a LOCA and/or MSLB

l. The effect of nuclear radiation on elastomeric and 1.

Q plastic components and materials, R W King et al, inside containment only; although Room 123 will ex-g REIC Report #21. perience harsh environmental conditions in the event of an MSLB, this equipment is not required for this accident (see Section II.D.6). The valves are located 20 feet f rom the containment wall.

G 0858 01 A

EOutPMENT QUALIFICATION REPORT p

Revision:

Facility: Pahsades Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATK)N REFERENCES OUAUFICATION OUTSTANOING EOUtPMENT DESCRIPTION METHOD ITEMS Parameter Accident Oueliteetion Accident Oues System: Operahng h Section See Component Cooling Sheet 2 Evaluation System 30 Days 30 Days III.B Plant i D. Number Temperature SV-0945,-0946 l*F) Section See Component. 104 104 II.D.6 Sheet 2 Evaluation Solenoid Valves Renwe I

Manutxturer: (PSIA) Section See ASCO 14.7 14.7 II.D.6 Sheet 2 Evaluation Model Number Relative HumkSty (%) Section See LB-831614 80 80 II.D.6 Sheet 2 Evaluation g _

O Chemical Spray Function / Service:

None Component Cooling Redist6on Section (Red)

Water Valves 0 6 II.b.7 1 Evaluation 2.5 x 10 7.0 x 10 Accuracy: Spec: Aging Section See L C#'oa: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 123 - See Note submergence Elevanon. 1 Not Subject ,

599 '- 0" , 59h'-6" to submergence

~ Flood Level Elevehon Above Fhod Level.

Yes- No:

DOCUMENTATION REFERENCES NOTES l

0 1. The effect of nuclear radiation on elastomeric and L. These components are required for a LOCA and/or llSLB to plastic components and materials, R W King, et al, inside containment only; although Room 123 will ex-REIC Report #21. perience harsh environmental conditions in the event of an HSLB, this equipment is not required for this accident (see Section II.D.6). These valves are 10-

^ -

cated 30 feer fmm rho en n t n i n mo n e wall. _

0858 01 A

O O)

Q) \

- O) u Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD liEMS Pwameter Accident Ouew. cation Accident Quas System: Ope.ahne Tirne Section See Radwaste System 30 Days 30 Days III.B Sheet 2 Evaluatian Plant 1 D. Nurnbe' Temperature See Note 1 (* F) Section See Corwent. 92 92 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure

Manufacturer: (PSIA) Section See i ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Relatrve Hu"*S Y( ) S ction See pa 'vPitT-8300B61-RF 8 8 I . D. 8 Sheet 2 Evaluation p Purchase Order Number:

Chemical Spray Funct6on/ Service: None PSDT cnd 01RT Radiation Containment Isola- (Rad) Section 6 II.D.7 1 Evaluation tion Valve 4.0 x 10 7.0 x 10 Accuracy: Spec: AQing Derno. Section See Loc 8 hon: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 150 - Note 2 Submergence ;

Elevation: Not Subject See Note 3 to Submergence Flood Level Elevat e

, Above Flood level:

Yes. No:

DOCUMENTATION REFERENCES NOTES

$ 1. The effect of nuclear radiation on elastomeric and 1. SV-1001, -1004, -103T, -106h and -1065 plastic components and materials, R W King, et al, 2. These valves are located 1 to 5 feet from the REIC Report #21. containment wall.

3. Respective eleva :ons:

606 '-8" , 606 '-8" , 604 '-8" , 60h '_8" , 60h '-8" G o858 01 A

soutPMENT OUAUFICATION REPORT

%ner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision:

Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAtyCATION OUTSTANDING EQUIPMENT DESCRIPTION MEMOD ITEMS Parametw Accident Ouahicate Accident Ouan System: Operahng Radwaste System Tim

Section See 30 Days 30 Days III.B Sheet 2 Evaluation Plant i D. Numb" Temperature SV-1002,-1007,-1036 ('F) Section See

component. 80 80 II.D.8 Sheet 2 Evaluation Salenoid Valve Pressure Manufacturer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Relative "U ' "

to WPitT-6300B61-RF 80 Sheet 2 Evaluation co 80 II.D.8 to Purchase Order Number Chemeal Spray Functiont Service.

None PSDT and CWRT Radiation Containment Isola- (Rad) Section 6 II.D.7 1 Evaluation tion Valves 4.0 x 10 7.0 x 10 Accuracy: Spec: Agan0 D*"*: Section See tocaton: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 118 - Note 1 %g, Elevation: Not Subject Note 2 to Submergence Flood Level Elevaton Above Flood Level:

I Yes No.

DOCUMENTATION REFERENCES NOTES l l to These valves are located 2 feet f rom the containment 4

< l. The ef fect of nuc.) ar radiation on elastomeric and 1.

M plastic components and materials, R W King, et al, wall.

REIC Report #21.

2. Respects.v., elevations:

596'-4" , 55 '-1" , 59 5'-3" 658 01 A

t O i O

\

L. %)

EQUIPMENT OUALIFICATION REPORT p

Facility: Palisades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDNG EOUtPMENT DESCRIPTION METHOO ITEMS

- Paramela Accident &mtion . Accident Oua, System: Operanno Radwaste System T* Section See 30 Days 30 Days III.B Sheet 2 Evaluation Plant i D. Number Tempwature SV-1038,-1044,-1045 (* F) Section See Component. 92 92 II.D.8 Sheet 2 Evaluation Solenold Valve Pressure Manutecturer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Rotative Hum myt%) Section See WPitT-8300B61-ItF

$ 80 80 II.D.8 Sheet 2 Evaluation u Purchase Order Numba Chemical Spray Functm/ Service.

None Rahuon 9 CWRT Containment isolation Valves I"*dI '"

5 6 II.D.7 1 Evaluation 3.0 x 10 7.0 x 10 Accuracy: Spec: g g,ng D*"* Section See Loc 8'*a: 40 Years + IDCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 118 - Note 1 Submergence Elevat6on: Not Subject Note 2 to Submergence i Flood Level Elevahon 1 Above Flood Level.

Yes: No:

y DOCUMENTATION REFERENCES NOTES g 1. The ef fect of nuclear radiation on elastomeric and 1. These valves are located 3 feet from the containment plastic components and materials, R W King, et al, wall.

REIC Report #21.

2. Respective elevations:

l 595'-2", 595'1", 596'-5" l

G 0858 0t A I

EOUlPMENT QUALIFICATION REPORT p

Revision:

Facuity: PaEsades Date:

Dockel: 50 255 ENVIRONMENT DOCUMENTATION REYERENCES OUTSTANOING OUAUFICATION EOUtPMENT DESCRIPTION Accident Quas usTHoD ITEMS Parameter Accident Ouaktication System: Operatwie

Section See Waste Gas System 30 Days 30 Days III.B Sheet 2 Evaluation

~

Plant I D. Number: Temperature SV-1101, 1102 (* FI Section See component: 92 92 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Manufacturer: (PSIA) Section See ASCO 14.7 14.7 LI.D.8 Sheet 2 Evaluation Model Number Relative to WPitT-8300861-RF 80 80 II.D.8 Sheet 2 Evaluation cu Purchase Order Number 4-Chemical Spray Function / Service. None IMDT Containment Ra$stkwt Isolation Valves (Rad) Section 6 II.D.7 1 Rveluation 4.0 x 10 7.0 v in Accuracy: Spec: gg,3g Dem Section See tocation: 40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation Room 150 - Note 1 Submergence i Ekvation. Not Subject 606'-3", 606'_1" to Submergence.

flood Levet Elevation Above Flood Level.

Yes No DOCUMENTATlON REFERENCES NOTES l

0 1. The effect of nuclear radiation on elastomeric and 1. The valves are located 4 to 5 feet from the contain-to plastic components and materials, R W King, et al, ment wall.

REIC Report #21.

- _ h 0858 Of A

O O O EOUtPMENT QUALIFICATION REPORT p

Facility: Palisades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANOING EOutPMENT DESCRIPTION METHOD ITE MS Pararqter Accident Qualehcation Accident Oues System: OpernM Radwaste System Section See 30 Days 30 Days ITT.B Sheet 2 Evaluation Plant i D Number Tempwature

(*FI Section See SV-1103, 1104 component: 80 80 II.D.8 Sheet 2 Evaluation Solenoid Valve Pre m me Manufactwer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Reletve Hun

sty t%) Section See WPi -8300 l 80 80 II.D.8 Sheet 2 Evaluation der N Chemical Spray

, Function / Service: None Containment Sump Radiation Drain Isolation (Red) Section 6 6 II.D.7 l Evaluation Valves 1.0 x 10 7.0 x 10 _

Accuracy. Spec: Ag Section See L CC

40 Years + LOCA 40 Years + LOCA II.D.8 Sheet 2 Evaluation See Note 1 Submergence Elevallon: Not Subject 586'-0", 586'-8" to Submergence Flood Level Elevation Above Flood Level Yes No DOCUMENTATION REFERENCES NOTES to

1. The effect of nuclear radiation on elastomeric and 1. Next to ESF room near 4" containment penetration.

m plastic components and materials, R W King, et al, REIC Report #21.

G O650 0t A

EQUIPMENT GUAllFICATION REPORT Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsades Revision:

Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFEFIENCES Accident Ou=, METHOD ITEMS Parameter Accident Ouahhcahon System: Operating I Miscellaneous Tin

Section See Gas Supply 30 Days 30 Days III.B Sheet 2 Evaluation Plent i D Number- Temperature SV-1358 ri Section See Component. 92 92 II.D.8 Sheet 2 Evaluation Solenoid Valve p, essure Manutecturer: (PSIA) Section See ASCO 116 .7 116 . 7 II.D.8 Sheet 2 Ev 'uation Mr el Number: Relative He m ec M on See m WPIIT 8300B61-RF 80 80 II.D.8 Sheet 2 Svaluation cn Os Purc use Order Number Chemical Spray Function / Service. None b Radiation Ni trogen Isolation (Rad) Iection Valve 0 6 II.D.7 1 Evaluation 2.0 x 10 7.t) x 10 ,

Accurar y' Spec: Aging D*"*: Section See Locate: 10 Year s + IDCA 4 10 Years + IDCA 4 II .D.8 Sheet 2 2 valuation Room R150 Note 1 wergence Elevot6on: Not Subject 605'-7" to Submergence Flood Level Elevatson Above Flood Love':

Yes No-DOCUMENTATION REFERENCES NOTES

1. The effect of nuclear radiation on elastomeric and 1. The valve is located ten feet from the containnient plastic components and materials, R W King, et al, wall.

REIC Report #21.

J858 OI A

O O O V V O EQUIPMENT QUALIFICATION REPORT ,

Facility: Palisades Reh * '

Docket: 50-255 Date:

EQUIPMENT DESCRW' TION

[ ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDING w METHOD ITEMS Parameter Accident OuaWession Accident System: Olioratino Heating, Ventilating Th* Section See and Air Conditioning 30 Days 30 Days TTT.B Sheet 2 Evaluati on Plant I D. Number Temperature SV-1501, 1502, 1503 (* F) Section See component: 92 92 II.D.8 Sheet 2 Evaluation Solenoid Valve p,,,,,,,

Manufacturer: (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation I

Model Number Relative Hety N Section See ro WPHT 8300861-RF 80 80 II .D.8 Sheet 2 Evaluation g ,

Chemical Spray Function / Service.

None Steam Heat %: ion Containment (Nd) 6

iection Isolation Valves 4.0 x 10 7.0 x 10 [I.D.7 1 Svaluation Accuracy: Spec: Aging Demo: 3ection See Loc tion: 40 Years + IDCA 40 Ye'ars + IDCA [I .D.8 Sheet 2 Byaluation

. Room 150 Note 1 Suw ne o

Elevation: ilot Subject Note 2 to Submergence flood Level Elevaton

! Above Flood Level:

_ - :.. No-DOCUMENTATION REFERENCES NOTES to y L. The effect of nuclear radiation on elastomeric and 1. The valves are located 5 feet from the containment g plastic components and materials, R W King, et al, wall.

REIC Report //21.

2. Respective elevations,: -

l 605'-11", 605'-10", 605' *;"

I

, G 0858 01 A b

EQUIPMENT QUAUFICATION REPORT ,

FacOy: Palisades Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATON REFERENCES QUAUFICATON OUTSTAN0edG EOUIPMENT DESCRtPTION ,

METHOD ITEMS Parametw Acciden*. Ouahncetion Accident Qua, System: Operating Heating, Ventilatint Tw Sect?on See and Air Conditionine 30 Days 30 Days III.B Sheet 2 Evaluation Ptent i D. Numbef- Temperature SV-1813, 1814 t ri Section See i component 92 92 II.D.8 Pheet 2 Evalu.'. tion Solenoid Valve Pressure Manutacturw: (PSIA) SeCtion P ?e STO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Reintive

"""'d"V ist Section See g La 831624 80 80 II.D.8 Sheet 2 Evaluation oo Purchese Order Number criemical Speer Function / Service. None Air Room Purge Radiation Containment Isola- (Rad) Section tion Valves 0 II.D.7 1 ?.valuati on 3.0 x 10 7.0 x 10 Ar: curacy: Spec: Agog Demo: Section See '

Loceton- 10 Years + LOCA 4 4') Years + IDCA II.D.8 Sheet 2 Svaluati on Room 150 Note 1 ,

Elevenon: Not Subject to Submergence 603' 4", 601'-2" 4

Flood Level Elevatica Above Flood Level:

Yes Peo

n G DOCOMENTATON REFERENCES NOTES t

y l ro 1. The effect of nuclear radiation on elastomeric and 1. The valves are located 7 feet from the containment plastic components and materials, R W King, et al, wall.

REIC Report #21.

W _

0858 Ot A

t'% p n U V U EQUIPMENT QUALIFICATION REPORT ,

Revision:

Facility: PaEsades Date:

Docket: 50-255

) ENVIRONMENT DOClIMENTATION REFERENCES OUALIFICATION OUTSTANDING

! EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Oudricamon Accident Qua, System: Operating Chemical Volume TL= Section See Control 30 Days 30 Days III.B Sheet 2 Evaluation Plant i D. humber Temperature See SV-2009, 2083 (*F) Section Component: 92 9^ II.D.8 Sheet ^ Evaluation Solenoid Valve Pressure Manutecturer: (" SIAL Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Relahve Hun.dty (%) Section See g WPHT 8300B61-RF 80 80 II .D.8 Sheet 2 Evaluation O Purchase Order Number:

Chemical Spray Function / Service:

%ne PC Letdown and m uon PC Pump Controlled (Rad) 3ection Bleed Off Isolation 6 rI.D.7 1 10 valuation 4.0 x 10 7.0 x 10 Accuracy: SpecValves g D'*0: 3ection See Location: 40 Years + IDCA 40 Years + IOCA [I.D.8 Sheet 2 E' valuation Room 150 Note 1 %,nc, Elevation: Not Subject 004'-8" to Submergence Flood Level Elevat.9n Above Flood Level: '

Yes- No:

DOCUMENTATION REFERENCES NOTES

n 6 1. The Effect of "uclear Radiation on Elastomeric and 1. The valves are located 1 to 5 feet from the Plastic Components and Materials, R W King, et al, containment wall.

REIC Report #21.

G 0858 01 A

Sheet 2 Component ASCO Solenoid Valves This equipment is required for LOCA and/or MSLB inside containment only.

The ares is maintained at normal, nonharsh, environmental conditions with respect to temperature, pressure and humidity. Therefore, this equipment does not experience significant stress due to a change in service conditions during an accident and the guidelines are met for these three parameters. The accident radiation dose has been calculated for the valve (s) based on its location from the containment wall and its location with respect to contain-ment penetrations, reference Section II.D.7. The qualification radiation dose at which the most susceptible elastomer becomes degraded (25* compression set) has been determined from Reference 1. The qualification of the v21ves, with respect to the radiation dose, is based on the reference data exceeding the calculated dose value. Age sensitive materials will be replaced in valves as necessary and then inspected per manufacturer's instructions. Initial inspec-tion and replacement of parts will be completed by June 30, 1982.

O l

l l

t O

! nu0481-0284c-43 290 l

l l

l

( D D t

( (V Owner: Consurners Power Company Cornponent Sheet No:

Facdity Pahsades Flevision:

Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAttFICATION OUISTANOWG EQUIPMENT DESCRIPTION METHOD HEMS Parameter Accident Quak hon Accident Qual System: Operating Chemical and Time 30 Days 30 Days Section 1 Test Volume Control III.B.

Plant I D Number; Temperature SV-2113, -2115 (*F) 278 346 Section 1 Test Component: Note 1 II.D.1 Solenoid Valve Pressure Manufacture,. (PSsA) 70 125 Section 1 Test ASCO Note 2 II.D.1 j Model Number Re'ative Hu"*8',y gg, 100 100 Section 1 Test m WPXilVA2023012F II.D.1 o

W Purchase Ordeer Number Ctemical 1750 to 2000 ppm Boric Acid Secti.on 1 Test 16J56 **V Boric Acid With See Sheet 2 Function / Service 50-100 ppm N 1I24 Charging System Radetton 8

Stop Valves (Rad) 2 x 10 2 x 10 Section 1 Test II.D.5 f Accuracy: Spec: A060 j Demo: 40 Years Plus LOCA 18 Years Plus LOCA Section 1, 2 Test &

i tocal;on: II.D.8 Ana1,9 is

'ontainmen t submergence

. Elevation: None l 011'-l1" I

f sood Level l Elevation 596'-0"

! Above Flood Level j Yes X No.

DOCUMENTATION REFERJNCES NOTES

1. ASCO Test Report No AQS21678/TR, Rev A. 1. For LOCA, 278 F; for MSLB, 3:10 F. See Section II,

" Figures 7, 8 and 10.

2. ASCO letter with attached interof fice correspondence W M Brown to M R Wade dated September 16, 1980. 2. See Figures 9 and 10.

GOMH0lA

EQUIPMENT QUAllFICATION REPORT Owner: Consumers Power Company Component Sheet No:

Facetity: Palisades Revision:

Docket: 50 255 Date:

' ENVIRONMENT DOCUMENTATION REFEDENCES

s OUALIFICAT80N OUTSTAtotNG EOutPMENT DESCRIPTION METHOD llEMS Parameter Accident ! Quahtication Accident Oual System Operating Chemical and Trne 30 Days 30 Days Section 1 Test Volume Control III.B Plant 1 D. Number: Temperatae 278 346 Section 1 Test SV-2117 (*F) component. Note 1 I1.D.1 Solenoid Valve Pressure Test Manufacturer; (PSIA) 70 125 Section 1 ASCO Note 2 II.D.1 Model Number Hetative 100 100 Section 1 Test m IITX-8320A16V im m II.n,1 so F Purche*e Order Number:

chemical 1750 to 2000 ppm Boric Acid Sec'cion 1 Test D '# Boric Acid With See Sheet 2 II.D.2 Function / Service. 50-100 ppm N 1I24 Pressurizer nadiation 8 Test Auxiliary Spray (Rad) 2.0 x 10 2.0 x 10 Section 1 Valve II.D.5 Accurney. Spec: Aging Desm) 40 Years Plus LOCA 18 Years Plus LOCA Section 1, 2 Test &

tocat ca II.D.8 Analysis Containment h rgence Elevation: None 611'-11" t kx>o te ot Elevation 596'-0" A') ova Flood level.

Yes X No DOCUMENTATION REFERENCES NOTES m

1. ASCO Test Report No ACS21678/TR, Rev A. 1. For IDCA, 278'F; for MSLB, 380*F. See Section II,

" Figures 7, 3 and 10.

2. ASCO letter with attached interoffice memo, W M Brown to M R Wade dated September 16, 1980. 2. See Figures 9 and 10.

~ - _ . DM8 01 A

SV-2113, -2115, -2117 Sheet 4 Component Solenoid Valves for Charging System and Pressurizer Aux Spray Valves The solenoid valves were part of the November 1978 CP Co submittal. Franklin Institute's comments on Page 9, Item 3, and Item 3.3.3.1, Page 22, are responded to below.

Based on the Franklin review to Engineering Report 112, it was concluded there was no basis to qualify the 202-301 model valve and since Report 110 was not available, there was no documentation to support any qualification for the 8320 model valve. Also, as stated by Franklin, the Report 112, which is identical to Report 110 except for the valve tested, does not provide required qualification as only temperature arsd seismic testing were done and radiation, humidity, chemical spray and pressure qualification was based on analysis and knowledge of materials as well as previous testing. ASCO has stated the subject valves contain materials identical to those in the valves tested identified in Test Report AQS21678/TR, Revision A. The enclosures for the subject valves are similar or less protective than the enclosures for the tested valves. Because of the similarity, the qualification test which provided thermal, radiation, wear aging, seismic simulation, vibration endurance, accident radiation and simulated LOCA is the basis for the qualifi-cation of the subject valves to the guideline requirements.

O t

nu0930-0513a-43 299 l

\

..s EQUIPMENT OUALIFICATION REPORT ,

Facihty: Pahsades Reh Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDING EOUtPMENT DESCRIPTION MEUtoD ITEMS Parameter Accident Ouawicamon Accident Oua:

System. Operatog Engineered Time Section See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant I D. Numt*' Temperature SV-3001, -3002 (*F) Section See Component. 80 See Sheet 2 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Mam,tacturer: (P$lA) Section See ASCO O.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Relahve "N " #

La WPHT 83MB61-RF 80 See Sheet 2 II.D.8 Shcet 2 Evaluation 8 Purchase Order Number Chs:nical Spra'y Funct6on1 Service.

None Containment Rachatton Spray Valves (Rad) Section J x 10 $ 7.0 x 10 6

II.D.7 1 Evaluation 1

Accuracy: Spec: Ag g D'*o ' Section See Locator 40 Years + LOCA See Sheet 2 II.D.8 Sheet 2 Evaluation Room 121B Submergence Einvahon: Not Subject 605'-11" to Submergence

, f tood Level Elevate Above Flood Level.

Yes No.

DOCUMENTATION REFERENCES NOTES l

j 1. The Effects of Nuclear Radiation on Elastomeric and m Plastic Components and Materials, R W Kine;, et al, ,

REIC Report #21.

r >

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^ Component Sheet No:

Owner: Consumers Power Company Facihty: Pahsades Revision:

i Date:

i Docket: 50 255 ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRsPTION METHOD ITEMS Parameter Accident Quawicelen Accident M I Operating System:

Engineered T'm Section See Safeguards System 30 l>ays See Sher. 2 ITI.B Sheet 2 Evaluation j Plant 1 D Number. Temperature i SV-3018, 3036, 3059 t*F) Section See l 30gog,1 135 See Sheet 2 II.D.8 Sheet 2 I: valuation j Solenoid Valve Pressure Menulacturer: (PSIA) Section See '

I ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation

Model Number Relehvo

"""'"'ty N Se tion See i LB 8316C 44 See Sheet 2 II .D.8 Sheet 2 c: valuation l

$g Purchese Order Number:

100 Chem 6 cal j Spray FunctiontService. None Safety Injection Radiation

and Shutdown (Red, 6

Section Cooling Valves 7 7.0 x 10 II.D.7 1 Evaluation

[ 1 x 10 l Accuracy. Spec: Ag,ng j D'mo Section See

. Location- 40 Years + IDCA See Sheet 2 II.D.8 Sheet 2 Evaluation ESP Room Submergence Elevanoa: Not Subject i Note 1 to Submergence iluod Level l Elevahon Above Flood Level I Yes No I

DOCUMENT ATION REFERENCES NOTES e

! < 1. The Effects of Nuclear Radiation on Elastomeric and 1. Respective elevations:

j N Plastic Components and Materials, R W King, et al, 571a'_14", 576'-3", 576'-2", 582'-2", 579'-9"

REIC Report //cl.

j G 08sB01A

EQUlPMENT GUALIFICATION REPORT Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsados Revision:

Docket: 50 255 Date:

OUALIFICATON OUTSTANDeNG EQUIPMENT DESCRIPTON METHOD ITEMS Parameter Accident Ouawication Accident Oug System. Opersico Engineered Tune Section See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant i D Numbe' Temperature SV-3027A (*O Section See Component. 135 See Sheet 2 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure

, Manufacturer; (PSIA) Sec ti on See ASCO 14.7 14.7 II.D 8 Sheet 2 Evaluation Model Number- Hetative

"*"** N 8* I" 8**

LB 8316C-34

$e Purchase Order Number-100 See Sheet 2 II.D.8 Sheet 2 Evaluation P Chem 6 cal l Spray Function t Service None SIRW Tank Level nadiation Controlled Valve (Rad) 7 6 Section 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Accuracy Spec ag,ng Demo Section See tocat.on 40 Years 4 UX'A See Sheet 2 II.D.8 Sheet 2 Evaluation ESP Room ,

Elevaton: Not Subject 578'-1" to Submergence ftuod Level Elevaton Above Flood level yes No DOCUMENTATON REFEHENCES NOTES

1. The Effects of Nuclear Radiation on Elastomeric and Plastic Components and Materials, R W King, et al.

REIC Report #21.

9 _ _ ,58 0t A

O v v

)

J Owner: Consumers Power Company Component Sheet No:

Facility: Pahsades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANOING EOUtPMENT DESCRIPTION METH O ITEMS Parameter Accident OuaWicalon Accident Qual System. Operstmo Engineered Time Section See Safeguards System 30 Days See Sheet 2 ITT.B Sheet 2 Evaluation Plant i D. Number: Temperature SV-3027B, 3029A, (*Fi Section See 30}0ft Q q31A 135 See Sheet 2 II.D.8 Sheet 2 Evaluation Solenoid Valve pressure Manufacturer; (PSIA) Section See ASCO 14.7 14.7 1 II.D.8 Sheet 2 Evaluation Model Number: Relehvo gm,y gg Section See LB 8316C-36 100 See Sheet 2 II.D.8 Sheet 2 Evaluation u Purchase Order Number:

$ Chemical Spray Functum/ Service. None SIRW Tank Level Radiate Controlled Valves (nad) * "

7 6 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Accuracy- Spec. Aging Demo Section See Locatorr 10 Years + LOCA 4 See Sheet 2 II.D.8 Sheet 2 Evaluation ESF Room Elevanon. Not Subject Hete 1 to Submergence fluod Level Elevaton Above F.aod Level Yes No.

DOCUMENTATION REFERENCES NOTES

1. The Effects of Nuclear Radiation on Elastomeric and 1. Respective elevations:

m Plastic Components and Materials, R W King, et al, 375'_l", 578'-0", 573'-5", 582'-10" REIC Report #21.

G O858 01 A

' Component Sheet No:

Owner: Consumers Power Company Facihty: Pahsades Revision:

Docket: 50-255 Date:

OuaurtCATION OUTSTANDING EQUIPMENT DESCRIPitON METHOD ITEMS Parameta Accident Ouawication Accident Oug System. Operalso Engineered Tm Section See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant i D Number: Temperature SV-3029B, 3031B, t Fi Section See 30Moonent. 135 See Sheet 2 II.n,8 Sheet 2 Evaluation Solenoid Valve Pressure Manufacturer. (PSIA) Section See ASCO 114 .7 114 .7 II.D.8 Sheet 2 Evaluation LB 8YNI sumiEty is Seetion See W

(Note 1)

Purchase Order Number:

100 See Sheet 2 II.D.8 Sheet 2 Evaluation S Chemical Spray Functkm/ Service. None SIRW Tank Level nadiatkm Controlled Valves (Rad) 7 g Section 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Accuracy Spec: Agog Demo Section See Location 40 Years + LOCA See Sheet 2 II.D.8 Sheet 2 Evaluati on ESP Room g ,

Elevaton. Not Subject Note 2 to Submergence Flood Level Elevation Atsove Flood Level' Yes No DOCUMENT ATION HEFERENCES NOTES

,, l 0 1. The Effects of Nuclear Radiation on Elastomeric and 1. SV-3029B is Model No LB 8316Chh to Plastic Components and Materials, R W King, et al, REIC Report #21. 2. Respective elevations:

578'-10", 583' h", 583'-1"

- . _ v58 O t A

q !Q (~

b V t Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision:

Docket: 50-255 Date:

t ENVIRONMENT DOCUMENTATION REFERENCES OUAurlCATION OUTSTANOING EQUIPMENT DESCRtPTION METHOD ITEMS Parameter Accident Ouancaton Accident Oua, System: Operateg l Engineered Inne Section See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation j

Plant I D. Number: Temperature SV-305SB tr Section See Component. 135 See Sheet 2 II.D.8 Sheet 2 dvaluation

Solenoid Valve Pressure i Manufacturer; (PSIA) Section See 1 ASCO 1 .7 14.7 II.D.8 Sheet 2 Evaluation Model Number. Rela'tive i LB 83160-34 Humuty(M Seetion See 1

u Purchase Order Number:

100 See Sheet 2 II.D.8 Sheet 2 Evaluation i g Chemical

! Spray s funcuan/ Service. ' 300

~

Shutdown Cooling Radianon Heat Exchanger (nad) * " 0**

7 6 Isolation Valve 1.0 x 10 7.0 x 10 TI.D 7 Sheet 2 Evaluation Accuracy' Spec: Ag no Demo Section See i

Locat.on: 40 Years + IDCA See Sheet 2 II.D.8 Sheet 2 Evaluation ESP Room Elevehon: Not Subject 578' 6" to Submergence

, ilood Level

Elevabon i Above Flood Level No Yes DOCUMENTATION REFERENCES NOTES

! 1. The Effects of Nuclear Radiation on Elastomeric and i Plastics Components and Materials, R W King, et al, i REIC Repol' #21.

l i

G 0858 OI A

EQUlPMENT OUAl.lFICATION REFORT Owner: Consumers Power Company Component Sheet No:

Facihty: Palisades Revision:

Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATK)N REFERENCES OUAUFICATION OUTSTANOING EQUIPMENT DESCRIPTK)N METHOD ITEMS Parameter Accident Ouakticat e Accident l Oual System. Operetno !

Engineered Tune Section ' See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant i D. Number: Temperature SV-3096A, B,-3057A (* r) Section See

%, 135 See Sheet 2 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Manutecturer; (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluati >n Model Number Relative Humidity (%) Section See I.B 8316C (Note 1) 100 See Sheet 2 II.D.8 Sheet 2 Evaluation u

LB-8316C Purchase der Number:

$ Chemical Spray None runctmeService SIRW Tank Level Radiatkm i Controlled Valves (Rad) 7 g Section 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Accuracy Spec- Ag,ng Demo Section See tocat.on 40 Years + IOCA See Sheet 2 II.D.8 Sheet 2 Evaluation ESF Room %,,,,

Elevation. Hot Subject Note 2 to Sutmergence i

F tood Level Elevat.on Above Flood ievel Yes No DOCUMENTATION REFE'IENCES NOTES l

$ 1. The Effects of Nuclear Radiation on Elastomeric and 1. SV-3056A is Model No LB-8316C36.

ro Plastic Components and Materials, R W King, et al, REIC Report #21. 2. Respective elevations:

578'-2", 575'-2", 580'-9"

r'S d s.) b i

Owner: Consumers Power Company Component Sheet No:

Revision:

Facihty: Pahsades l Date:

Docket: 50 255 i

ENVIRONMENT DOCUMENTATION REFERENCES Ot;AUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS j Ps ametw Accident QuaW6caten Accident Oual

' Systeer Operatino Engineered Tune Section See Safeguards System 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant i D. Numbef Temperature SV-3213A i ri Section See Com m t. 135 See Sheet 2 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure (PSIA) Section See Manufacturer:

ASCO I

I+7 136 .7 II.D.8 Sheet 2 Evaluation Model Number. Relative See Humi*ty(N Seetion LB 8316C 16 4

! W 100 See Sheet 2 II.D.8 Sheet 2 Evaluation Purchase Order Number:

4 S Chanicas Spray 3 FunctiontService. Hune Safety Injection Radiation and Shutdown (Rad) 7 6 Section 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Cooling Valves j Accuracy: Spec; Aging Demo Section See Locaton- 10 Years + LOCA 4 See Sheet 2 II.D.8 Sheet 2 Evaluation Submergence a

Elevahon: Not Subject 578'-O" to Submergence flood Level Elevation

Above Flood Level Yes No DOCUMENTATION REFERENCES NOTES

1. The Effects of Nuclear Radiation on Elastomeric and Plastic Components and Materials, R W King, et al, REIC Report #21.

G O858 OV A

Owner: Consumers Power Company Compone.'t Sheet No:

Facihty: Pahsades Revision:

Docket: 50-255 Date:

OUALIFICATION OUTSTANOING EOuePMENT DESCRfPTION -

METHOD ITEMS Parameter Accident Oumcation Accident Quas System: Operstmo Engineered The Section See Safeguards System 30 Days See Shee' 2 III.B Sheet 2 Evaluation Plant 1 D. Number: Temperature See Note 1 (*F) Section See compon.nt. 135 See Sheet 2 II.D.8 Sheet 2 l Evaluation Solenoid Valve p,,,,,,,

(PSIA) Section See Manufacturer:

ASCO 14.7 14.7 II.D.8 Sheet 2 Evaluation Model Number Hetative

""'ety t%1 Section See LB 8316C-34 w Purchase Order Number g Chen*:ss Spra, Functw/ Service. None Safety Injection nedenon and Shutdown (nad Section Cooling Valves 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Accuracy Srec Aging D'* Section See Locaton 40 Years + LOCA See' Sheet 2 II.D.8 Sheet 2 Evalua tion ESP Rooms Submergence Elevatm Not Subject Note 2 to Submergence .

Flood Level Elevation Above Flood level Yes No DOCUMENT ATION DEFEn[NCES OTES l

4 1. The Effects of Nuclear Radiation on Elastomeric and 1. SV-3212B, -3213B, -3223A, B, -3224n, and -3037.

" Plastic Components and Materials, R W King, et al, REIC Report #21. 2. Respective elevations:

579'-10", 581' h", 579'_0", 579'_0", 576'-0", 573'-9" 9 - _ e58 01 A

C\ /O ['S V V (

Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision:

i Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALXICATION OUTSTANDING i EQUIPMENT DESCRIPTION METHOD liEMS Parameter Accident Ou . , i Accident Oug System: Operating Engineere.1 Time Section See Safeguards System 30 Days See She 4 '

III.B Sheet 2 Evaluation Plant 1 O Number. Temperature SV-3212A, 3224A t ri

, Sectie See

! component: 135 See Sheet 2 3 II.D.8 Sheet 2 Evaluation Solenoid Valve Pressure Manufacturer; (PSIA) Section See ASCO 14.7 14.7 II.D.8 Sheet 2 Evalua '. ion Mooel Number Relative Humid 6ty t%) Section See LB 8316c-36 100 See Sheet 2 II.D.8 Sheet 2 Evaluation u Purchase Order Number:

H Chemical O Spray one Functeon/ Service.

Safety Injection Radiation i and Shutdown inad) Section 6 II.D.7 1 Evaluation Cooling Valves 1.0 x 10 7.0 x 10 Accuracy: Spec: Ag,y D'** Section See Locate- 40 Years + LOCA See Sheet 2 II.D.8 Sheet 2 Evaluation ESP Room %,g, Elevatm: Not Subject Iote 1 to Submergence flood Level Elevation 1 Above Flood Level.

i Yes No DOCUMENTAT40N REFERENCES NOTES y

$ 1. The Effects of Nuclear Radiation on Elastomeric and 1. Respective elevations:

M Plastic Components and Materials, R W King, et al, 576'-9", 576'-0" REIC Report //21.

G 0858 01 A

Sheet 2 O

Component ASCO Solenoid Valves - SV-3001, -3002, -3018, -3027, -3029,

-3030, -3031, -3036, -3037, -3055, -3056, -3057, -3059, -3070,

-3071, -3212, -3213, -3223, -3224 All these valves are in the engineered safety system. The valves that are required to operate (containment spray and SIRW 1evel controlled valves), do so before the room becomes a hostile area; ie, prior to recirculation of the containment sump water. Once the valves do operate, they are not required to operate again. Several valves are electrically locked open or closed to provide proper alignment of the safety injection system. These valves are in their de-energized on-the-shelf positions and will remain in these positions.

The remaining valves (SV-3070 and 3071) are also not required to operate from their de-energized on-the-shelf positions.

No qualification information for these valves could be located. Should a failure occur which would result in a position change from the normal posi-tion, the operator would detect it and would secure the air to the valve.

However, all valves will be replaced by June 30, 1982.

O l

1 l

l 9

nu0481-0284d-43 311

v Sheet 3 DORGR 3 Service Conditions Outside of Containment DORGR 3A Area Subject to a Severe Environment as a Result c' a High-Energy Line Break (HELB)

DORGR 3B Areas Where Fluids Are Recirculated From Inside Containment To Accomplish Long-Term Core Cooling Following a LOCA Except for SV-3001 and SV-3002, the service conditions are as follows: 135'F, atmospheric pressure, 100% relative humidity, 1 x 107 rads TID Radiation Dose and 40 years plus LOCA aging. The areas do not become hostile until after recirculation begins. All valves have been aligned at this point and no further operation of the valves is necessary. The valves are not qualified to operate in the hostile environment and will be replaced. See Sheet 2.

Radiation is discussed in DORGR 5 and aging in DORGR 7.

DORGR 3C Areas Normally Maintained at Room Conditions i

The service conditions for SV-3001 and SV-3002 are 80*F, atmos-

[)

\_,/

pheric pressure, 80% RH, 1 x 10' rads TID Radiation Dose and 40 years plus LOCA aging.

Radiation is discussed in DORGR 5 and aging is discussed in DORGR 7.

l l

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nu0481-0284d-43 312 Rev 2

Sheet 3 (Contd)

DORGR S Qualification by a Combination of Pfethods (Test, Evaluation, Analysis)

DORGR SA Qualification by Evaluation and/or Analysis The 30-day radiation dose is calculated using the recirculating piping in the areas as radiation sources. The methodology is discussed in Section II.D.7. The referenced dose where the valve elastomers become degraded by 25*, compression set is exceeded by the TID. The valves will be replaced.

O O

l nu0481-0284d-43 313 l

l

4 Magnetrol SV-0823A&B, SV-0806A&B

!O l

4 Sheet 4

- Component Solenoid Valves '

The components were not includec in the November 1978 CP Co submittal and, therefore, were not addressed by the Franklin Research Center report.

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l 4

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i nu0980-0532a-43 319 i

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EQUIPMENT OUALIFICATION REPORT ,

Revision:

Facility: Palisades Date:

Docket: 50-255 "6

ENVIRONMENT DOCUMENTATION REFERENCES METHOD ITEMS Parameter Accident Ouahncahon Accident Oual

~

System: Operanno Time 30 Days 30 Days Section 1 Test Critical Service III B Water Plant 1 D. Numbe' Temperature See Note 1. 278 346 S,ection 1 Test

(* F)

Component:

Note 2 II.D.1 Solenoid Valve p,,,,u,,

70 125 Section 1 Test (PSIA)

II*U 1 ASCO Model Number Rela #ve NP-831654E Hum 6dity (%) 100 100 Section 1 Test II.D.1 u Purchase Order Number y c spr B ric Acid Boric Acid Section 1 Test IT.D.2 Function / Service.

Service Water for Radism 8 2.0 x 10 7 2.0 x 10 Section 1 Test Containment Air (Rad)

II.D.5 Coolers Accuracy: Spec: Aging Demo 40 .'ars Plus LOCA 18 Years Plus LOCA Section- 2 Test &

Locaton: II.D.8 Ana1ysis Containment % ,,nc, Elevahon:

Yes No Section See -

II.D.3 Sheet 2 Note 14 Flood Level Devanon 596'-0" Above Flood Level:

Yes- No- X DOCUMENTATtON REFERENCES NOTES

1. ASCO Test Report AQS21678/TR, Revision A. 1. SV-0861, -0862, -0864, -0865, -0867, -0869, -0870 ro and -0873.

2. ASCO letter with attached interof fice correspondence, W M Brown to Ff R Wade dated September 16, 1980. 2. For I.OCA 278"F; for MSLB 380"F. See Section II, Figures 7, 8 and 10.

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SV-0861, -0862, -0864, -0865, SV-0867, -0869, -0870, -0873 Sheet 2 Component Solenoid Valves to Containment Air Cooler Service Water Valves The ASCO solenoid valve Models NP-831654E is qualified for use in the containment accident environment by the type test described in ASCO Test Report AQS21678/TR, Revision A. The test was based on suggestions contained in IEEE 323-1974, IEEE 382-1972, IEEE 344-1975 and IEEE 382/ ANSI N27R.2.1, Draft 3, Revision 1, June 1977. Seven valves were tested representing six generic families of ASCO solenoid valves and are qualified by adequately passing the test. The testing subjected the sample valves to thermal, radiation, wear aging, seismic simulation, vibration endurance, accident radiation and a 30-day LOCA simulation, complete with chemical spray.

The operating time required for the solenoid valves to operate is within seconds following a safety injection signal (SIS). SIS initiates tripping of the containment air cooler "B" fans which, in turn, de-energize the solenoid valves and the control valvea open providing additional cooling water to the "A" fan coolers. The solenaid valves remain de-energized throughout the incident.

The containment temperature and pressure curves in Figures 7, 8, 9 and 10 in Section II provide the environmental requirements for the solenoid valves.

The test LOCA simulation enveloped these pressure and temperature curves except for the peak temperature following an MSLB. This is discussed in DORGR 2A.

100* relative humidity was provided in the steam environment in the LOCA simulation. The boric acid spray during the 30-day LOCA simulation provided test qualification of the solenoid valves.

Both aging and accident radiation were subjected to the valves for a total dose of 2.0 x 10' rads of gamma radiation.

The aging criteria was determined based on preaging of the valves at 268*F for 12 days to simulate 4.4 years at 140*F. The normal operating temperature na valves are in is 104*F. The qualified life calculated form the 10 C rule is 18 years.

The solenoid valves have not been qualified to operate when submerged. How-ever, the valves are not required to operaia while submerged. Qualification is discussed under DORGR 1C. The valves will be moved to a location where submergence will not occur as a preventative measure.

nu0980-0513b-43 322

SV-0861, -0862, -0864, -0865, SV-0867, -0869, -0870, -0873

-/ Sheet 3 Component Solenoid Valves to Containment Air Cooler Service Water Valves DORGR 1 Service Conditions Inside Containment for a LOCA DORGR 1A Temperature and Pressure Steam Conditions The ASCO qualification test exceeded the maximum tempera.ure, pressure steam conditions and duration for the FSAR LOCA analysis.

DORGR 1B Radiation

- Gamma The total integrated dose for equipment inside containment is 2 x 10' rads. The test provided, in two stages, a total dose of 2 x 10' rads of gamma radiation. The guidelines are met.

Beta Although the solenoid valves become submerged, the valve will operate, de-energize and vent off air from the control valve prior

, to being subjected to any beta dose.

DORGR 1C Submergence The valves are located such that they become submerged. However, I \ as stated on Sheet 2, the valves have de-energized on a signal

\'- following a trip of the "B" containment air cooler fans which are tripped by SIS (initiated by CHP or steam generator low level).

The flooding of the lowest solenoid will occur after sufficient time for the solenoid valves to de-energize and vent air from the control valve cylinder and open the control valve. Refer to Table 2,Section II, and Sheet D of Appendix A. See Sheet 2.

DORGR 1D Containment Sprays The Palisades concainment sprays are boric acid (1,750 to 2,000 ppm boron) asd 50 to 100 ppm hydrazine. Sodium hydroxide may be added as a pH buffer. ASCO's test consisted of sprays of boric acid (3,000 ppm horon) in solution with 0.064 molar sodium hydroxide to a pH between 9 and 11 at room temperature. The boric acid in the test is a higher concentration of acid and considered to be more detrimental to the valves. Hydrazine addition in the Palisades sprays is for a short period of time and does not remain in solution as hydrazine for any appreciable amount of time; therefore, the ASCO test without hydrazine is considered accept-able.

The solenoid valves also have operated before the containment sprays are on and are not required to operate subsequent to this.

(N_ ,/ nu0980-0513b-43 323

SV-0861, -0862, -0864, -0865, SV-0S67, -0869, -0870, -0873 Sheet 3 (Contd)

DORGR 2 Service Conditions for a PWR MSLB Inside Containment DORGR 2A Temperature and Pressure Steam Conditions The ASCO test envelops the Palisades containment MSLB response shown on Figure 10 of Section II, except for the peak temperature of 380 F. The duraticn of time in which the Palisades transient exceeds the test peak tamperature of 346*F at 110 psig is about 20 seconds (from 48 to 68 seconds on curve, Figure 4). The duration is then very short and because of this will have very little or no effect on the equipment.

Also, being that the valves operate prior to the temperature exceeding the test temperature, the higher assumed MSLB temperature will have no effect on the operability of the valves.

The guidelines are met by these valves as the requirements are met for LOCA, and Palisades is equipped with automatic containment sprays that are not subject to disabling single failure.

DORGR 2B Radiation See DORGR 1B above.

DORGR 2C Submergence See DORGR 1C above.

DORGR 2D Chemical Sprays See DORGR 1D above.

DORGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Qualification is by test. ASCO Test Report AQS21678/TR, Revision A.

DORGR 4B Qualification by Type Testing

1. Simulated Service Conditions and Test Duration The simulated LOCA envloped the Palisades LOCA and MSLB analysis as explained above. It included a steam environment with chemical sprays and pretest irradiation. The simulated LOCA duration was 30 days. The conditions and test duration meet the guideline requirements.

nu0980-0513b-43 324 Rev 2

l l

SV-0861, -0862, -0864, -0865, SV-0867, -0869, -0870, -0873 bh LJ Sheet 3 (Contd) 2.

Test Specimen The test specimca was one of a generic family of valves which includes the inscalled solenoid valve. The materials are identical and only the enclosure was different. The test specimen meets the guideline requirements.

3. Test Sequence Radiation was applied prior to the simulated LOCA environment.

The test sequence meets the guideline requirements.

4. Test Specimen Aging The test specimen was preaged using Arrhenius techniques to simulate a lifetime of 4.4 years at 140*F. The preaging exposed the valves to 268'F for 12 days. The guideline requirements for aging are satisfied.

5. Functional Testing and Failure Criteri~a f The valves operated during and following the LOCA simulation 1

( and all valves passed the test. The test met the guideline requirements.

6. Installation Interfaces The valve is designad to operate in any position and no particular emphasis was applied in how to install the in-plant solenoid valves. The intent of the guidelines is met.

DORGR 6 Margin Meeting the guidelines of DORGR 4 satisfies the margin requirements.

DORGR 7 Aging Maintenance schedules will require replacement of all nonmetallic

. components, including coil, every 18 years.

DORGR 8 Documentation i References 1 and 2 provide the documentation.

O nu0980-0513b-43 325 Rev 2

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SV-0861, -0862, -0864, -0865, SV-0867, -0869, -0870, -0873 Sheet 4 Component Solenoid Valves to Containment Air Cooler Service Water Valves These solenoid valves were part of the November 1978 CP Co submittal.

Franklin Institute's comments on Section 3.3.2.2 are responded to below,

a. A detailed test report, ASCO Test Report AQS21678/TR, Revision A, has been obtained which describes the qualification testing for the subject valves.

b. The test conducted by ASCO tested seven valves representing six generic families of solenoid valves. The valve tested, from the generic family for the installed valves, has but two insignificant differences. They differ in pipe size fitting and type of enclosure which is explosionproof and watertight as opposed to only watertight. All other valve parts materials, design of the valve and construction are the same for both the tested and installed valves.

c. Submergence is discussed on Sheet 3, Item DORGR 1C.

d. Qualified life for the valve based on the testing and information supplied by ASCC based on the Arrhenius equation and based on a normal ambient temperature of 104*F provides for a qualified lifetime of 18 years plus 1 LOCA. As stated earlier, the preventative maintenance program will be updated to show replacement of nonmetallic components that are due within the 18-year period.

nuG980-0513b-43 326

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EQUIPMENT OUALIFICATION REPORT Owner. Consumers Power Company Component Sheet No:

Facility: Palisades Reh Docket: 50-255 Date:

EMONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANOING i EQUIPMENT DESCRIPTION METHOD ITEMS Parameta Accident Oualifceta Accident Oues System: Operstwig Tm 3 IIours See Sheet 2 See See Evaluation Engineered Safe- Sheet 2 Sheet 2 guard System

' " " See Figures 7 & 8 See Sheet 2 i.7""

seeYte1 Section See Evaluation II.D.1 Sheet 2 component.

Solenoid Valve Preneure

' psi,'

See Figure 9 See Sheet 2 Section See Evaluation II.D.1 Sheet 2 ASCO Rotenve 1 Model Number Hurnuty t%)

100 See Sheet 2 Sec ti on See Evaluation i 'JPIff8300n61-RF II.D.1 S" tt 2

M Purchase Order Numbw t

u cram 6cei 1750 to 2000 ppm See Sheet 2 Section S .e Evaluation spray j Boric Acid With II.D.2 Sheet 2

{ Function / Service 50-100 ppm N 1I24 3afety Injection Mt'oa Pank Valves (Red) 2.5 x 106 7.0 x 10 6 Section 1 Evaluation II.D.5

- - - - ^0'"9 10 Years 6 See Sheet 2 Section See Evaluation Locata:

+ LOCA II.D.8 Sheet 2

[nside Containment Sutergence Not Subject to Elev Submergence i 3S),enon

617' h" Flood Le.wi

, Elevehon 5%'0" i

Above Flood Level.

i Yes Y No

! DOCUMENTATION REFERENCES NOTES i m j $ 1. The Effects of Nuclear Radiation on Elastomeric and 1. SV-3069, -0338, -0342, -0346 and -0347

, to Plastic Components and Materials, R W King, et al, REIC Report #21 G-0858-01 A 1

ASCO SV-3069, -0338, -0342 SV-0346, -0347 Sheet 2 Component ASCO Solenoid Valves The safety injection tank check valve leakage isolation valves, SV-0338,

-0342, -0346, -0347 and -3069 all close on SIS which is very early in the event. All but SV-3069 are de-energized to their on-the-shelf position.

No qualification data could be located for these valves. Should these valves fail due to age-related degradation, there is a possibility that the line from the safety injection tanks to the primary system drain tank could be opened.

This is a one-inch line. The analyses presented in CEN-114P, Combustion ingineering NSSS Response to Small LOCAs, show tnat SI tanks are required only for breaks 0.1 ft' and greater. The safety injection signal occurs for this break prior to 30 seconds. Computing the flow to the primary system drain tanks assuming no line loss, atmospheric pressure in the drain tanks and 200 psig in the SI tanks yields a loss of 36 ft' of SI tank liquid compared ta 1,103 ft' in the tank. This is an acceptchle loss. For the large LOCA, this loss will be significantly less as the safety injection signal occurs at one second.

If these solenoid valves fail in the long term, HPSI flow may be diverted to the Primary Coolant System Drai t Tank instead of to the Primary Coclant System. Failure to the open position is not considered probable because, as stated above, these valves close early in the event on SIS. They de-energize to their on-the-shelf position which is closed and vented. The only possible path for air to get to the control valve is through the seat. The seats fail by hardening or cracking not through total disintegration. Also, the vent path is open so any seepage will be vented. CP Co believes that the control valve will not receive sufficient air pressure to open even if all of the failures occur as pestulated.

Even if the valve opens the results are acceptable. For large LOCAs, the Primary Coolant System rapidly depressurizes so that the path to the PSDT is the same pressure as the path to the Primary Coolant System. Since the flow is very much smaller (3/8-inch throat diameter), the loss will be negligible.

For small break LOCAs, the core does not uncover. The containment conditions are less severe and, sinc 6 the core does not uncover, the radiation levels are much less. The solenoid valve, if it fails at all, will fail later in the accident. The Primary Coolant System pressure is dropping during small breaks but not as quickly as during the large LOCAs. As a result, the flow to the PSDT will be a larger portion of the safety injection flow to the Primary Coolant System than it was during the large breaks. However, failure still should not result in core uncovery for any significant period of time as the core level is at least four feet above the top of the core for these small breaks. This is based on the fact that for breaks as small as 0.02 ft the amount diverted is only 2.5*.' of the total flow (flow area of path to the PSDT is only 10% of the break area and 25% spillage is assumed). For breaks even smaller where the flow area of the path to the PSDT is a signficant fraction of the break area, the charging pumps have the capacity to make up for the last flow.

These valves will be replaced with qualified valves by June 1982.

nul080-0001a-43 328 Rev 1, 10/30/80

O p p Owner: Consumers Power Company Component Sheet No:

fievision:

Facihty: Palisades Date:

Docket: 50 255

' ENVIRONMENT DOCUMENTATION REFERENCES

^ '^"

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Ouas fication Accident Ouai System Operatino Component Tw 30 Days See Sheet 2 Sec III.B See Sh 2 Evaluation Cooling System Plant I D. Number: Temperature See Note 1 (*O 135 See Sheet 2 Sec II.D.8 See Sh 2 Evaluation Component.

Solenoid Valve Pressure (PSIAl 14.7 14.7 Sec II.D.8 See Sh 2 Evaluation Meturer-ASCO Model Number Relative WPitT-8300-B61-RF H

I*I 100 See Sheet 2 Sec II.D.8 See Sh 2 Evaluation W Purchase Order Number M'

Chemical D 'Y None Function / Serske I Caponent Cooling Radiation 6 6 i and Shutdown llenat (Rad) 1.0 x 10 7.0 x 10 Sec II.D.7 1 Evaluation I Exchanger Accuracy: Spec: Ag,ng 4

D*" # 40 Years Plus 1.0CA Sec II.D.8 Ste Sh 2 Evaluation l Location ESF Room % g,,c, Eievation: Not Subject t Submergence Note 2 l Flood Level

, Elevahon Above Flood level Yes No DOCUMENT ATION REF FRENCES NOTES m

1. The effect of Nuclear Radiation on Elastomeric and L. SV-0947, -0948, -09'.9, -0950 and -0951.

" Plastic Components and Materials, R W King, et al,

. Respective elevntions:

REK Report #21. 57h '-0" , 57h '-0" , 57h '-0" , 583 '-8" , 581 '-8" l

G O858 01 A

1 1

l Sheet 2 O

Component ASCO Solenoid Valves SV-0947, -0948, -0949, -0950 and -0951 For breaks inside containment which would, following RAS, make this a hostile area, only one valve SV-0950 operates. It receives an SIS signal and opens to allow cooling to the ESS pumps. Following this operation, which is prior to RAS, the valves are not required to operate for these breaks. For an HELB outside containment, which would render the component cooling water pumps inoper.ble, SV-0950 would have to be manually closed and SV-0951 manually opened. For this event though, the area is not hostile because cooling of the primary coolant system will be accomplished using the auxiliary feedwater system. The safeguard pumps can operate for awhile without cooling water. If they should fail, the core will still remain covered and filling of the primary coolant system will be accomplished with the charging pumps. Because operation occurs prior to the area becoming hostile and the valves remain in their de-energized on-the-shelf positions, operation of the systems is not jeopardized. The valves, however, are not qualified for the hostile environments and do not meet the guideline requirements. Due to this, they will be replaced or moved by June 30, 1982.

O O

nu0980-0601a-43 332

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I l- -__ _ _ _ _ _ . _ _ _ _ , , , _ _ _ _ _ _ , _ , _ _ _ _ _ __ _

M EQUIPMENT OUAl.lFICATION REPORT Component Sheet No:

Facility: Palisades Revision Docket: 50-255 Date:

DOCUMENTATION REFERENCES I ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS Paramera Accident Ouawication Accident Oual system: Operstmo Tir 30 Days 30 Days Section See Evaluation Service Water Syster .

III.B Sheet 2 plant i D. Number- Temperature SV-0644 (*F) See Note 1 See Sheet 2 Section See Evaluation

%, II.D.6 Sheet 2 Solenoid Valve Pressure w ,c tessAl 14.7 14.7 Section See Evaluation ASCO II.D.6 Sheet 2 Model Number Relative LM 831614 " 'rl%) 100 See Sheet 2 Section See Evaluation w Purchase Order Num.ar:

II U 6

~ Chenkel

" spray None Functon/ service.

Service Water Shut- Racket 6cn (Rad) 1.,0 x 10 6 Se on 1 Evaluation off and Crosstie 7.0 x 10 Accuracy: Spec:

Aomo 40 Years See Sheet 2 Section See Evaluation

+ Accident II.D.8 Sheet 2 LOCalion:

Room 123 - Note 2 sub - gence Not Subject to Elevahon:

593'-2" 8"D**#E*" * ,

F tood Level Elevation Above Flood Level Yes *40 DOCUMENTATION REFERENCES NOTES

1. The Effect of Nuclear Radiation on Elastomeric and 1. For LOCA 104 F, for MSLB Outside Containment 212 F Plastic Components and Materials, H W King, et al, for One Hour Then Linear Decline to T=104 F at REIC Report #21 24 Hours

2. The Valve is Iocated 10 Feet From the Containment Wall 858 01 A

q I

s l G Q)'

EQUIPMENT GUAllFICATION REPORT Facility: Paltsades Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDING EQUIPMENT DESCRIPTION -

METHOD ITEMS Parameter Accident Quahtication Accident Qual Water System 30 Days 30 Days h tion e Evaluation Servi Plant i D. Number Temperature See Note 1 See Sheet 2 Section See Evaluation SV-0815 6 (* F)

II.D.6 Sheet 2 Solenoid Valve Pressure I

%,,co.,. (PSIA) 16.7 1

14.7 Section See Evaluation ASCO II.D.6 Sheet 2 See Sheet 2 Section g,g 7[ y 33 100 II.D 6 See Sheet 2 Evaluation w Purchese Order Number e Chemical

" Spray None Funciton/ Service.

Service Water Shut- Redonoa 6 le 7.0 x 10 Section 1 Evaluation off and Crosstie (Radi 3.0 x 10 II . D . */

- - "CY' Ao*0 1+0 Years SectSheet 2 Section See Evaluation

+ Accident II.D.8 Sheet 2 Location-Room 123 - Hate 2 Sutmoence Not Subject to Submergence 593' Y+"

Flood Level Elevaton Above Flood Level Yes No.

DOCUMENTATION REFERENCES NOTES

1. The Effect of Nuclear Radiation on Elastomeric and 1. For IDCA 1014 F, for MSLB Outside Containment 212 F Plastic Components and Materials, R W King, et al, for One llour Then Linear Decline to T=10 4! F at REIC Report #21 21 4 ilours

2. The Valve is Located 30 Feet From the Containment Wall G 0858 01 A

EQUIPMENT QUAUFICATION REPORT Facsty: Paksades Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANOING EQUIPMENT DE: CRIPTION METHOD ITEMS Ps ameter Accident QuaMiceon Accident Qual System. Operateo Service Water System Tme 30 Days 30 Days Section See Evaluation III.B Sheet 2 Plant 1 D Number: Temperature SV-0846 g F3 See Note 1 See Sheet 2 Section See Evaluation component.

II.D.6 Sheet 2 Solenoid Valve Pressurn Manufacturer; (PSIA) 14,7 14.7 1 Section See Evaluation ASCO II.D.6 Sheet 2 Model Number Reletrve Humuity (%) 100 See Sheet 2 Section See Evaluation F"f-8316C-lh II.D.6 Sheet 2 w Purchase Order Number j'

chamas Spray Hone FunctontService

.iervice Water Shut- %non g aff and Crosstie (Rad) 4.0 x 10 h.h x 106 Section 1 Evaluation II.D.7

- - * ^0*0 40 Years See Sheet 2 Section See Evaluation

- '=.,, + Accident II.D.8 Sheet 2 m 3 - N te 2 Submergence Not Subject to Ekveon. Submergence 593'-2" Fluod Level Elevation Above Fiood ievel.

Yes No y DOCUMENTATION REFERENCES l NOTES m 1. The Effect of Nuclear Radiation on Elastomeric ard 1. For IDCA 10h"F, for MSLB Outside Containment 212 F Plastic Components and Materials, H W King, et al, for One Hour Then Linear Decline to T=1040F at REIC Report #21 24 Hours

2. The Valve is Located 25 Feet From the Containment Wall

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- _ _858 01 A

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'L/

EQUIPMENT QUAllFICATION REPORT ,

Facehty: Pausades Revir. ion Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTANDING EOUtPMENT DESCRW' TION METHOD ITEMS Parameter Accident ! Outteeton Accident Ouel System: . Operating Service Water System +w 30 Days 30 Days Section See Evaluation III.B Sheet, 2 Plant i D. Numb 8' Temperature SV-0857 (* F)

See Note 1 See Sheet 2 Section See Evaluation Cornw II.D.6 Sheet 2 Solenoid Valve Pressure 14.7 14.7 Section See Evaluation Manufacturer; (PSIA) II.D.6 Sheet 2 ASCO ,

Model Number Rektive Hu'naddy m) 100 See Sheet 2 Section See Evaluation LB.8316115 II.D.6 Sheet 2 ca Purchem Order Number b Chem 6 cal

Spray None FunctiontService.

Service Water Shut- u non off and Crosstie (Red) 4.0 x 10 7 0 x 10 Section 1 Evaluation II.D 7

- - "' Aomo 40 Years See Sheet 2 Section See Evaluation

+ Accident II.D.8 Sheet 2 loom 123 - Note 2 Submergence Not Subject to Submergence i93'-2" flood Level Elevaton Above Flood Level.

Yes No m DOCUMENT ADON REFERENCES NOTES 0 1. The Effect of Nuclear Radiation on Elastomeric and 1. For LOCA 104 F, for MSLB Outside Containment 212 F N Plastic Components and Itaterials, R W King, et al, for One Hour Then Linear Decline to T=104 F at REIC Report #21 24 Hours

2. The Valve is located 20 Feet From the Containment Wall G 0858 01 A

Owner: Consumers Power Company Component Sheet No:

Facihty: Paksades Revision Docket: 50-255 Date:

E N MENT DOCUMENTATION REFEREP CES OUALFICATION Ot!TSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Ouabhcahon Accident Ouel System: Operstm Service Water Syster Time 30 Days 30 Days Section See Evaluation III.B Sheet 2 Plant 10 Numbe' Temperature SV-0876 (* F) See Note 1 See Sheet 2 Section See Evaluation II.D.6 Sheet 2 fp$47* 14.7 14.7 Section See Evaluation ASCO II.D 6 Sheet 2 Model tbmber Relehve LB 831614 t w ivtsi 100 See Sheet 2 Section See Evaluation' W Purchese Order Num'>er II.D.b Sheet 9

$ Chemical Spray Hone Funcnon/ Service Cooling to Diesels R**8Sa h 6 Section 1 Evaluation (Rad) 3.0 x 10 7.0 x 16 II.D.7

- ^0'"O h0 Years See Sheet 2 Section See Evsluation II.D.8 Sheet 2 m 3 - Note 2 Suemeroence not Subject to Elevehen. Submergence 596'- 2" Flood Level Elevahon Above Flood Level Yes No DOCUMENTATION REFERENCES NOTES g

0 1. The Effect of Nuclear Radiation on Elastomeric and 1. For IDCA 1040F, for MSLB Outside Containment 2120F to Plastic Components and Materials, R W King, et al, for One Hour Then Linear Decline to T=1040F for REIC Report #21 24 Hours

2. This Valve is Incated 30 Feet From the Containment Wall

_ _ _ 58 01 A

. _ _ _ _ _ . . . . _ . . . . .. _ .- . _ . - . . .. . . ~ . . . - _ __ _ _ .. __ ___. ___ = _ _ _ _ . _ _ _ _ _ . _

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i Component ASCO Solenoid Valves SV-0844, -0845, -0846, -0857, -0876, -0877 i

s This. equipment was not included in the November 1978 CP Co Submittal and, I therefore, was not addressed by the Franklin Research Center Report.

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s Owner: Consumers Power Company Component Sheet No:

Facdity: Pahsades Revision:

Docket: 50 255 Date:

ENVIRONME NT DOCUMENTAT1ON FtEFEHENCES OUALIFICATION OUTSTANDt4G EQUIPMENT DESCRIPTION METHOO liEMS Paramets Accident Ouuhhcaton Accident Oues 8'"" " Section Service Water 30 Days See Sheet 2 III.B See Sheet 2 Evalt ion Plant l D Number Temperature Section SV-0824 (* F) 135 See Sheet 2 II.D.8 See Sheet 2 Evaluation Component-Solenoid Valve Pressure gg,

,,;- --: '"s'^ >

14.7 14.7 II.D.8 See Sheet 2 Evaluation

- He._e "

Humory (N 100 See Sheet 2 See Sheet 2 Evaluation LB-831614 w Purchase Ordw Number u Chemical

** None Funcitan/ Service Shutoff to Service "" 7 6 Section Water to Containment tran 1.0 x 10 7.0 x 10 II.D.7 1 Evaluation Air Coolers Accuracy Spec: ggeg Demo. Section toc,,,on. 40 Years + IDCA See Sheet 2 II.D.8 see Sheet 2 Evaluation ESF Room 3 Elevam Not Subject 579'-10"

' 8"D"*F8""'"

ilood Level Elevaten Above Floou levei Yes No y DOCUMENTATION FIE FEHENCES NOTES

" 1. The Effect of Nuclear Radiation on Elastomeric and Plastic Components and Materials, R W King, et al, REIC Report #21

- _ _ so o t A

Sheet 4 Component ASCO Solenoid Va'.ve SV-0824 This valve was not included in the November 1978 CP Co submittal and was, therefore, not addressed by the Franklin Research Center Report.

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l nu0980-0602b-43 355 1

EQUIPMENT QUAtlFICATION REPORT g p

Facihty: Pahsades Revision:

Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCR6PTION METHOD ITEMS Paramein Accident Ouatication Accident Ouas System. Operating Service Water Systei :

T""* 30 Days 30 Days Section See Evaluation III.B Sheet 2 Plant i D. Number Temperature ,

SV-0879, 0880 (* FI See Note 1 See Sheet 2 Section See Evaluation g; II.D.6 Sheet P Solenoid Valve pressure w,cug. (PSIA) lk.7 14.7 Section See Evaluation ASCO II.D.6 Sheet 2 Model Number. Relative WHIT 83000n61-RF Hunwy (%) 100 See Sheet 2 Section See Evaluation u", Purchase Ordw Number.

II.D.6 Sheet 2 cm Chemical Spray None Function! Service.

Service Water Radiatioa 4.0 x 10 b

70x10 6 Section 1 Evaluation Backup to Cool (Rad)

II D 7 ESF Pumps

'* * ^9'"O 40 Years See Sheet 2 Section See Evaluation

+ Accident II . D .8 Sheet 2 Room 123 - Note 2 Submwoence not Subject to Subm rgence 595 - 595'-3" f tood Level Elevation Above Flood Level.

Yes No DOCUMENTATION REFEHENCES NOTES m

1. For IDCA 104 F, for MSLB Outside Containme:J 212 F 0 1. The Effect of Nuclear Radiation on Elastomeric and for One Hour Then Linear Decline to T=104 F at 24 M Plastic Components and fiaterials, R W King, et al, REIC Report #21 24 Ilours

2. These Valves are Incated 20 Feet From the Containment Wall 58-01 A

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(Duplicate on Page 268) i I

f nu0481-0284f-43 361 Rev 2 I

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" A Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsades Reh:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAtlFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD HEMS Parameta Accident Quawication Accident cual System. Opwating Section Primary Coolant im 30 Days See Sheet 2 III.B ice Sheet 2 Evaluation System Piant i D. Number. Tampasture S"Uti "

S V- 19 01. , 2 , 3,4 , 5 (* r) See Figures 768 See Sheet 2 II.D.1 3ee Sheet 2 Evaluation Component.

Solenoid Valve Pressure Sectio..

(PSIA) See Sheet 2 Manufacturer: See Figure 9 II.D.1 see Sheet 2 Evaluation ASCO Model Number Relative Section itT8320A22 Humkkty (%) 100 See Sheet 2 II.D.1 ice Sheet 2 Evaluation

" Purchase Ordw Number

$ Chemical 1750 to 2000 ppm ,j Section spray Boric Acid With See Sheet 2 11.0.2 Evaluation Function / Service. 50-100 Ppm N II24 See Sheet 2 NSSS Sampling meion Section Valves (Rad) 6 2.0 x 10 4.4 x 10 II.D.5 1 Evaluation Accuracy spec: ^9*Q Section D*w- 40 Years See Sheet 2 tocaton: Inside + LOCA Containment Submergence Not Subject Elevanon:

To Submergence Note 1 flood Level Eievation 596'-0" Above Flood Level.

Yes. X No.

DOCUMENI ATION REFERENCES NOTES l

1. The Effects of Nuclear Radiation on Elastomeric and 1. Respective elevations:

Plastic Components and Haterials, R W King, et al, 631 '-h", 630 ' h" , 629 '-h" , 628' 10", 628 '-2" REI Report #21.

m .. -

58-01 A i

. - _ - __ . __ _ _ . = _ . _ _ _ _ _ _ _ _ .- _ _ . _ . . . _ -._._. ~ _ _ - _ _ _ _ _ __. _. ._ _--... _ ____._. . _.. _ ___

i SV-0522A i

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i i Sheet 4 i

Component ASCO Solenoid Valve SV-0522A 3

This equipment was not included in the November 1978 CP Co submittal and was, j therefore, not addressed by the Franklin Research Center report.

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l nu0980-0586a-43 371

Owner: Consumers Power Company Component Sheet No:

Facahty: Pahsades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUALIFICATION OUTSTAN0eNG EOuiPMENT DESCRIPTION METHOD ITEMS Parametw Accident Quahtcation Accident Ouas System Section 7""'atin 30 Days 30 Days See Evaluation Main Steam System III.B Sheet 2 Plant I D Nunter.

SV-0736, -0739, -0767,Temperaturo .r3 110 110 Section See Evaluation

-07 g770,-0771 II.D.8 Sheet 2 Solenold Valve pressure Matactur.<: (PSIA) lle.7 lk.7 Section See Evaluation ASCO II.D.8 Sheet 2 Modal Number. Relative Hu"*r N 95 95 Section See Evaluation WPHT 8300B61-RF II.D.8 Sheet 2 w Purchase Order Numbw N Chemical

" Spray None Function / Service Steam Generator Ra6ation b 6 Blowdown Isolation (RA2) 4.0 x 10 7.0 x 10 Section 1 Evaluation Valves II.D.7 Accuracy- Spec: ggg D"* -

40 Years & IDCA 40 Years + IDCA Section See Evaluation Locaton:

Room 238 See Note 1 _,

Ei.,pnon- Not Subject to 611'-1",613'- !" Submergence 611'-1 613 ' _P",610'_10".611'- . -P" F tood Level Elevatiori Above Flood Level Yes No-DOCUMENTATION REFERENCES !

I NOTES to 1. The Effect of Nuclear Radiation on Elastomeric and 1. These Components are Required for a LOCA and/or PSLB Plastic Components and Materials, R W King, et al, Inside Containment Only; Although Room 238 Will REIC Report #21 Experience Harsh Environmental Conditions in the Event of a MSLB. This Equipment is not Required for l This Accident (See Section II.D.6). These Valves are Located 1 to 7 Feet Prom the Containment Wall -

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! Component ASCO Solenoid Valves SV-0438A, B l This equipment was not included in the November 1978 CP Co submittal and, j- therefore, was not addressed by the Franklin Research Center Report. ,

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. ,, ww w .,n n ,v - - - - - - - - - - - - - - - - -

EQUIPMENT QUALIFICATION REPORT ,

Facility: Palisades RevisPA:

Date-Docket: 50 255 ENVIRONMENT DOCUMENTATION REFERENCES OUALFICATION OUTSTANOING EQUIPMENT DESCRIPTION METHOD ITEMS Peremeter Accident Ouancata Accident Ouel System: Operatog I" Corrponent Cooling Tim

30 Days 30 Days B 1 Evalt ton System Plant i D. Numbef Temperature - ' " Evaluation EMA-1208, 1116, 110! (*F) 104 104 1 8

Component:

Motor Pressure Section uenutecturer: (PSIA) 14.7 14.7 II g g 1 Evaluation Louis-Allis Model Number. Relative Section 8289252001,2,3 Humioty (%) 80 100 1, Evaluation I1.D.8 COGX y Purchese Order Number o Chemical 5935-M34 Spray None Funct6on/ Service Ccmponent Coo'.ing nedetion 5 Motor (Red) 6x10 See Sheet 2 Section 6 Evaluation II.D.7 Accuracy- Spec: Ageng i

D** # "

40 Years See Sheet 2 II.D.8 6 Evaluation toc.i,on:

Room 123 -

Submergence See g tg 1 Not Subject 592'-9" E 8"D""#8""'"

Flood Level Elevatm Above Flood Level:

Yes No NOTES c DOCUMENTATION REFERENCES l g 1. Electric Motor Data Sheet for Component Cooling 1. These motors will be affected by Main Steam Line Motors Submitted by Louis-Allis Break outside containment but are not required to operate for that break.

2. Letter From Mr Schreiber of Louis-Allis to C St onge of_Bechtel, Dated September 17, 1980 _. _

258 01 A

.s, b...n----,-. ---.s. - -- -.A- A----s- n . = - - n --amm-- u en . > a - >- u"a-- w-> a - -.u.------ a - - ------ - -

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EQUIPMENT GUALIFICATION REPORT ,

Facety: Palisades Rom Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOD HWS Pwamesw Accident Quahncation Accident Qual sysi. w Opwahng Section i Engineering The III*U safeguards system 1 Ilour Plant I D. Number Temperature Sed Section See Note 1 (* F)

Figures 7 6 8 See Sheet 2 II.D.1 See Sheet 2 Evaluation Eles D_bumatic Pressure

.Tra g g w gp3:33 See Section Figure 9 See Sheet 2 II.D.1 ice Sheet 2 Evaluation Fischer Controls Co Model Numbw Relehve w,y g3 Section E/P-546 100 ice Sheet ? II.D.1 ice Sheet 2 Evaluation M Purchase Order Number Chemical 1750 to 2000 ppm v'

't-233 88Y "'I "

Boric Acid with ice Sheet 2 Function / Service. 50 to 100 ppm hit, "*

Safety Injection Tanl, Indenon 6 Section T-82A,B,C,D Valves (Rad) 2.5 x 10 .ee Sheet 2 4

II.D.5 ice Sheet 2 Evaluation Accuracy: *p; Aging Demo: 40 Years + LOCA ice Sheet 2 Section

>ee Sheet 2 Evaluation tocaten: II.D.8 Inside Containment dot a rgence riot Subject to Ebenon: Submergence

, lote 2 f tood tevel tie, non 596'-0" Above Flood Level-Yes. X No' m NOTES (D DOCUMENTATION REFERENCES

" E/P-0338, E/P-03h2, E/P-03L6, E/P-0317

1. Laboratory Report, " Operational Tests of the Fischer 1. 4 Type 546 Electropneumatic Transducer for Nuclear Reactor Containment Vessel Service," June 12, 1973. 2. Respective elevations:

615'-6", 615'-6", 618'-6", 615'-6"

2. I.etter f rom 11 Douglas Waldron, liarley Company, to W - Cooper, Consumers Power Company. January 24. 1978 - - -

58 01 A

o)

\. O J (J')

EOLNPMENT QUALIFICATION REPORT p ,

Facihty: Paksades Revisaon Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES '

EOutPMENT DESCRIPTION l

Paramenw Accident Quahhcahon Accident Oud MEmOO ITEMS System: Operahne i Engineering Tune Section l safeguards system 30 days 30 III.B ice Sheet 2 .;<aluation .

Plant I D Numbw Tempwature Section

E/P-3025 t*F) 135 135 II.D.8 ice Sheet. 2 Evaluation

Component Electro pneumatic Pressure Section E 'bENw. (PSIA) 14.7 14.7 II.D.8 ice Sheet 2 Evaluation Masonellan Model Numbw %hva SCClion I 8012 HurmMy N 100 100 II.D.8 ice Sheet 2 Evaluation

Purchase Ordw Numbw M-233 h*'

Spray

' None Funchor / Service.

! Lineup & monitor h hon 7 Section 7 1 x 10 i shutdown cig flow (Rad) 1 x 10 II.D.7 1 Evaluation Accurxy: Spec:

A0'a0 Seetion Dano 40 years + LOCA Yes 1 Evaluation II.D.8 tocahon.

. F room

Submwoonce Not subject to Elevahon.

submergenee 57h'-7" Flood Level i Elevahon Above Flood Level Yes No

g DOCUMENTATION ilEFERENCES NOTES ro j 1. Let ter f rom Jef f rey Waal, Masonellan, to K Toner, Consumers Power Company, August 28, 1980.

E 4

G o858 01 A

M;.consilan EP-3025 Sheet 2 Component Masonellan Electro-Pneumatic Positioner With respect to pressure and relative humidity, the required values (atmos-pheric and 100*. rh) are benign conditions and do not expose the component to stress.

With respect to temperature, 135*F is designated as a harsh or hcstile en-vironment; however, the equipment is considered adequate for 30-day operation at 135*F. Metallic parts, in particular, are not susceptible to degradation at 135*F and nonmetallic parts are generally adequate to 150*F. This is based on broad industrial and power plant applications.

Qualification to aging and radiation is provided in Reference 1. The manu-facturer is testing models "similar in design and construction with respect to components that are susceptibl.a to thermal aging and radiation." These tests have shown that, after 1 x 10' rads and 99'C for 45 days, no detrimental effects have occurred.

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J 1

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1 Component Masonellan Electro-Pneumatic Positioner This positioner was not included in the November 30, 1978 CP Co submittal; 4 therefore, it was not reviewed by Franklin Research Center.

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nu0481-0284h-43 393

' Component Sheet No:

Owner: Consumers Power Company Revision:

Facihty: Pahsades Date:

Docket: 50-255 ENW10NMENT DOCUMENTATION REFERENCES I OUALFICATION OUTSTANOING EQUIPMENT DESCRIPTION METHOO HEus Parameter Accident Quahhcahon Accident Qua, System: Operatng Engineering Safe- Tee guards System 30 Days 10 Days see TTT n son sh 9 Evaluatfon Plant i D. Numt* Temperaturo PT-0306 (*FI See Note 1 212 Sec II.D.6 See Sh 2 Evaluation Component Pressure Transmitter Pressure 14.7 Sec II.D.6 See Sh 2 Evaluation pf," **((ber 14.7 Model Number: Rets%ve 50EP1072A 80 80 Sec II.D.6 See Sh 2 Evaluation j Purchase Order Number Chenicas

M206 None Spray Function / Service.

LP Safety Inj Radiatm Discharge Press Ind IRad) Negligible Yes Sec II.D.4 See Sh 2 Evaluation Accuracy. Spec: Agng D'** 40 Years Plus tocat m LOCA Sec II.D.8 Room 123 % ,,nc, Elevaton Not Subject 59h Q " to Submergence ilood Level Elevation Above Flood Level-Yes No

13 NOTES o DOCUMENTATION FEFEftENCES r0 Fischer-Porter Instruction Bulletin 50EP1000. 1 212 F for one hour, then linear decline to T = 110 F 1.

at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I O858 01 A

- . . . - . . . .... - - .- - -. ...-. .. - ._ ..._- -. .. .-.__- -_. _ . .- . -~. .-=._ _.

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i Sheet 4 1 3 i l' Component Pressure Transmitter (PT-0306) i This. component was not included in the November 1978 CP Co submittal and, therefore, it was not reviewed by Franklin Research Center Report. 1 1

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Owner: Consumers Power Cornpany Component Sheet No:

Facihty: Palisades Flev:Jon:

Docket: 50-255 Date:

ENVIRONMEN1 DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION OUAUFICATION OUTST/.NDING Parameter Accident Ouawicamon Accident Qual METHOO ITEMS

Y**; D'" Section 1 h

Safety injection i hour 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months II.B.5 See Sheet 2 Test Plant i D. Number Temperature

(*F) Section I See g See Figures 768 320 " *"'2 *8' '

II.D.1 Pressure transmitter Pre:.aure l

(PSIA)

Manufacturer:

9 90 S" ,tfna g g Fischer & Porter 11. 1 1 Model f&rnbar Relative 1 50EP1042A 100 100 . See Sheet 2 Test w Purchase Order Number g Chemical 1,750 to 2,000 ppm H-206 Spray boric acid with 50 y,, &c&n See Sheet 2 Evaluation F a non m e: t 100 N Il24 [I.D.2 Safety injection Radiation tank pressure M 1.8 x 10 6

Yes See Sheet 2 Test Accuracy: Spec: Aging Demo: s e ggteet 2 Section 40 years + LOCA See Sheet 2 Evaluation

, I . D.8 Inside containment Submeegence Elevanon: Not s ubj.ect to submergence 2

Elevanon 596'-0" Above Flood Level:

Yea: X No:

DOCUMENTATION REFERENCES NOTES

1. Fischer & Porter Repo t DP-2204-51-B-006, dated 1. PT-0338, PT-0342, PT-0346, PT-0347 m 12/2/68, Special iligh Temperature Steam Application

2. Respective elevations:

2. Fischer & Porter Report DP-2224-1 #002 61S'-6", 618'-5", 615'-9", 615'-6'

' GO85SO1A

Fischer & Porter PT-0338, -0342, -0346, -0347 t

'N~/

Sheet 3 Component Fischer & Porter Safety Injection System Pressure Transmitters DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions Figures 7, 8 and 9 of the report define the service conditions and the test conditions exceeded the service conditions. The guide-lines are met as discussed in Sheet 2.

DORGR 1B Radiation Gamma The guidelines are met as the radiation received is less than the qualified level.

Beta DORGR 1C Submergence These transmitters are located above the flood level of 596'-0";

therefore, the guidelines are met for submergence.

DORGR 1D Containment Sprays The guidelines are met. Equipment is qualified for chemical spray by evaluation as presented in Sheet 2.

O nu0481-0284j-43 401 Rev 2

Fischsr & Porter PT-0338, -0342, -0346, -0347 Sheet 3 (Contd)

O Component Fischer & Porter Safety Injection System Pressure Transmitters DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions Use of the LOCA conditions is acceptable because CP Co and NUREG-0458 recognize that, although the peak temperature and pressure for an MSIS inside containment are greater than that for a LOCA, the duration is short and the effect will be minimal.

DORGR 2B Radiation Same statement as DORGR 1B DORGR 2C Submergence Same statement as DORGR 1C DORGR 2D Chemical Sprays Same statement as DORGR 1D i

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, nu0481-0284j-43 402 Rev 2 l

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,Q b b V d d Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EOulPMENT DESCRIPTION QUALIFICATION OUTSTANDING Parameter Accident Qualification ' Accident Qual METHOO ITEMS j Syatem: Operating h Section Engineered 30 days 177,3 cafeguards system Plant 1.D. Number: Temperature Section LS-1105; LS-1108 ( F) 135 See Sheet 2 See Sheet 2 Evaluation II.D.8 Component:

-l Mechanical alternator Pressure Section Manufacturer: (PSIA) 14.7 Sed Sheet 2 11. D. 8 See Sheet 2 Evaluation Square "D" Company Model Relative g Class g p,r: Humid.*f (%) 100 See Sheet 2 Section Evaluation l II.D.8 See Sheet 2 y Ty e AW-1 chase Order Number:

i 5935-M-22 S Function /fvvice:

Actuates ESF room Red 6 Section sump pumps 5 x 10 See Sheet 2 II.D.7 See Sheet 2 Evaluation i Accuracy: Spec: Aging t

' Demo: Section 40 years Greater than 40 II.D.8 1 Evaluation

years ESF room Submergence l

Elevauon: Not subject to 570'-10" submergence Flood Level Elevatm Above Finod Level:

Y s: No:

m DOCUMENTATION REFERENCES NOTES 0

y 1. Final Report on Consulting Services for Engineering Support on LS-1105 and LS-1108. Nuclear Environmental Qualification Report, Wyle Laboratories G-OR5A.01 A

Squara D LS-1105, LS-1108 Sheet 2 O

Component Square D Mechanical Alternator These alternators are used to turn on the sump pumps in the ESF rooms should they be needed. Qualification data has been located. The materials have a qualified life of over 40 years but are not qualified for the total radiation dose which will be received. They are qualified for 1 x 10' rads and the accident will result in 5 x 10' rads. Should these switches fail, due to radiation damage, the operator can ascertain the ESF room level by the indication and alarm from LT-1107 and LT-1110 and manually actuate the sump pumps.

Since it would be better if the operator could be freed from having to manually start the sump pumps, these switches teill be replaced with qualified switches by June 1982 assuming no procurement problems.

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nu0481-0284k-43 408

f n Owner: Consumers Power Company Component Sheet No:

Facility: Palisades Revision:

Docket: 50 255 Date:

ENVIRONMENT DOCllMENTAllON REFERENCES OUALMATM MTMA N EQUIPMENT DESCRIPTION METHOD llEMS Parameter Accident Ouablication Accident Oues System Operatin0 Engineered Time 30 Days See Sheet 2 Section See Evaluation Safeguards System III.B Sheet 2 Plant I D. Number: Temperature LT-0358, LT-0359 ( r) See Figures 7 6 8 See Sheet 2 Section See Evaluation component:

II.D.1 Sheet 2 Level Transmitter p,,,,,

y,no,acturer- IPSIA)

See Figure 9 See Sheet 2 Section See Evaluation Fischer & Porter II.D.1 Sheet 2 Mo'$et Number Relative Hun *sity m) 100 See Sheet 2 Section See Evaluation 10B24655ECBB1 II.D.1 Sheet 2 H Purchase Order Number chemica 1,750 to 2,000 ppm See Sheet 2 Section See Evaluation M206(97) Spray Boric Acid With 50 II.D.2 Sheet 2 runc w is m e. t 100 ppm N Il24 Containment Sump hh 7

Level (Rad) 2 x 10 See Sheet 2 Section See II.D.5 Sheet 2 Accuracy: Spec: A 0ang Demo 40 Years Plus IACA See Sheet 2 Section tocation: I1.D.8 Inside atainment Submeroence Not Subject To Submergence 608'4,,

fluod Level Elevation Above Flood Lovet.

Yes X No DOCUMENT ATION REFERENCES NOTES ro G 08'i8 0 t A

?

I Sheet 2 Component Containment Sump Level Transmitter LT-0358, LT-0359 No qualification data for the containment sump level transe.itter could be located. These instruments provide indication of the containment sump level.

Since there is no way to drain the majority of the sump water during the LOCA and since the functioning of these transmitters was not considered in the FSAR safety analysis, qualification is not required. As described in Consumers Power Company's response to NUREG-0737 (dated December 19, 1980 to D M Crutchfield of NRC), Item II.F.l(5), new containment level transmitters will be installed by January 1, 1982.

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EQUIPMENT OUAltFICATION REPORT ,

Revision:

FacAty: Palisades Date:

Docket: 50-255 ENVIRONMENT DONJMENTATION REFERENCES OUALIFICATION OUTSTANDING EQUIPMENT DESCRsPTION METHOD ITEMS Parameter Accident Quahtcahon Accident Oua, 30 Days 30 Days tion 1 Evaluation Engi e red Safety System Plant i D. Number- Temperature 135 135 Section 1 Evaluation EMA-1210, 1112, 11141 g F)

II.D.8 Component.

"

SSection 2 Evaluation

, ,py,7* 14.7 14.7 Louis-Allis II.D.8 ty (%) 100 100 Section 2 Evaluation B2 8600 2, 3 H t- COGS II.D.8 g Purchase Order Number che.ucas 5935-Mg None Spray Functiont Service.

Containment Spray Raaston g ,,, g6 See Sheet 2 Section 6 Evaluation Pump Motor (Rad)

II D 7 Accuracy- Spec: Ag D*'" 40 Years See Sheet 2 Section 6 Evaluation L C*"' II.D.8 ESF Room Subrwoenc* Not Subject to 8" **#E*"

571'-10" I f tood Level Elevaten Above Flood Level Yes No DOCUMENTATION REFERENCES NOTES l

$ 1. Electric Motor Data Sheet for Containment Spray Pump ru Motors Supplied by Iouis-Allis

2. Letter from Mr Schreiber of Louis-Allis to C St Onge of Bechtel, dated September 17, 1980 3 Letter from C St Onge of Bechtel to Mr Schreiber of Lo' -Allis, dated September 9, 1980 - -

,58 O f A

, - - . . . . . . . . -. .. . _ _ . . . - - - - - - _ . - . - . . . . - = .

E k

Sheet 4 4

/

! Component Containment Spray Pump Motors (EMA-1210,'.112,1114) l t

l These components were not included in the November 1978 CP Co Submittal and, therefore, were not addressed by the Franklin Center Report. .

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nuG980-0593c-43 420

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

EQUtPMENT GUALIFICATION REPORT Owner: Consumers Power Company Component Sheet No:

Facuity: Palisades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRfPDON OUALIFICATION OUTSTANDitK1 Parameter Aca.ident Quahncarica Accident Qual METHOD ITEMS System: Operanno Tw Section Test and Engineered 30 days 30 days III.B 1' 2 Evaluation safeguards system Ptet i D. Number Temperature EMA-1113 -1207,-1200 Section T" "

(* F) 135 140 II.D.8 1* 2 Evaluation '

. Motor Pressure Section Test and Meutacturer: (PSIA) 14.7 14.7 II.D.8 1* 2 Evaluation Westinghouse Model Number Relauve Test and Section y 68F13512 H

VI%I 100 100 Evaluation II.D.8 b

H Purchase Order Number:

Chemical 5935-M-1 Spray None ,

Function / Service lip safety injection Radiation pump motor (Rad) 5 x 10 6 8 Section Test and 2 x 10 II.D.7 2, 3 Evaluation Accuracy: Spec: Agno Dem: 40 years + LOCA Section 40 years + LOCA Location: II.D.8 2' 3 ESF room Su w gerice Elevation: Not subject to 572'-1" submergence Flood Level Elevation Above Flood Level:

Yes: No:

DOCUMENTATION REFERENCES NOTES l

$ 1. Westinghouse data sheet for IIPSI motor giving tempera-N ture rise and insulation

2. Environmencal Qualification of Class 1E Motors for Ng lear Out-of< ontainment Use, dated 6/76 _ -

' G 0858-01 A

= , - - - - _ . . -

i Westinghouse EMA-1113, -1207, -1209 l 4

Sheet 4 I

Component High-Pressure Safety Injection Pump Motors i^

This equiment was not included in the November 1978 CP Co submittal and, therefore, was not addressed by the Franklin Research Center report. ,

4 J

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i I

nu0481-02841-43 429 '

i

EQUIPMENT GUALIFICATION REPORT ,

Facety: Palisades Reh Cate:

Docket: 50-255 -

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOD ITEMS Parameta Accident Quahtcas.on Accident Qual System: Operetna Engineered Safety Tkn* Section 0 Days 30 Days 1, 2 Evaluation System III.B Plant 1 D. Number- Temperature M4A-120(>-1111 (* F) 135 140 1, 2 Evaluation 8

Component:

Motor Prnsure Manufacturer: (PSIA) 34,7 34,7 Section

1, 2 Evaluation General Electric II.D.8 Mode 4 Number: Ronalvve Hu"*"Y N "

SK8188h7A100 100 100 1, 2 Evaluation 8

o Furchase Order Number-5935-M-1 Spr Funct6an/ Service.

Low Pressure Safety )

6 6 Section

( 5 x 10 5 x 10 Analysis Injection Pump II.D.7 Mo or curacy Spec: Agng ection Derno 40 Years + LOCA 40 Years + LOCA Analysis g,,, II . D. 8 ESF Room %g, E w atton: Not Subject to 572

_8" , 572 e _9a submergence Flood Level Elevaten A: eve Flood Level.

Yes. No _

NOTES DOCUMENTATION REFERENCES l

'l 1. General Electric Co data sheet for LPSI motor giving to temperature rise and insulation class level.

2. Letter dated August 21, 1980 from J M Allen of Mobil Oil Corp to J 11 Knoblach of Wyle Lab regarding lubri-caring of1. ,_ _

858 Ot A

I GE EMA-1206, -1111 l Sheet 4 ;

Component GE LPSI Pump Motors (EMA-1206 and -1111)

This equiment was not included in the November 1978 CP Co submittal and, therefore, was not addressed by the Franklin Research Center report.

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i nu0481-0284m-43 434

EQUIPMENT OUALIFICATION REPORT ,

Facihty: Pahsades Revision:

Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOO ITEMS Psameter Accident Quahticahon Accident Quel System: Operating Engineered Time 30 Days 30 Days Section 1, 3 Simultaneous Safeguards System III.B Test Plant i D. Number T w eture See Note 1 ('F) See Figures 7 & 8 300 Section 1, 3 Simultaneous II.D.1 Test Mot % Irted Pressure Va lEfecturer. (PSIA) See Figure 9 84.7 Section 1, 3 Simultaneous Limitorque (Rel) II.D.1 Test Ac Motor I Model Number Reteeve Humioty m) 100 100 Section 1, 3 Simultaneous

s. SMB-00-15 II.D.1 Test d Purchase Order Number chemicas 1750 to 2000 ppm Boron Water, Sodium Spray Boric Acid With 50 Thiosulfate and Section 1,2,3 Simultaneous Funcnonts e e. to 100 ppm N 3124 Solution of Naoll II.D.2 Test See Note 1 RmSanon 7 g (Rad) 2x 10 2.04 x 10 Section 1, 3 Sequential II.D.5 rest Accuracy: Spec: Aging Demo: 40 Years Plus LOCA 100 llours at 180*C Section 1, 3 Sequential tocation: P1us LOCA II.D.8 Test Inside Containment Elevahon: Not Subject To gog 59 7'-0" Submergence Flood tevel Elevahon 596'-0" Above Flood tevet:

Yes. X No.

DOCUMENTATION REFERENCES NOTES m

l G

l

< l. Test Report 600456, Nuclear Power Station 1. liigh-pressure injection valves MO-3007, -3009, -3011 to Qualification Type Test Report, Limitorque Valve and -3013; redundant high-pressure injection valves Ac taa to rs for PWR Service MO-3062, -3064, -3066 and -3068.

858-01 A

._ m

O O EOUlPMENT QUALIFICATION REPORT O

p Component Sheet No.:

Facety: Pallsados Revision Docket: 50-255 Date:

DOCUMENTATION REFERENCES (cont) NOTES (cont) i'

2. BLC-7999, R L Castleberry (Bechtel) to 2. MO-3007, MO-3009, MO-3011 and MO-3064 are at ,

R C Bauman (CP Co), dated August 13, 1979. elevations:

2 597'-1", 596'-11", 596 11", 597'-3", respectively.

3. Report B0058, Limitorque Valve Actuator Qualifica- The rest ,of the MOVs are at 597 '-0".

tion for Nuclear Power Station Service.

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to G-0858-02A

Limitorque M0-3007, M0-3068 Sheet 2 O

Component Limitotaue Valve Actuators These units were tested using the type test method described in IEEE Std 382-72. Test Report 600456 and Appendices A through F describe the results of the test performed on a typical Limitorque valve actuator (SMB-0) with a 40-foot-pound motor (SMB-0-40). A typical unit was used because the only difference in units is size (Reference 3). All materials used are the same as in Model SMB-00-15. The unit was mechanically aged to approximately 40 years of service life. The motor was thermally aged for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 180 C. The unit was also radiation aged at 4 megarads plus an accident dose of 200 megarads (2.04 x 10') radiation aging. LOCA testing was performed at Limitorque's environmental test facility. The LOCA test consisted of the dual spike with maximum temperature attained in 15.2 and 13.8 seconds, respectively. Chemical spray was maintained at a pH of 10.5 using a mixture which is primarily a sodium thiosulfate solution (in accordance with Table 1 of IEEE Std 382-72). This is more caustic than the 7 to 8.3 pH solution of hydrazine solution used at the Palisades Plant (Reference 2). The first spike of 300 degrees and 84.7 psia was maintained for 33 minutes, then reduced to the 120*F starting point. The second transient was attained with a dwell of 30 minutes at 300*F and 84.7 psia. The chamber temperature was then reduced to 250*F and 44.7 psia and maintained at these conditions for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

Temperature and pressure wete again reduced to 200*F and 24.7 psia and maintained for the duration of the test. Chemical spray was maintained at an average pH of 10.5, and relative humidity was maintained at 100% by keeping the condensate at the bottom of the tank at the same temperature as the air / vapor mixture by periodic injection of steam. The equipment operated satisfactorily before, during and after the above test.

The valve operators are located inside containment above the 596'-0" flood level; therefore, they are not subject to submergence.

1 i

l l

O nu0980-0479a-43 437 Rev 2 i

Limitorqua M0-3007, MO-3068 Sheet 3 Component Limitorque Valve Actuators DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Con u. tons The test was run at temperature and pressure steam conditions which exceed that given in the FSAR and the report,Section II.D.1; therefore, the guidelines are met.

DORGR IB Radiation Gamma The valve actuator was subjected to a radiation dose of 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10'), which exceeds the 2 x 10' rad requirement; therefore, the guidelines are met.

i Beta DORGR IC Submergence j -

These valve operators are above the 596'-0" flood level.

i V Therefore, the guidelines are met.

DORGR ID Containment Sprays

[ Chemical sprays used were in accordance with IEEE Std 382-72, wtich consisted of boron water, sodium thiosulfate and sodium hydroxide to a pH of 10.5. This solution is more caustic than the boron water, hydrazine and sodium hydroxide at a pH of 7 to 8.3

used at the Palisades Plant (Reference 2); therefore, the guidelines are met.

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions Use of the LOCA conditions is acceptable for main steam line break (MSLB) qualification because CP Co and NUREG-0458 recognize that although the peak temperature and pressure for an MSLB inside containment is greater than that for a LOCA, its duration is shore and the effect will be minimal. Use of more realistic assumptions l'

results in a temperature profile that is within the LOCA profile; therefore, the guidelines are met.

O f

1 nu0980-0479a-43 438 Rev 2

Limitorqua MO-3007, M0-3068 Sheet 3 (Contd)

Component Limitorque Valve Actuators DORGR 2B Radiation The valve operators were subjected to a total operational and accident dose of 2.04 x 10' rads, which exceeds the required 2 x 10' rad dose for this accident; therefore, the guidelines are met.

DORGR 2C Submergence Same statement as in DORGR IC.

DORGR 2D Chemical Sprays Same statement as in DORGR 1D.

DORGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Type testing was selected.

DORGR 4B Qualification by Type Testing

1. Simulated Service Conditions and Test Duration The test duration was 30 days, and the test profile was the dual spike given in IEEE Std 382-72, which satisfies the 30-day requirement; therefore, the guidelines are met.

2. Test Specimen Typical Limitorque valve oporator SMB-0-40 was tested and is similar to SMB-00-15 (Reference 3); therefore, the guidelines are met.

3. Test Sequence The test sequence was as follows: aging (thermal, mechanical and radiation), saismic (not discussed), radiation exposure and LOCA simulation and is discussed in Sheet 2; therefore, the guidelines are met.

t nu0980-0479a-43 439 Rev 2

Limitorque M0-3007, M0-3068 O)

\~-

Sheet 3 (Contd)

Component Limitorque Valve Actuators

4. Test Specimen Aging Thermal - 100 Hours at 180*C Mechanical - 1,208 Operations Radiation - 2.04 x 10' Total Dose Gamma These conditions satisfy the 40-year operating life plus the LOCA requirement; therefore, the guidelines are met.

4

5. Functional Testing and Failure Critieria The test specimen was successfully operated during the LOCA test of 30 days and did not fail; therefore, the guidelines are met.

6. Installation Interfaces The existing valves and the test valve have the same

( installation orientation; therefore, the guidelines are met.

DORGR 6 Margin The guidelines of DORGR 4 are satisfied and no margin factors are required.

DORGR 7 Aging l See DORGR 4B.

DORGR 8 Documentation References 1, 2 and 3 form the documentation.

[

nu0980-0479a-43 440 Rev 2

Limitorqua MO-3007, MO-3068 O Sheet 4 Component Limitorque Valve Actuators The qualification test that was referenced in the CP Co submittal of November 1978 is not the test normally provided by Limitorque for pressurized water reactor (PWR) units. Franklin Institute's comment on this submittal, which states that the test specimen was not exactly the same as that being qualified, is true. However, all Limitorque valve operators are the same except for size; ie, materials are identical (Reference 3). This fact is also true for the Reliance motors which, together with the Limitorque units, compose the motorized valve operator.

The test profile of Test Report 600456 in which the Limitorque valve operator and Reliance motor are tested as a unit more closely follows that required by the Palisades FSAR and Figures 7 and 8 for the 30-day period. For these reasons, Test Report 600456 is sufficient qualification for Limitorque/

Reliance motor-operated valves with Class H insulation in a LOCA environment.

(~~

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nu0980-0479a-43 441

EQUIPMENT QUALIFICATION REPORT p

Revision Facihty: Palisades Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES METHOD ITEMS Parameta Accident Oualifcation Accident Ouas system: Opwatog 1, 3 Simultaneous Engineered Time 30 Days 30 Days Section III.B Test Saf egua rds System MO N 2,~ D bl0, T ature See Figures 7 & 8 300 Section 1, 3 Simultaneous g,

MO-3014 II.D.1 Test Mot D ' rated Pressure Valve See Figure 9 84.7 Section 1, 3 Simultaneous acturer IPSIA)

LimYrque -(Rel) II.D.1 Test Ac Motor SMB 1

'Y WI

II.D.1 Test b Purchase Order Number Chemical 1750 to 2000 ppm Boron Water, Sodlum spray Boric Acid With 50 Thiosulfate and Section 1, 2, 3 Simultaneous Funct6on/ Service.

to 100 ppm N 114 2 Solution of Naoll II.D.2 Test

! Iow-Pressure Ran$stkm 7 g Injection Valve (Rad) 2 x 10 2.04 x 10 Section 1, 3 Sequential II.D.5 Test Accuracy: Spec: Agong Demo 40 Years Plus LOCA 100 llours at 180*C Section 1, 3 Sequential Plus LOCA II.D.8 Test tocaton:

Inside Containment ElevatWm:

Not Subject To Submergence

! Flood tevel Elevaten 596'-0" Above Floodlevel.

Yes- A No:

NOTES 2

DOCUMENTATION REFERENCES l

1. Respective elevations:

n) 1. Test Report 600456, Nuclear Power Station Qualification Type Test Report, Limitorque Valve 596'-11", 597'-2", 596'-7".

Actuators for PWR Service 858 01 A

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Limitorque M0-3010, M0-3014 O

Sheet 2 Component Limitorque Valve Actuators This unit was tested using the type testing method described in IEEE Std 382-72. Test Rcport 600456 and Appendices A through F describe the results of the test performed on a typical Limitorque valve actuator (SMB-0) with a 40-foot pound motor (SMB-0-40). A typical unit was used because the only difference in units is size (Reference 3). All materials used are the same as in Model SMB-3-100. The unit was mechanically aged to approximately 40 years of service life. The motor was thermally aged for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 180*C. The unit was also radiation aged at 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10') radiation aging.

LOCA testing was performed at Limitorque's environmental test facility. The LOCA test consisted of the dual spike (referenced in IEEE Std 382-72) with maximum temperature attained in 15.2 and 13.8 seconds, respectively. Chemical spray was naintained at a pH of 10.5 using a mixture which is primarily a sodium thiosulfate solution (in accordance with Table 1 of IEEE Std 382-72).

This is more caustic than the 7 to 8.3 pH solution of hydrazine solution used at the Palisades Plant (Reference 2). The first spike of 300 degrees and 84.7 psia was maintained for 33 minutes, then reduced to the 120*F starting point . The second transient was attained with a dwell of 30 minutes at 300*F and 84.7 psia. The chamber temperature was then reduced to 250*F and 44.7 psia and maintained at these conditions for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . Temperature and pressure were again reduced to 200*F and 24.7 psia and' maintained for the duration of the test. Chemical spray was maintained at an average pH of 10.5, and relative humidity was maintained at 100% by keeping the condensate at the bottom of the tank at the same temperature as the air / vapor mixture by periodic injection of steam. The equipment operated satisfactorily before, during and after the above test.

The valve operators are located inside cor.tainment above the 596'-0" flood level; therefore, they are not subject to submergence.

O nu0980-0477a-43 444 Rev 2

Limitorqua MO-3010, M0-3014

\-

Sheet 3 Component Limitorque Valve Actuators DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions The test was run at temperatura and pressure steam conditions which exceed that given in the FSAR and the report,Section II.D.1; therefore, the guidelines are met.

DORGR IB Radiation Gamma The valve actuator was subject to a radiation dose of 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10'), which exceeds the 2 x 107 rad requirement; therefore, the guidelines are met.

B_e t_a DORGR 1C Submergence

'~'N The valve operators are above the 596'-0" flood level; therefore, the guidelines are met.

DORGR 1D Containment Sprays l

! Chemical sprays used were in accordance with IEEE Std 382-72, which consisted of boron water, sodium thiosulfate and sodium hydroxide to a pH of 10.5. This solution is more caustic than the boron water, hydrazine and sodium hydroxide at a pH of 7 to 8.3 used at the Palisades Plant (Reference 2); therefore, the guidelines are met.

DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment l

DORGR 2A Temperature and Pressure Steam Conditions Use of the LOCA conditions is acceptable for main steam line break (MSLB) qualification because CP Co and NUREG-0458 recognize that although the peak temperature and pressure for an MSLB inside

containment is greater than that for a LOCA, its duration is short and the effect will be minimal. Use of more realistic assumptions results in a temperature profile that is within the LOCA profile; therefore, the guidelines are met.

l l [\-)/

s nu0980-0477a-43 445 Rev 2

Limitorqua M0-3010, MO-3014 Sheet 3 (Contd)

O Component Limitorque Valve Actuators DORGR 2B Radiation The valve operators were subjected to a total operational and accident dose of 2.04 x 10' rads, which exceeds the required 2 x 10' rad dose for this accident; therefore, the guidelines are met.

DORGR 2C Submergence Same statement as in DORGR 1C.

DORGR 2D Chemical Sprays Same statement as in DORGR 1D.

00RGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Qualification was by test.

DORGR 4B Qualification by Type Testing

1. Simulated Service Conditions and T_est Duration The test duration was 30 days, and the test profila was the dual spike given in IEEE Std 382-72, which satisfies the 30-day requirement; therefore, the guidelines are met.

2. Test Specimen Typical Limitorque valve operator SMB-0-40 was tested and is similar to SMB-3-100 (Reference 3); therefore, the guidelines are met.

3. Test Sequence The test sequence was as follows: aging (thermal, mechanical and radiation), seismic (not discussed), radiation exposure and LOCA simulation as discussed in Sheet 2; therefore, the guidelines are met.

4. Test Specimen Aging Thermal - 100 Hours at 180*C O

nu0980-0477a-43 446

Limitorque M0-3010, MO-3014 6

l

/N b Sheet 4 l

l

, Component Limitorque Valve Actuators The qualification test that was referenced in the CP Co submittal of November 1978 is not the test normally provided by Limitorque for pressurized water reactor (PWR) units. Franklin-Institute's comment on this submittal, which states that the test specimen was not exactly the same as that being qualified, is true. However, all Limitorque valve operators are the same except for size; ie, materials are identical (Reference 3). This fact is also true for the Reliance motors which, together with the Limitorque units, compose the motorized valve operator.

The test profile ot Test Report 600456 in which the Limitorque valve operator and Reliance motor ace tested as a unit more closely follows that required by the Palisades FSAR and Figures 7 and 8 for the 30-day period. For these reasons Test Report 600456 is sufficient qualification for Limitorque/

Reliance motor-operated valves with Class H insulation in a LOCA environment.

\~./ l l

l l

1 l

l O

nu0980-0477a-43 448

EQUIPMENT GUALIFICATION REPORT g p

Revision Facihty: Paksades Date:

Docket: 50-255 ENVIRONMENT DOCLAENTATION REFERENCES EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Ouahhcaton Accident Oual System: Operatino Engineered Time 30 Days 30 Days section 1, 3 31multaneous

[II.B rest Safeguards System

tant I D. Nurrber: Temperature MO-3015, MO-3016 (* F) See Figures 7 & 8 300 Section. 1, 3 Simultaneous II.D.1 Test i

Moto N ra.ted e,..au,e Valve See Figure 9 84.7 Section 1, 3 Simultaneous (PSIA)

Lin N T[ueturer ( Rel) II.D.1 Test Ac Motor Model Number l'.olaHvo

"""#Y N '

S' MB-2-60 II.D.1 Test

$ Purchase Order Number Che.nicas 1750 to 2000 ppm Boron Water, Sodium Spray Boric Acid with 50 Thiosulfate and Section 1, 2, 3 Simultaneous Function / Service.

to 100 ppm N 1124 Solution of Na0li iI.D.2 Test Shutdown Clg From Radianon Primary & Clg Water (Rad) 2 x 10 2.04 x 10 Section 1, 3 Sequential Return II.D.5 Test Accuracy: Spec: Aging Demo: 40 Years Plus LOCA 100 llours at 180 C Section 1, 3 Sequential tocatav Plus LOCA II.D.8 Test Inside Containment Submergence Not Subject To Elevallon:

Submergence 612'-10" Flood tevel Elevahon 596'-0" Above Flood tevel:

Yes: y No.

NOTES g

DOCUMENTATION REFERENCES l M 1. Test Report 600456, Nuclear Power Station l

Qualification Type Test Report Limitorque Valve l Actuators for PWR Service, 1

l 2858 01 A i

I

\

! EQUIPMENT OUALIFICATION REPORT Component Sheet rdo...

Owner: Consumers Power Company

. Facihty: Pdaades Reh Date:

! Docket: 50-255 l .

! DOCUMENTATION REFERENCES (cont) NOTES (cont)

I j 2. BLC-7999, R L Castleberry (llechtel) to R C Bauman (CP Co), dated August 13, 1979.

3. Report B0058, Limitorque Valve Actuator Qualifica-tion for Nuclear Power Station Service.

1 i

1 1

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o 4

4 i

1 1

5 i

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i i

i G-0858-02A

)

l

Limitorqua FO-3015, M0-3016 Sheet 2 Component Limitorque Valve Actuators. _

These units were tested using th type test method described in IEEE Std 382-72. Tat Report 600436 and Appendices A through F describe the results of the test performed on a typical Limitorque valve actuator (SMB-0) with a 40-foot pound motor (SMB-0-40). A typical unit was used because the only difference in units is size (Reference 3). All materials used are the same as in Model SMB-2-60. The unit was mechanically aged to approximately 40 years of service life. The motor was thermally aged for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 180*C.

The unit was also radiation aged at 4 megarads plus an accident dose of 200 megarado (2.04 x 10') r;diation aging. LOCA testing was performed at Limitorque's environmental test facility. The LOCA test consisted of the dual spike (referenced in IEEE Std 382-72) with maxix.an temperature attained in 15.2 and 13.8 seconds, respectively. Chemical spray was maintained at a pH of 10.5 using a mixture which is primarily a sodium thiosulfate solution (in accordance with Table 1 of IEEE Std 382-72). This is more caustic than the 7 to 8.3 pH solution of hydrazine solution used at the Palisades Plant (Reference 2). The first spike of 300 degrees and 84.7 psia was maintained for 33 minutes, then reduced to the 120*F starting point. The second transient was attained with a dwell of 30 minutes at 300*F and 84.7 psia. The chamber temperature was then reduced to 25]*F and 44.7 psia and maintained at these conditions for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . Temperature and pressure were again reduced to 200'F and 24.7 psia and maintained for the duration of the test. Chemical spray was maintained at an average pH of 10.5, and relative humidity was maintained at 100*. by keeping the condensate at the bottom of the tank at the same temperature as the air / vapor mixture by periodic injection of steam. The equipment operated satisfactorily before, during and after the above test.

The valve operators are located inside containment above the 596'-0" flood level; therefore, they are not subject to submergence.

O nu0980-0478a-43 451 Rev 2

Limitorqua M0-3015, M0-3016

,n.

(a I Sheet 3 Component Limitorque Valve Actuators DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions The test was run at temperature .nd pressure steam conditions which exceed that given in the FSAR and the report,Section II.D.1; therefore, the guidelines are met.

DORGR 1B Radiation Gamma The valve actuator was subjected to a radiatica dose of 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10'), which exceeds the 2 x 10' rad requirement; therefore, the guidelines are met.

Beta

_s DORGR 1C Submergence kl s The valve operators are at an elevation above the 596'-0" flood ,

level. Therefore, the guidelines are met.

DORGR 1D Containment Sprays Chemical sprays used were in accordance with IEEE Std 382-72, which consisted of boron water, sodium thiosulfate and sodium hydroxide to a pH of 10.5. This solution is more caustic chan the horon wacst, hydrazine and sodium hydroxide at a pH of 7 to 8.3 used at the Eslisades Plant (Reference 2); therefore, the guidelines are met.

DORGR 2 Service Coaditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions Use of the LOCA conditions is acceptable for main steam line break (MSIS) qualification because NUREG-0458 recognizes that although the peak temperature and pressure for an MSLB inside containment is greater than that for a LOCA, its duration is short and the effect will be minimal. Use of more realistic assumptions results in a temperature profile that is within the LOCA profile; therefore, the guidelines are met.

/O nu0980-0478a-43 452 Rev 2

Limitorqua M0-3015, MO-3016 Sheet 3 (Contd)

O Component limitorque Valve Actuators DORGR 2B Radiation The valve operators were subjected to a total operational and accident dose of 2.04 x 10' rads, which exceeds the required 2 x 10' rad dose for this accident; therefore, the guidelines are met.

DORGR 2C Submergence Same statement as in DORGR 1C.

DORGR 2D Chemical Sprays Same statement as in DORGR 1D.

DORGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Qualification was by test.

DORGR 4B Qualification by Type Testing

1. Simulated Service Conditions and Test Duration The test duration was 30 days, and the test profile was the dual spike given in IEEE Std 382-72, which satisfies the 30-day requirement; therefore, the guidelines are met.

2. Test. Specimen Typical Limitorque valve operator SMB-0-40 was tested and is similar to SMB-2-60 (Reference 3); therefore, the guidelines are met.

3. Test Sequence The test sequence was as follows: aging (thermal, mechanical and radiation), seismic (not discussed), radiation exposure and LOCA simulation as discussed in Sheet 2; therefore, the guidelines are met.

O nu0980-0478a-43 453 Rev 2

Limitorque MO-3015, M0-3016 V

Sheet 3 (Contd)

Component Limitorque Valve Actuators

4. Test Specimen Aging Thermal - 100 Hours at 180'C Mechanical - 1,208 Operations l Radiation - 1.04 x 10' Total Dose Gamma i

1 These conditions satisfy the aging requirement of a 40-year operating lifu plus LOCA; therefore, the guidelines are met.

5. Functional Testing and Failure Critieria The test specimen was successfully operated during the LOCA test of 30 days and did not fail; therefore, the guidelines are met.

6. Installation Interfaces

[~')

N_s/

The existing valves and the test valve have the same installation orientation; therefore, the guidelines are met.

DORGR 6 Margin The guidelines of DORGR 4 are satisfied and no margin factors are required.

DORGR 7 Aging See DORGR 4B.

DORGR'8 Documentation References 1, 2 and 3 form the documentation.

J nu0980-0478a-43 454 Rev 2

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

O O O EQUIPMENT GUALIFICATION REPOftT Component Sheet No:

Owner. Consumers Power Company .

Facility: Palisades Revision Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES

COUIPMENT DESCRIPTION METO.s ITEMS Paramelw Accident OueWenien Accident Oual

System: Opwating '

Feedwater Time 30 Days Section See 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant i D. Numbe' Tempwature 4

LT-0751A, B, C, D gar) Section See

%: See Figures 7 & 8 See Sheet 2 II.D.1 Sheet 2 Evaluation Level Transmitter p, essure i Manufacturw: (PSIAI Section See Foxboro See Figure 9 See Sheet 2 II.D.1 Sheet 2 Evaluation Model Numbw Relative m t*1 Se tion See I 613 DM a

$ 100 See Sheet 2 II.D.1 Sheet 2 Evaluation

" Purchas. Order w Chemicas 1,750 to 2,000 ppn1 i M-1 Sp'*Y boric acid with Section See i runctioniService. 50 to 100 ppm wt N2il 'iSee Sheet 2 II.D.2 Sheet 2 Evaluation Steam Generators % ion Level - Reactor (Rad) Section See 7

Trip Alarm & Indicat 2 x 10 See Sheet 2 II.D.5 Sheet 2 Evaluation Accuracy: Spec: g g .g D'* : Section See Locaton: 140 Years + IOCA See Sheet 2 II.D.8 Sheet 2 Evaluation

[nside Containment %g,

, Elevanon: Subject to .

Section 3ee 595'-7" Submergence See Sheet 2 II.D.3 1heet 2 Evaluation Flood Level Elevaton 596' Above Flood Level.

Yes No: X i

' NOTES DOCUMENTATION REFERENCES G 0858 0t A

A A N Owner: Consumers Power Company Component Sheet No:

Facility: Parisades Reh Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFEnENCES STN EQUIPMENT DESCRIPTION METHOD ITEMS Paramela Accident oudraion Accident ouas System: Operatmo Feedwater Time 30 Days Section See 30 Days See Sheet 2 III.B Sheet 2 Evaluation Plant I D tW Temperature LT-0752A, B, C, D (*F) Section See component. See Figures 7 & 8 See Sheet 2 II.D.1 Sheet 2 Evaluation Level Transmitter Pressure Manufacturw: (PSIA) Section See Foxboro See Figure 9 See Sheet 2 II.D.1 Sheet 2 Evaluation Model Number Relative

" # N 8* I" 8**

613 IN 100 See Sheet 2 II.D.1 Sheet 2 Evaluation

$ Purchase Order Numbw ct=macai 1,750 to 2,000 ppr M-1 Spray boric acid with Section See Function / Service. 50 to 100 ppm U2H: See Sheet 2 II.D.2 Sheet 2 Fvaluation Steam Generator nadiation Level - Reactor Trip (Rad) ,7 Section See Alarm & Indication 2 x 10' See Sheet _ II.D.5 Sheet 2 Evaluation Accuracy: Spec: A0ing Demo. Section See Locaron: 140 Years + LOCA See Sheet 2 II.D.8 Sheet 2 Evaluation Inside Containment % g,nc, Elevation: Not Subject to 597' 8" Submergence , ,

Flood Level Elevaton 596' Above Flood Level-Yes X No DOCUMENTATION REFERENCES NOTES I

l

O O O EQUIPMENT OUALIFICATION REPORT Compm.ent Sheet No:

Reh Facility: Palisados Docket: 50 255 ENVIRONMENT DOCUMENTATION REFERENCES sin EQUIPMENT DESCRIPTION METHOD ITEMS Parameta Accident Ouawenhon Accident Oues System: gauna 1 llour Section Feedwater III.B.5 i

Plant I D. Number Temperature See Note 2 (*F) See Figures 7 & 8 See Sheet 2 Section See Sheet 2 Evaluation Component: II.D.I

)

Level Transmitters e e See Figure 9 See Sheet 2 Section See Sheet 2 Evaluation Manufacturer:

31,p,3

, Fischer & Porter Modet Numbo, we 100 See Sheet 2 Section See Sheet 2 Evaluation See Note 2 Hun *my W) ,

, II.D.1 l

$ Purchase Order Number:

ICE-31 Chemical 1750 to 2000 Ppm SP'"Y Boric Acid With 50 lee Sheet 2 Section ice Sheet 2 Evaluaticn Funct6ont Senrice. Lo 100 N 1124 II.D_2 SG Level and Radenon 6

Pressure for (Red) 1.8 x 10 See Sheet 2 Section See Sheet 2 Evaluation Feedwater Control II.D.5 i Accurecy: Spec: Aging

o.mo: '60 Years Plus LOCA 3ee Sheet 2 Section See Sheet 2 Evaluation Location: II.D.8 Inside Containment Submwoenc* yes See Sheet 2 Section See Sheet 2 Evalua tion Elevet6on:

II.D.3 (See Note 1)

Flood tevel j Elevaton 596'-0" Above Flood Level-Yes' No. y NOTES W DOCUMENTATION REFERENCES -

(D L. LT-0701, -0702, -0704, PT-0702, -0704, at 593'-3",

m LT-0703 at 592'-8".

2. Level transmitters are Model 13Dh65EA and Plant tag numbers LT-0701 through LT-0704. Pressure transmit-ters are 50EP1031B and Plant tag numbers PT-0702 and PT-0704.

G 0858 01 A

Owner: Consuraers Power Company Component Sheet No:

Facihty: Palisades Revision:

Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUALIFlcATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Ouehnceton Mcident Ouel System. Operenna Tlme I 11 ur Section Feedwater II.D.5 Plant i D. Number: Temperature FT-0701 Thru FT-070 t'n See Figures 7 & 8 See Sheet 2 Section See Sheet Evaluation II.D.1 2 component:

Flow Transmitter p,,,,,,,

See Figure 9 See Sheet 2 Section See Evaluation Manufacturer: (PSIAI Fischer & Porter II.D.1 Sheet 2 Model Number. Relative See Evaluation Hun *"4ty t%) 100 See Sheet 2 Section 10B2466AAABI II.D.1 Sheet 2

$ Purchase Order Number N*si 1750 to 2000 Ppm See Note 1 spray See Evaluation Boric Acid with 50 See Sheet 2 Section FunctionIService to 100 Ppm N 3324 II.D.2 Sheet 2 See Note 2 Radelen 6 See Evaluation (Red) 1.8 x 10 See Sheet 2 Section II.D.5 Sheet 2 Accuracy: Spec: gy g

Derno 40 Years Plus LOCA See Sheet 2 Section See Evaluation toceton~ II.D.8 Sheet 2 Inside Containment ,

Devoton: Yes See Sheet 2 Section See Evaluation II.D.3 Sheet 2 591'-3" Flood tevel Elevate Abrive Flood Level Yes' Na X DOCUMENTATION REFERENCES NOTES

1. PO 9801527 (CE) for FT-0701 and FT-0702 only; to PO ICE-B1-9801527 for FT-0703 and FT-0704 only.

2. Steam generator flow for FT-0703 and FT-0704; 1 feedwater flow for FT-0701 and FT-0702.

G otA

g...___ . _ __ _ . _ ___ _ _ _ _ _ _ .._.. .___. _._ _ ___ _ _ _ _ __.___._____ _ _ . _ ___._.._ _ _ __. _ . _ _.___.. _ _ _ _

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!' LT-0701, LT-0704 l PT-0702, PT-0704 l

FT-0702, FT-0704 l Sheet 4 1

Component Fischer & Porter Level, Pressure and Flow Transmitters i <

l i This wquipment qualification was not reviewed by Franklin Research Center.

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nul080-0053d-43 471 i

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EQUIPMENT OUAllFICATION REPORT Owner: Consumers Power Company Component Sheet No:

Facihty: PaEsades flevision:

Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES Parameter Accident ouawication Accident Qual METHOD ITEMS system: Operahno inne Section Feedwater 30 days See Sheet 2 try,g See Sheet 2 Test Plant i D. Number. Ternporature PT-0752A, 11, C & D g.pl 88CEI""

See Figures 7 & 8 See Sheet 2 PT- g gg B,C&D II.D.1 See Sheet 2 Test Pressure transmitter Pressure Manufacturer: (PSIA) See Figure 9 See Sheet 2 Section Foxboro II.D.1 See Sheet 2 Test Model Number Re:ative Section 611CM """*8dVI%I 100 See Sheet 2 t II.D.1 See Sheet 2 Test t

Purchase Order Number crwmical 1,750 to 2,000 ppm H-1 Spray I" boric acid with See Sheet 2 See Sheet 2 Evaluation Functm/ Service: 50-100 ppm N II24

See Note 1 Radiation (Haa) 7 Section 2 x 10 See Sheet 2 See Sheet 2 Evaluation II.D.5 Accuracy spec: 39 ,g Derno. "

40 years + LOCA See Sheet 2 See Sheet 2 Evaluation toc,non 11.D.8 Inside containment g

L**

Note Yes See SIeet 2 II.D.3 tee Sheet 2 Evaluation Flood Level

, ,g ,,

L Atation Above Flood tevel:

Yes. x No:

DOCUMENTAllON REFEREK,t2 NOTES

1. Letter from R.J. Breen (Foxboro) f.o A.H. Yuile 1. Steam generator pressure - 2/4 logic ro (Combustion Engineering), dated 5/ //69 end reactor trip

2. Letter, R J Breen (Foxboro) to M R' Wade, Consumers Power Company, April 7, 1980 2. Respective elevations:

3. Letter R L llau,erer vcIall(CombustionFngineefng)to

)1 Consumers Power Companv i 597 '-8" , 597 '-9" , 597 '-7 " , 59'l '-7" ,

505'-7" 505' 7"_ 549'-7" 50s' 7"

31A

Foxboro PT-0752A, B, C & D PT-0751A, B, C & D b

\- >

Sheet 2 Component Foxboro Pressure Transmitte..a Reference 1 provides a description and results of the test performed on trans-mitter Models 613DM and 611GM. The cable connecting the transmitters to other associated equipment will be qualified separately.

A saturated steam-air mixture was applied to the test chamber for the first hour at a pressure of 90 psig and a temperature of 318*F. Pressure was then reduced to 60 psig and temperature to 288'F for a period of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with the steam-air still being used. At the end of this period, pressure and tem-perature were reduced to O psig and 75'F, respectively, with a relative humidity of less than 50%. During testing, output of the cells was monitored and calibration checked at each test condition and at the conclusion of test-ing. All transmitters were tested with integral amplifiers. The transmitters operated satisfactorily at the end of the 13-hour test.

With respect to chemical spray, the corrosion rate on the housing from chemi-cal spray conditions is negligible. Because the housing protects the trans-mitter internals, chemical spray is not a consideration.

[~T Reference 2 states that Foxboro believes that these transmitters will with-

\ stand 1 x 108 rads TID if fitted with the MCA kits. Reference 3 shows that these were kitted. l'x 10' rads TID will occur within'the first hour if 100%

core melt at initiation is assumed and much later if lesser amounts of damage occur. No aging information could be located for these transmitters.

These transmitters are required to provide reactor trip on low steam generator pressure should an MSLB occur and for steam generator pressure indication during a LOCA. During the main steam line break, the low steam generator pressure trip will occur at or before high containment pressure trip or high containment radiation trip so that the transmitters only need be qualified for 190*F, 5 psig and 20 R/h until trip (high radiation set point is 20 R/h). The transmitters are qualified for these conditions as shown by the test and the evaluation of the ability to withstand radiation. Since the time elapsed until actuation is short, the effects of accelerated aging will bs insignifi-cant. PT-0751A, B, C & D are subject to submergence (~ 5"); however, the transmitters provide the necessary trip prior to submergence. No aging du a could be located for these transmitters which would demonstrate qualification for long-term post-LOCA steam generator monitoring. Should these monitors fail, steam generator pressure could not be monitored; however, plant shutdown could still proceed in an orderly fashion as steam generator pressure indi-cation is not central for a LOCA.

However, since CP Co believes this to be of some value to the operator, these transmitters will be replaced with qualified transmitters by June 1982 assuming no procurement problems.

O' O

nu0980-0577a-43 473 Rev 2

i Foxboro 0752A, B, C & D Sheet 3 Component. Foxboro Pressure Transmitters Refer to Sheet 2 for discussion of this equipment.

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Component Thermostats TS-1849, -1650, -1851, -1852, -1856, -1857, -1858, -1859

]

l -This equipment was not included in the November 1978 CP Co submittal and, l

therefore, was not addressed by the Franklin Research Center report.

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nu0481-0284n-43 483

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

EQUIPMENT OUALIFICATION REPORT ,

p Revision Facility: Pallsades Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Accident Quawcaton Accident Qual System: Operatog Tim

30 Days 30 Days Section See Sheet 2 Evaluation IIVAC III.B Plant i D. Number Temperature See Note i g.F) 104 104 Section See Sheet 2 Evaluation Component: See Note 2 II.D.8 Pressure Switch pressure See Sheet 2 Evaluation Manufacturer. (PStA) 14.7 14.7 Section II.D.8 United Electric Model Number Relative Humksty t%) 80 80 Section See* Sheet 2 Evaluation J302-553 II.D.8 s- Purchase Order Number Chemical 98994 Spray None Functiont Service.

Containment fligh- tion 0 4 1.3 x 10 3.0 x 10 Section 1. Evaluation Pressure Switches II.D.7 Accuracy: Spec: 30*O 40 Years Plus 1,0CA 1. Evaluation 40 Years Plus Section o o:

LOCA II.D.8 g,,,.

Rooms 118 & 123 Subrw oence Not Subject Elevat6on:

to Submergence Note 3 Flood Level Elevaton Above Flood Level:

Yes: No.

DOCUMENTATION REFERENCES NOTES

$ 1. Wyle NEQ Report No 17435-1 dated August 4, 1980. 1. PS-1801, -1801A, -1802, -1802A, -1803, -1803A, -1804

, to and -1804A.

2. Temperature for Room 123 is 104*F; for Room 118 is 80 F.

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v v EQUIPMENT GUALIFICATION REPORT -

Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsades Revision Docket: 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES l OUAUFICATION OUTSTANOING ENNT DESCWim METHOO HEMS Parametw Accident QuaWication Accident Oual System- Opwateo i Section ays Days m .B See Sheet 2 Evaluation id r Co i Plant 10 Numbw: Tempwature

, Section I 3 See Sheet 2 Evaluation PT-1805 & PT-1814 80 212 II.D.8 Component.

Transmitter Pressure u.nutacturw: IPSIA) SectiOn Fischer & Porter 14.7 14.7 II.D.8 See Sheet 2 Evaluation Motjel Nunca Relative Section SOEP 1071 ACX "'Y OI 80 80 II.D.8 See Sheet 2 Evaluation

@ Purctme Ords Numbw Cwas

! 5935-M-206 Spray None i

Functiont Service Containment Pressurs "

f Section Negligible Yes II.D.7 : See Sheet 2 Evaluation Accuracy Spec: 3 9 ,g

' Demo: Sec fon tocai.on- ,See 40 Years + 1.0CA Yes II 0.8 See Sheet 2 Evaluation Notes 1 and 2

- - - liot Subject Ei.,v.non; i 592'-8", 593'-8" to Submergence Ilood Level Elevaton Above Flood Level Yes No

, DOCUMENTATION REFERENCES NOTES ro 1. Instruction 15ulletin 50EP1000, Rev 1. 1. PT-1805 and PT-1814 are located in the corridor near Room 118 behind a l'-6" thick wall.

l

2. Fischer & Porter Engineering Report

DP-2204-51-B--006, Dated December 2, 1968 i

G 0858 0 t A

Owner: Consumers Power Company Component Sheet No:

Facthty: Pahsades Revision:

Docket: 50-255 Date:

ENVinONMENT DOCUMENTATION REEEHENCES OUAUFICATION OUTSTANDe4G EQUIPMENT DESCRIPTION METHOD liEMS Parameter Accident Oudfecahon Accident Qual System Operstmo Section lleating, Ventilation- Trne 30 Days 30 Days III.B See Sheet 2 Evaluation and Air Conditionini Plant i D Numter: Temperature Section PT-1812,-1815 (*'I 104 212 II.D.8 See Sheet 2 Evaluation Component.

Transmitter Pressure Manufacturer: Ip I Section 14.7 14.7 II.D.8 3ee Sheet 2 Evaluation Fischer & Porter m Number: netanve Section Hu Yl%I 80 80 II.D.8 3ee Sheet 2 Evaluation 50M" E M 03 Purchase Order Number: --

5935-M-206 None E _ ,S m .

"" Section Containment Pressure Negligible Yes II.D.7 ice Sheet 2 Evaluation Accuracy: Spec ^9"9 Demo Section 40 Years + LOCA Yes II.D.8 ice Sheet 2 Evaluat on Locaton Room 123-See Note 1 g_,

tu,vanon. Not Subject 596'-0" to Suhmergence F tuod Level Elevahun Above Flood Level Yes No' DOCUMENTATION REFERENCES NOTES

1. Instruction Bulletin 50EP1000, Rev 1 1. These components are required for a LOCA only; Pischer & Porter 2204-51-B-006 although Room 123 will experience harsh environmental conditions in the event of an MSLB, this equipment is not required for this accident (see Section II.D.6).

8 01 A

C O O EQUIPMENT QUALIFICATION REPORT ,

Facility: Palesades W

Date:

Docket: 50 253 ENVIRONMENT DOCUMENTATION REFERENCES METHOD ITEMS Paramela Accident Ouawicesion Accident 'Oual System Operating lleating, Ventilating Tim

30 Days See Sheet 2 Sec III.B. See Sh 2 Evaluation and Air Conditioning Piant i D. Number- lemperature EMB- 1, p rl 135 See Sheet 2 Sec II.D.1 See Sh 2 Evaluation 0

componenk 33{

Motor Pressor.

Manufacturer: PSIA)

General Electric 14.7 See Sheet 2 Sec II.D.1 See Sh 2 Evaluation Model Nun.ter: Relative 5K256YK161 Hunwy m) 100 See Sheet 2 Sec II.D.1 See Sh 2 Evaluation v-

Purchase Order Ninnber:

C 5035-M-59 Spr None r_ , S.

Room Air Cooler Radiation 7

Motor (Rad) 1 x 10 See Sheet 2 Sec II.D.5 See Sh 2 Evaluation Accuracy: Spec: g g,ng Demo 40 Years Plus LOCA See Sheet 2 Sec II.D.8 See Sh 2 Lvaluation ESF Rooms w egence Elevation: Not Subject to Submergence Note 1.

flood Level Elevation Above Flood Level' Yes X No.

DOCUMENTATION REFERENCES NOTES

!g ro 1. Respective elevastions:

585'-S", 58h'-7", S85'-S", 58h-7".

l G Otl58 01 A

GE EMB-0131, -0133, -0211 and -0221 O

Sheet 2 Component ESF Room Air Cooler Motors The Engineered Safeguards Rcom air cooler motors are required for cooling after a LOCA. No qualification data could be located for these motors. The motors are qualified for temperature, pressure and humidity by virtue of being Class H insulation. However, qualification to aging and radiation are unknown. The temperature and radiation dose comes from the assumption that all of the safeguards' pumps are working and all of the piping is full of hot water. This is not always the case during the LOCA. There is a 46* safety factor in the heat load calculation for the room. The plant emergency procedures state that the LPSI pumps will be stopped at the time at which switchover to recirculation is reached (20 minutes for large LOCAs). That will decrease the heat load about 10% of the load (including safety factor) initially and more as the LPSI piping cools. If one of the fan motors should fail, there is a redundant one already working. If more than one cooler motor fails, the motor will still be operating within the rating. The operator can open the doors and hatches to the room and also override the high radi2 tion trip on the damper of the normal ESF room ventilation duct. These motors, howeve:, will still be replaced with qualified motors by June 1982, provided no procurement problems arise.

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nu0980-0531a-43 495

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! Component Reuter Stokes Neutron Detectors (

i Franklin Research had no questions on these monitors.

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- ~ - _ _ _ .

O EQUtPMENT QUALIFICATION REPORT g

Facliity: Palisades .

Revision Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION Parameter Accident Quahhcanon Accident M METHOO ITEMS System: Operahno Tkm' "

Primary coolant 30 days 30 days 1, 3 Simultaneous system test Plant i D. Number Temperature H0-1042A,HO-1043A (*F) See Figures 73B 300 Section 1, 3 Simultaneous Component: II.D.1 test Motor operated vgivp g fpy* See Figure 9 84.7 Section Simultaneous LimItorque (Rel) II.D.1 1, 3 test ac motor M Nurnber e y 3 100 100 Seetion Siisultaneous SMB-000 II.D.1 1, 3 test

""**O'"

, Chemicas 1,750 to 2,000 ppm Boron water, g spray Section Simultaneous boric acid with 50 sodium thiosulfate, 11.D.2 1,2,3 test

, ,% to 100 ppm NpH4 and solution of NaOH Isolation for Ramaton pressure relief (Rad) 8 Section Sequential 2 x 10 2.04 x 10 II.D.5 1, 3 test valves Accuracy: Spec:

Demo:

" 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at Section Sequent'.a1 40 years + LOCA toco, n: 180C + LOCA 11.D.8 1, 3 test Inside containment % gonc.

Elevation:

. submergence 660'-0" _

Flood Level Elevation 596'-0" Above Flood Level.

Yes. x No:

.o DOCUMENTATXWe REFERENCES NOTES o l

1. Test Report 600456, Nuclear Power Station Qualification Type Test Report, Limitorque Valve Actuators for PWR Service y 858-0tA 4

~ O ORT O

Owner: Consumers Power Company Component Sheet No.:

Facil6ty: Palisades Revision.

Docket: 50-255 Date:

DOCUMENTATION REFERENCES (cont) NOTES (cont)

2. BLC-7999, R.L. Castleberry (Bechtel) to R.C. Batsman (CPCo), dated 8/13/79

3. Report B0058, Limitorque Valve Actuator Qualifi-cation for Nuclear Power Station Service Nc-i G-0858 02A 1 ,

l I

Z,imitorque MO-1042A,. MO-1043A Sheet 2 O

Compenent Limitorque Valve Actuators These units were tested using the type test method described in I'IEE Std 382-72. Test Report 600456 and Appendixes A through F describe the results of the test performed on a typical Limitorque valvo actuator (SMB-0) with a 40-foot pound motor (SMB-0-40). A typical unit was used because the oniv difference in units is size. All materials used are the same as in Model SMB-000. The unit was mechanically aged to approximately 40 years of service life. The motor was thermally aged for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 180*C. The unit was also radiation aged at 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10') radiation aging. LOCA testing was performed at Limitorque's environmental test facility. The LOCA test consisted of the dual spike (referenced in IEEE Std 382-72) with maximum temperature attained in 15.2 and 13.8 seconds, respectively. Chemical spray was maintained at a pH of 10.5 using a mixture which is primarily a sodium thiosulfate solution (in accordance with Table 1 of IEEE Std 382-72). This is more caustic than the 7 to 8.3 pH solution of hydrazine solution used at the Palisades Plant (Reference 2). The first spike of 300*F and 84.7 psia was maintained for 33 minutes, then reduced to the 120*F starting point. The second transient was attained with a dwell of 30 minutes at 300*F and 84.7 psia. The chamber temperature was then reduced to 250*F and 44.7 psia and maintained at these conditions for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . Temperature and pressure were again reduced to 200*F and 24.7 psia and maintained for the duration of the test. Chemical spray was maintained at an average pH of 10.5 ar.d relative humidity was maintained at 100*, by keeping the condensate at the bottom of the tank at the same temperature as the air / vapor mixture by periodic injection of the steam. The equipment operated satisfactorily before, during and after the above test.

The valve operators are located inside containment at an elevation well above the 596'-0" flood level; therefore, they are not subject to submergence.

O nu0481-0284p-43 515 Rev 2

i Limitorque M0-1042A, MO-1043A s

v Sheet 3 c omponent Limitorque Valve Actuators DORGR 1 Service Conditions Inside Containment for LOCA Conditions DORGR 1A Temperature and Pressure Steam Conditions The test was run at temperature and pressure steam conditions which exceed that given in the FSAR and the report, Sec-tion II.D.1; therefore, the guidelines are met.

DORGR 1B Radiation Gamma The valve actuator was subjected to a radiation dose of 4 megarads plus an accident dose of 200 megarads for a total dose of 204 megarads (2.04 x 10'), which exceeds the 2 x 10' rad requirement; therefore, the guidelines are met.

Beta DORGK IC Submergence (A) These valve operators are at an elevation well above the 596'-0" flood level; therefore, the guidelines are met.

DORGR 1D Containment Sprays Chemical sprays used were in accordance with IEEE Std 382-72, which consisted of boron water, sodium thiosulfate and sodium hy-droxide to a pH of 10.5. This solution is more caustic than the baron water, hydrazine and sodium hydroxide at a pH of 7 to 8.3 used at the Palisades Plant (Reference 2); therefore, the guidelines are met.

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nu0481-0284p-43 516 Rev 2 l

Limitorque M0-1042A, MO-1043A O

Sheet 3 (Contd)

Component Limitorque Valve Actuators DORGR 2 Service Conditions for a PWR Main Steam Line Break Inside Containment DORGR 2A Temperature and Pressure Steam Conditions Use of the LOCA cenditions is acceptable for main steam line break (MSLB) qualification because CP Co and NUREG-0458 recognize that, although the peak temperature and pressure for an MSLB inside ontainment is greater than that for a LOCA, its duration is short and the effect will be minimal. Use of more realistic assumptions results in a temperature profile that is within the LOCA profile; therefore, the guidelines are met.

DORGR 2B Radiation The valve operators were subjected to a total operational and accident dose of 2.04 x 10' rads, which exceeds the required 2 x 10" rad dose for this accident; therefore, the guidelines are met.

DORGR 2C Submergence Same statement as in DORGR IC DORGR 2D Chea1 cal Sprays

.iame statement as in DORGR 1D O

nu0481-0284p-43 517

C O O EQUIPMENT OUALIFICATION REPOAT ,

Facility: Paksades bh:

Date:

Docket: 50 255 ENVIRONMENT DOCUMENTATION REFERENCES ,

EOUtPMENT DESCRIPTION METHOO ITEMS l Parametw Accident Quaikaton Accident Quer System: Operahng Time 30 Days Section See Sheet 2 Evaluation PCS III.B.5 j Plant i D. Numbe' Tempwature Section LT-0103 ( ri Fig 7 and 8 See Sheet 2 II.D.1 m heet 2 Evaluation Component:

Level Transmitter Pressure sgm Manufacturw: (PSIA) Fig 9 See Sheet 2 ee Sheet 2 Evaluation a

II.D.1

, Foxboro i

Model Number: Relahve Humidity (%) 100 See Sheet 2 Section See Sheet 2 Evaluation 613 let II.D.1 Purchase Ordw Numbw sn Chemical 1,750 to 2,000 ppm y MI B Spray Boric Acid, 50 to See Sheet 2 Section See Sheet 2 Evaluation 100 ppm N 1124 II.D.2

)

FuncDon/ Service.

Radianon Section Pressurizer (Radj 2x10 7R See Sheet 2 Se Sheet 2 Evaluation II.D.5 Level Accuracy: Spec: Ag,ng Demo: Partial 40 Years + ACC See Sheet 2 Section See Sheet 2 Evaluation t ocat.on: I1.D.8 Cont Submer0ence ""'I "

Elevehon: Yes See Sheet 2 See Sheet 2 Evaluation II D 3 4

590'-0" Flood Level Elevehon 596'-0" Above Flood Level:

Yes: No' X l

to DOCUMENTATION REFERENCES NOTES k

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T O

Sheet 2 Component Foxboro Level Transmitter No qualification data could be located for this transmitter. This transmitter provides for wide-range pressurizer level indication. Pressurizer level indication is not required for safe shutdown of the plant following LOCAs or MSLBs as evidenced by the fact that the procedures do not mention the use of pressurizer level indication.

Since pressurizer level indication may prove to be useful, a qualified level l transmitter will be purchased and installed in place of this transmitter by June 30, 1982.

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O O od Owner: Consumers Power Company Component Sheet No:

Facihty: Pahsados Flevision:

l Docket: 50 255 Date:

ENVIRONMENT DOCUMENTAilON REFERENCES Accident oues MEllOO lif Mr.

Parameter Accident ouewscahon 30 Days See Sheet 2 Section See Evaluation Pr r Coolant III.B Sheet 2 l

System Plant I D. Number: Temperature j PT-0103 (* F) See Figures 7 & 8 See Sheet 2 Section See Evaluation II.D.1 Sheet 2 p Cggi:

j A See Figure 9 See Sheet 2 Section See Evaluation

1. 0EracdYE Foxboro II.D.1 Sheet 2 Model Number: Relative Evaluation 100 See Sheet 2 Section See l 611Gli Hum 8d4 8%)

II.D.1 Sheet 2 Purchew Order Number:

M-1 1,750 to 2,000 ppn1 See Sheet 2 Section See Evaluation 1 M Chemical SPY II.D.2 Sheet 2 Boric Acid With

! runctionsService 50-100 ppm N 21I4 Pressurizer T-72 w enon 7 See Sheet 2 Section See Pressure Indication (Rad) 2 x 10 II.D.5 Sheet 2 Accuracy. Spac: Aging Demo 40 Years Plus LOCA See Sheet 2 Section See l

Locat.on-II.D.8 Sheet 2 Inside Containment I

'8*"**

Yes See Sheet 2 Section See Evaluation Eiev. tion 591'-0" II.D.3 Sheet 2 4 5 tood Level

! Elevation 596'-0"

. Above Flood level Yes No X i

i DOCUMENT ATION REFEHENCES Notts

1. Qualificatioid Test Report for Rosemount Pressure

Transmitter Model 11J3A. Rmt Rpt 3788, Rev A,

! March 1980.

l G OM'A 08 A

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Foxboro PT-0103 !

O Sheet 2 Component Foxboro Pressure Transmittet No qualification data could be found concerning these transmitters. These transmitters are used to monitor pressurizer pressure on a wide range. The Plant will install at the first appropriate outage Rosemount 1153A pressure transmitters for wide-range pressure signal and indication for the subcooling meter. These transmitters will be used to monitor primary system pressure wide range.

The Rosemount pressure transmitter 1153A has been tested for LOCA environment per IEEE 323 (1971) (Reference 1). The tests included:

a. Temperature pressure and humidity test.

1. Rise to 350*F and 120 psig.

2. Hold for 10 minutes and add chemical spray.

3. Let cool; then rise to 350*F and 120 psig and hold for 10 minutes.

4. Let cool to 303*F and 55 psig and hold for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

5. Let cool to 250'F, 15 psig and hold for 56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months .

6. Chemical spray during Steps 3 and 4 and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months of Step 5.

7. Let cool.

b. No aging test. This is satisfactory as the transmitters are brand new and, thus, have had no degradation should there be a LOCA in this interim O

period.

c. Radiation at 0.5 Mrad /h until 44 Mrad is reached (4.4 x 10').

d. No submergence data is required as these are mounted above the submergence level.

These transmitters will operate throughout the LOCA for the following reasons:

The temperature in the LOCA after 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months (total test time) is about 140*F.

Conditions will return to ambient at t = 11 days. Since the transmitter is new, it will withstand the additional aging obtained from 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months to 11 days.

Detailed calculations show that the containment atmosphere is 1.1 x 107 TID for 30 days. The transmitter is mounted on a 2-ft thick wall very close ::o two other thick walls which are perpendicular to the one on which the .

transmitter is mounted. As a result, the dose is reduced by a factor of 4 (ie, 1/4 of an infinite cloud of radioactivity will affect the valve).

O nul080-0499d-43 527 Rev 2

Foxboro PT-0102A, B, C&D l

v Sheet 4 (Contd)

Component Foxboro Pressure Transmitters Frankline: TLs guidelines require that equipment which is exposed to chemical sprays must be qualified for the most severe chemical environment l by either test or analysis. In addition, the effects of enclosure i pressure boundary integrity and fluid in-leakage must be consid-ered. The licensee has stated that the transmitters have aluminum top covers, and some of the transmitters will become submerged, at which time seal leakage would become competitive with corrosion.

Documentation providing evicence (in the form of either testing or analysis) that the performanco of this equipment due to contain-ment spray should be provided.

Response: As discussed in Sheet 2, the equipment will perform its functica prior to submergenre; therefore, degradation due to submergence is not a consic'eration. Also, the corrosion rate due to the chemical spray environment of aluminum is insignificant over the time interval involved. Thus, the instrumentation incide the housing is protected from the spray, and degradation due to chemical spray is not a consideration.

O L) v' nu0980-0415c-43 537

Owner: Consumers Power Company Component Sheet No:

Facility: Pabsades Revtsson Docket: 50-255 Date:

ENVIRL. it:NT DOCUMENTATION REFERENCES EQUIPMENT DESCR6PTION OUALIFICATION (MJTSTANDING Parameter Accident Quantcaem Accident Qual ' METHOD ITEMS System: Operatog Seetton .

Primary taolant T== 30 days See Sheet 2 111.8 See Sh 2 Evaluation Plaru l D. Nunce'), Temperature Section See Notes l&~ ('F)

See Figures 768 See Sheet 2 II D'I See Sh 2 Evaluation Resistance tempera-Presswo Section ti g @gy,,ptor (PSIA) See Figure 9 See Sheet 2 11.D.1 See Sh 2 Evaluation Rosemount Model Number blative Seetion 104 VCX Hundety (%) 100 See Sheet 2 See Sh 2 Evaluation 11.o.1

" Purchase Order Number:

$ 1703781 cnemcas 1,750 to 2,000 ppm Section

- V boric acid with 50 See Sheet 2 II.D.2 Functm/Servce. to_100_ ppm _N2 34 Ilot cold leg Ramation Section coolant temp 7 (Rad) 2 x 10 See Sheet 2 II.D.5 See Sh 2 Evaluation Accuracy: Spe De'a)

Aomo 40 years + 1.0CA Section See Sheet 2 II.D.8 See Sh 2 Evaluation tocata:

Inside containment Elevate: Not subject to lotes 1 & 2 submergence viood tevei 596'-0" Elevate Above Flood tevel Yes. X No DOCUMENTATION REFERENCES NOTES l

l. Plant identification numbers are as follows:

m TE-Oll2CA TE-Oll211A TE-0122CA TE-012211A TE-0112CB TE-0110 lie TE-0122CB TE-012211B TE-0112CC TE-011211C TE-0122CC TE-012211C TE-0112CD TE-011211D TE-0122CD TE-0122ilD _

! Gl858-01 A l

i O O EOutPMENT OUALIFICATION REPORT O

Owner: Consumers Power Company Component Sheet No.:

Facety: Pdsades Revision Date:

Docket: 50 255 i

DOCUMENTATION REFERENCES (cont) NOTES (cont) l 1. The respective elevations of the above resistant temperature detectors are:

619'-1" 613'-2" >607' 616'-10" 617'-11" 613'-6" 617'-6" 616'-10"

>607' 613'-5" >607' 616'-10" J

617'-11" 613' 6" 617'-6" 616'-10" i 2. Plant identification numbers are as follows:

TE-0111A TE-011111 TE-0121A TE 012111 i TE-0111B TE-0121B The respective elevations of the above resistance temperature detectors are:

w y >607' 613'-5" >607' 616'-10" l 617'-11" >607' l

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Rosemount TE-0112CA Through TE-0122HD O

Sheet 2 Component Rosemount Primary Coolant Temperature Detectors The primary loop temperature elements are used to provide input to the steam dump and bypass valves' regulators after trip to provide subcooling indication and to provide input to the thermal margin / low-pressure trip. Qualification information concerning these elements could not be located; however, should these elements fail and that failure be in an unsafe direction, safe shutdown could still be achieved and off-site doses minimized.

Failure of temperature elem( tts TE-0111A, TE-0111B, TE-0111H, TE-0121A, TE-0121B or TE-0121H may result in the steam atmospheric dump valves opening.

The failure would have to be in a specific direction and may require more than one element to fail, depending on the severity of the failure. Should this happen, the operator will definitely hear the open valve (from plant experience) and close it. There are four ways to close the valve and these are located in three areas of the plant. This action was submitted as short-term resolution of problems put forth in I&E Information Notice 79-22 (letter Bixel to Ziemann, October 9, 1979). These elements will be replaced with qualified elements by June 1982 if no procurement problems occur.

The other temperature elements are used as input to the subcooling meter and Thermal Margin / Low-Pressure (TM/LP) trip. The TM/LP trip is not needed during high energy line breaks inside containment. Failure of one channel of sub-cooling indication would still leave one channel functioning and also leave the ability to determine subcool.ing using the two channels of TM/CP which a m not part of the subcooling indication.

Failure of both subcooling channels would still leave indication possible by use of the remaining TM/LP elements. Should all temperature elements fail, rubcooling determination is still possible with use of the in-core thermo-couples. Voids could be detected by erratic behavior of the ex-core neutron detectors or in-core thermocouples. Also, the safety analysis presented in the FSAR showed acceptable consequences with no credit taken for the subcooling meter. As part of the work to comply with NUREG-0578, an order will be placed to purchase qualified temperature elements in November 1980.

O nu0980-0511a-43 540

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Rosemount TE-0112CA Through TE-0122HD f~

t Sheet 4 l Component Rosemount Primary Coolant Temperature Detectors i

i These components were not included in the November 1978 CP Co submittal and were therefore not addressed in the Franklin Research Center report.

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EQUIPMENT OUALIFICATION REPORT ,

Facility: Palisades Revision Docket 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION METHOD ITEMS Paramela Accident Ouahticat a Accident Oual System: Operatoo Twie Section Primary Coolant Sys 30 Days 777,3 Plant i D. Number Tempwature Section E/ P 1057,1059 (* F) See Figures 7 & 8 320F Test II.D.1 1 comperr.nt.

Electropneumatic Pressure Trhtsciurw: (Pe*W See Figure 9 75 psig 1 Test Fischer Controls Model Number Relative Hun *sity mi 'I "

E/P-546 100 100% 1 Test II.D.1 Purchase Order Nrmber:

o O ppm Y

w 68553 Spray See Sheet 2 Section boric acid with 11*D*2 See Sheet 2 Evaluation Functm/ Service 50-100 ppm N 1174 Pressurizer Spray Radiathan 7 7 Se d on Valves (Rad) 2 x 10 2 x 10 2, 4 Evaluation II.D.5 Accuracy: Spec: Aging D'*C: 40 Years + LOCA See Sheet 2 8 3, 4 Evaluation tocation:

Inside Containment Submegence Not Subject to povetton:

Submergence 611'-7", 612'-3" F tood Level Elevation 596' Above Flood,(evel:

Yes A No-DOCUMENTATION REFERENCES NOTES 0 1. Laboratory Report, " Operational Tests of the Fischer to Type 546 Electropneumatic Transducer for Nuclear Re-actor Containment Vessel Service," June 12, 1973.

2. Let ter 11 Douglas Waldron, liarley Company, to W C Cc:,per, Consumers Power Co, Jan 24, 1978.

. ncacc netween 3 ne a.a go n , riscner controis

>a o t A J s, Wyle Laboratories, on Sept 12, 1980. - _

Victoreen RE-1805, -1806, -1807, -1808 It h v

Sheet 2 Component Containment Radiation Monitors These monitors are used to provide containment isolation on high radiation.

These monitors need only be qualified for conditions which might require a high radiation trip but no high containment pressure trip. These conditions are 5 psig, 170*F (saturation at 5 psig) and 20 R (set point is 20 R/hr).

Conditions more severe than this would result in containment isolation on high containment pressure or radiation. The environmental test covered the pres-sure, temperature and humidity and all materials can withstand 20 R.

No aging data could be located concerning these monitors. However, the normal environment is 104*F which is a nonhostile environment. During the accident, the effects of accelerated aging will not be significant due to the short time required for operator, the sealed heavy wall container shielding the monitor from the temperature increase and the very low radiation levels. It is believed that these monitors are qualified with respect to aging.

A new high-range radiation monitoring system will h., installed per post-TMI requirements. The new system will provide the operator with information on radiation levels; however, the new system will not be used to isolate con-

! ,-s tainment on high radiation.

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o nu0481-0284r-e* 552 Rev 2

Victoreen RE-1805, -1806, -1807, -1808 O

Sheet 3 Component Containment Radiation Monitors DORGR 1 Service Cenditions Inside Containment for LOCA Conditions DORGR 1A Temoerature and Pressure Steam Conditions The test parameters exceed the environment to which it must be qualified. See Sheet 2.

DORGR 1B Radiation

'Jamma The monitors will receive a dose of 20 R. All materials can withstand this dose.

Beta DORGR 1C Submergence The monitors will most likely actuate prior to becoming submerged.

If this is not the case, then only one monitor may fail due to submergence but the other three will be able to function.

DORGR 1D Containment Soravs Equipment is qualified for chemical sprays by evaluation as presented in Sheet 2; therefore, the guidelines are met.

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4 i Fischer & Porter LT-1107 i a

! Sheet 4 4

(

Component Fischer & Porter Level Transmitters l This equipment was not included in the November 1978 CP Co submittal and,

therefore, was not addressed by the Franklin Research Center report.

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nu0980-0552d-43 562

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EOUleMENT QUALIFICATION REPORT Fachty: Palisades Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAUFICATION OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parametw Accident Quawicaron Accident Qual System: Opwatog Tw. 30 Days See Sheet 2 Section See Evaluation Radwaste System III.B Sheet 2 EMB"6NS,"""YEE65,

-0245 & -0255 Tyme

, 125 See Shee 2 Section See Evaluation II.D.1 Sheet 2 Component:

Motor Pressure

%,cg,; 4ps43 14.7 See Sheet 2 Section See Evaluation II.D.1 Sheet 2 General Electri Co Model Numbw Relative 8""

5K143DL2348 Hun *my (N 100 See Sheet 2 Section Evaluation II*N'1 Sheet 2 Purchase Order h vn 59 35-11-22BC Chemkai

$ Spray None Function / Service Injection Room Sump Rectanon 6 (Rad) 5 x 10 See Sheet 2 Section See Evaluation Pump tiotor II.D.5 Sheet 2 Accuracy: Spec: Ag,ng onmo 40 Years Plus LOCA See Sheet 2 Section See Evaluation tocation.

II.D.8 Sheet 2 ESF Rooms Not Subject To Elevation Submergence 1

A l , - 5,,

Flood Level Elevation Above Flood Level.

Yes No.

OOCUMENTATON REFERENCES NOTES m

e 4

r0 58 01 A

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i i GE EMB-0155, -0165, -0245, -0255 4

Sheet 4 {

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} Component GE Room Sump Pump Motors l 1, i l Franklin Research Center has not reviewed this equipment for qualification. '

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EQUIPMENT OUALIFICATION REPORT p

Facility: Palisades Revision Date:

Docket: 50-255 ENVIRONMENT DOCUMENTATION REFERENCES Accident Oua, METHOO ITEMS Parameter Accident Oualification System: Operstwig Waste Gas h 30 Days 30 Days Section 1, 2 -

III.B Plant I D. Number Temperature M69A, M69B (* F) 278 750 Section 1, 2 Test component. II.D.1

!!ydrogen Recombiner Pressure Manutecturer: (PSIA) 70 35 Section 1, 2 Test II.D.1 Westinghouse Model Number Relative Hun *sity (%) 100 100 Section 1, 2 Test Model A II.D.1 Purchase Order Number g chemical Spray 1750 to 2000 ppm 2500 ppm Boron as N Boric Acid With 50 Boric Acid With Section 1, 2 Test Function / Service: to 100 ppm N II24 Naoll for nH of in II.D.2 11yd togen Ractation g 7

Recombination (Rad) 2.0 x 10 2.0 x 10 Section 1, 2 Test II.D.5 Accuracy: Spec: Aging D'* : 40 Years Plus IDCA 40 Years Plus LOCA Section 1, 2 Test LDC8oa: II.D.8 Containment Submergence Elevation: None 659'-0" I Flood te"el Elo ntion 596'-0" Above Flood Level:

Yes: X No.

DOCUMENTATION REFERENCES NOTES l

7

1. WCAP-7709-L and Supplements 1 through 6, " Electrical I liydrogen Recombiner for Water Containments,"

" Westinghouse Electric Corporation.

2. Letter W G Bohl, Westinghouse Electric Corporation, t o -'. Kuemin, CP Co, dated July 29, 1980. - -

>S-01 A

Sheet 2 Component M69A, B Hydrogen Recombiners WCAP-7709-L and Supplements 1 through 6 provide descriptions and results of several tests performed on the Model A electric hydrogen recombiners. The recombiners consist of heater elements and bus bar. The cable will be separately qualified. The controls are outside of containment. One test sequence was first energize heaters to 40 kW, then a rapid injection of steam to pressurize the en iber to 69 psia in 10 seconds and then inject sodium tetraborate spray (2,500 ppm boron as boric acid with NaOH to a pH of 10).

Hold at 69 psia for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce to 25 psia for 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months and then 35 psia for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Another separate test was also run in which steam was used to pressurize the test vessel. The test sequence was to increase pressure to 85 psia and hold for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , then reduce the pressure to 20 psia and hold for 21 days (vessel temperature held at 155*F during the 21-day period). During this test, at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the heaters were fully energized and achieved a temperature of 750*F which was maintained throughout the test. This can be seen to envelop the Palisades conditions. During all of these tests, the heaters were energized although in onl; one test is the actual heater temperature noted. Sodium tetraborate was injected into the test chamoer during two of the tests. The sodium tetraborate addition resulted in a spray which contained 2,500 ppm boron as boric acid and sodium hydrozide to give a

[' pH of 10. Both of these spray parameters are more severe than those at

\~ - Palisades. The recombiners are at the Elevation 659'-0" level which is far above the submergence level of Elevation 596'-0". Qualification for aging was demonstrated through an aging test which consisted of 80 heat-up and cooldown cycles. After the seven LOCA tests, the entire unit was irradiated to 2 x 10' Rads gamma. The equipment operated satisfactorily during and/or after all of these tests as described in the report. The report and its Supplements 1 through 4 have been reviewed by the NRC and satisfied the criteria for topical reports and was accepted. Reference 2 provided verification that the recombiners at Palisades were the same as those which were tested.

The hydrogen recombiners are only required for LOCA; therefore, MSLB need not be addressed.

)

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nu0980-0512a-43 568 Rev 2 i

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O Sheet 3 Component M69A, B Hydrogen Recombiners DORGR 1 Service Conditions Inside Containment for LOCA Ccnditions DORGR 1A Temperature and Pressure Steam Conditions The test was run at temperature and pressure steam conditions which exceed that given in the FSAR and the report,Section II.D.1; therefore, the guidelines are met.

DORGR 1B Radiation Gamma Tre recombiner was subjected to a radiation dose of 200 megarads which exceeds the 20 megarad (2.0 x 10 7) requirement; therefore, the guidelines are met.

Beta Beta doses will not affect the recombiner which, except for cable, are all metallic. Cable will be addressed elsewhere.

DORGR IC Submergence The recombiners are located above the flood level; therefore, the guidelines are met.

DORGR 1D Containment Sprays The containment sprays as discussed on Sheet 2 are considered more caustic than the spray water used at Palisades; therefore, the guidelines are met.

DORGR 4 Qualification Methods DORGR 4A Selection of Qualification Method Qualification of the recombiners is by testing.

l DORGR 4B Qualification by Type Testing l

l 1. Simulated Service Conditions and Test Duration The recombiner tests were a series of tests which eventually lead to an accepted topical report an<' c"311fication to IEEE 323-1974. The simulated service c.vnditions exceed those environments at the Palisades Plant. Duration of testing in some cases may not cover the total time .e accident.

Sufficient testing has been done to met une guideline requirement.

O nu0980-0512a-43 569

/

V)

Sheet 3 (Contd)

. Component M69A, B Hydrogen Recombiners

2. Test Specimen The test specimen was the same model recombiner as those installed at Palisades.

3. Test Sequence The radiation was applied after the aging test and the seven LOCA tests. The recombiners have no parts which are age sensitive, so this sequence is acceptable and the guidelines are met.

4. Test Specimen Aging To qualify the recombiner for a 40-year life, it was estimated two test cycles per year would be required of the recombiner.

Eighty cycle tests were initially performed to demonstrate that, if significant aging would have taken place, the

()

recombiners could have withstood the effects. The guidelines are met.

5. Functional Testing and Failure Criteria The test specimen operated during all phases of testing and did not fail; therefore, the guidelines are met.

6. Installation Interfaces The test installation and the existing recombiners have the same orientation.

DORGR 6 Margin DORGR 4 of the guidelines are met; therefore, the margin requirements are met.

DORGR 7 Aging See DORGR 4B.

DORGR 8 Documentation References 1 and 2 form the documentation.

i nu0980-0512a-43 570 Rev 2

Sheet 3 (Contd)

DORGR 8 Documentation References 1 and 2 form the documentation.

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nu0980-0512a-43 571

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Environmental Qualification of f Safety-Related~ Electrical Equipment i

! Palisades Plant

( October 1980 1- i f Consumers Power Company .

, Bechtel Associates Professional Corporation

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.nul080-0075a-43 Rev 2 f

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l Environmental Qualification of l Safety-Related Electrical Equipment I

j Palisades Plant October 1980 I

Consumers Power Company l Bechtel Associates Professional Corporation i

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l Aupendix IV i Computer Output Listing of Equipment l

Found in Hostile Areas I

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RPT. 51 PAL LCS MOTOR CLASS 1E AND SELECTED R00d5 BY SYSTEM 06/05/81 PAGE 1 TYPE COMP ID REO H0 MANUFACTURER MODEL LOC SERVICE PAL CCS MOTOR EMA-1109 M- 34 LOUIS ALLIS CO COGX 03/590 COMP 0HEHT COOLING PUMP P-52A MOTOR EMA-1116 M- 34 LOUIS ALLIS CO COGX 03/590 COMP 0HENT COOLING PUMP P-52C HOTOR EMA-1208 M- 34 LOUIS ALLIS CO COGX 03/590 COMPONENT COOLING PUMP P-52B

.. . . . .. . . . . . .~

VALVE SV -0910 ft-240 AUI0MATIC SUITCH COM LB-831614 R123 COMP. CLG. WATER IHLET TO CONTAIHMENT VALVE SV -0911 M-240 AUTOMATIC SWITCH COM LB-831614 R123 COMP. CLG. WATER DISCH. FROM CONTAIN. CKil VALVE SV -0913 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R123 COMP 0HENT COOLINGSSHUTDH HEAT EXCH. VALVES 2 VALVE SV -0937 M-240 AUTOMATIC SWITCH CON LB-831614 R123 COMP 011EHT C00 LING 1SHUTDH HEAT EXCH. VALVES 2 VALVE SV -c938 M-240 AUTOMATIC SWITCH COM LB-831614 R123 COMPONENT C00 LING 1SHUTDH l! EAT EXCil. VALVES 1 VALVE SV -3940 M-240 AUTOMATIC SWITCil C0!l LB-831614 R123 COMP. CLG. WATER DISCH. FRbM CONTAIN. CKT2 VALVE SV -0944A M-354 AUTOMATIC SWITCil COM THT-8344-Al R123 COMP 0HEHT C00LIllGESilUTDH HEAT EXCil. VALVES 2 VALVE SV -0945 M-240 AUTOMATIC SWITCll CON LB831614 R123 COMPONENT C00LIllG8SiluTDN HEAT EXCH. VALVES 2 VALVE SV -0946 M-240 AUTOMATIC SWITCil COM LB831614 R123 COMPollEHT COOLINGSSHUTDN llEAT EXCH. VALVES 1 VALVE SV -0947 M-234 AUT0!1ATIC SWITCll COM WPHT-8300B61-RF 03/570 COMPONENT C00LINGESHUTDH HEAT EXCH. VALVES 2 VALVE SV -0948 (1-234 AUT0t1ATIC SWITCH COM WPitT-8300B61-RF 03/570 COMPONENT C00 LING 85HUTDH HEAT EXCil. VALVES 1 VALVE SV -0949 M-234 AUTOMATIC SWITCH COM WPitT-8300861-RF 03/570 COMPONENT C00LIllGISHUTDH llEAT EXCil.VALVESI VALVE SV -0950 M-234 AUTOMATIC SWITCH COM WPitT-8300B61-RF 03/570 COMP 0HEtiT C00LIllGtSHUTDH HEAT EXCil. VALVES 2 VALVE SV -0951 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF 03/570 COMP 0HEHT C00LINGSSHUTDN HEAT EXCll.VALVEG1 f

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RPT. 51 PAL' U S PENETR CLASS 1E AHD SELECTED Rs - BY SYSTEM 06/05/81 \ PAGE 2l TYPE CCMP ID REQ HO MANUFACTURER' MODEL LOC SERVICE PAL CIS PEHETR EZ -0110 E- 20 VIKING INDUSTRIES P4 23-0024-0000 FANS V2A & V4A CAHISTER PEHETR EZ -0101 E- 20 VIKING INDUSTRIES P1 23-0048-0000 PRI. COOLANT PP. P508 CAHISTER PEHETR EZ -0102 E- 20 VIKING INDUSTRIES P1 23-0049-0000 SPARE CAHISTER PEHETR EZ -0103 E- 20 VIKING INDUSTRIES P1 23-0050-0000 PRI. COOLANT PP. P50C CAHISTER PEHETP EZ -0104 E- 20 VIKING IHD4STRIES P1 23-0051-0000 PRI. COOLANT PP. P50B CAHISTER PEHETF EZ -0105 E- 20 VIKING INDUSTRIES P1 23-0052-0000 PRI. COOLANT PP. P50A CAHISTER PEHETR EZ -0106 E- 20 VIKING INDUSTRIES P2 23-0020-0000 SPARE CANISTER PEHETR EZ -010/ E- 20 VIKING INDUSTRIES P2 23-0021-0000 LOAD CENTER'B-15 FEEDER CAHISTER PEHETR EZ -0108 E- 20 VIKING INDUSTRIES P2 23-0022-0000 LOAD CENTER B-16 FEEDER CAHISTER PEHETR EZ -0109 E- 20 VIKING INDUSTRIES P3 23-0023-0000 MCC H0.9 FEEDER CAHISTER PEHETR EZ -0111 E- 20 VIKING INDUSTRIES -PS 23-0026-0000 NOV,NOTORS 8 MISC. CAHISTER PEHETR EZ -0112 E- 20 VIKING INDUSTRIES PS 23-0027-0000 MOV, MOTORS & MISC. CAHISTER PEHETR EZ -0121 E- 20 VIKING INDUSTRIES C-1A 23-0029-0000 CONTROL CAHISTER PEHEIR EZ -0141 E- 20 VIKIH0 INDUSTRIES H-1A 23-0042-0000 HUCLEAR INSTR. CAHISTER PEHETR EZ -0142 E- 20 VIKING INDUSTRIES H-1A 23-0043-0000 HUCLEAR INSTR. CAHISTER PEHETR EZ -0143 E- 20 VIKING INDUSIRIES I-1A 23-0038-0000 IHSTRUMENTS CAHISTER PEllETR EZ -0146 E- 20 VIKING INDUSTRIES I-3A 23-0046-0000 INSTRUMENTS & MISC. CANISTER PEHETR EZ -0210 E- 20 VIKING INDUSTRIES P4 23-0025-0000 FAHS VIA & V3A CAHISTER PEHETR EZ -0211 E- 20 VIKING INDUSTRIES P6 23-0028-0000 MOV, MOTORS 8 MISC. CAHISTER PEHETR EZ -0221 E- 20 VIKING INDUSTRIES C-1B 23-0030-0000 CONTROL CANISTER PEHETR EZ -0222 E- 20 VIKING INDUSTRIES C-1B 23-0031-0000 CONTROL CAHISTER PEHETR EZ -0223 E- 20 VIKING INDUSTRIES C-2 23-0032-0000 ROD DRIVE MECH. C0HTROL CAHISTER PEHETR EZ -0224 E- 20 VIKING INDUSTRIES C-2 23-0033-0000 ROD DRIVF MECH. CONTROL CAHISTER PEHETR EZ -0225 E- 20 VIKING INDUSTRIES C-2 23-0034-0000 ROD DRIVE NECH. CONTROL CAHISTER PEHETR EZ -0226 E- 20 VIKING INDUSTRIES C-2 23-0035-0000 SEC. ROD POS. IND. SYSTEM CAHISTER PEHETR EZ -0227 E- 20 VIKING INDUSTRIES C-2 23-0036-0000 SEC. ROD POS. IND. SYSTEM CAHISTER PENETR EZ -0228 E- 20 VIKING INDUSTRIES C-2 23-0037-0000 SEC. ROD POS. IND. SYSTEM CAHISTER PEHETR EZ -0241 E- 20 VIKING INDUSTRIES H-1B 23-0044-0000 HUCLEAR INSTRU. CAHISTER PEHETR EZ -0242 E- 20 VIKING INDUSTRIES N-1B 23-0045-0000 HUCLEAR INSTRU. CANISTER PEHETR EZ -0243 E- 20 VIKING INDUSTRIES I-1B 23-0039-0000 IHSTRUMENTS CANISTER PEHETR EZ -0244 E- 20 VIKING INDUSTRIES I-2 23-0040-0000 IH-CORE MONITOR CAHISTER PENETR EZ -0245 E- 20 VIKING INDUSTRIES I-2 23-0041-0000 IH-CORE MONITOR CAHISTER PEHETR EZ -0246 I-3B 23-0047-0000 INSTRUMEHTS S MISC. CAHISTER i

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RPT. 51 PAL t.VC VALVE CLASS 1E AND SELECTED R0uMS BY SYSTEM 06/05/81 PAGE 3 TYPE COMP ID REQ NO MANUFACTURER MODEL LOC SERVICE PAL CVC VALVE SV -2113 M-234 AUTOMATIC SUITCH COM WPXitVA2023012F CONT CHARGING CISTRIBUTION STOP VALVES VALVE SV -2115 M- lHC AUTOMATIC SMITCH COM WPXHVA2023012F CONT CHARGING DISTRIBUTION STOP VALVES VALVE SV -2117 M- lHC AUTOMATIC SWITCH COM llTX8320A16V CONT AUXILIARY SPRAY STOP VALVE VALVE SV -2009 M-234 AUTOMATIC SWITCil COM WPHT8300B61-RF R150 PRIMARY COOLANT LETDOWN ISOLATION VALVE VALVE SV -2083 M-234 AUTOMATIC SWITCH COM WPHT8300B61-RF R150 PRI. COOL. PUMP CONTROLLED BLEED-OFF VALVE

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{} CLASS 1E AND SELECTED L _ ,3 BY SYSTEM 06/05/81 k,,e 4-RPT. 51 PAL \ _)S INSTRU PAGE TYPE COMP ID REQ HD MANUFACTURER MODEL LOC SERVICE PAL ESS INSTRU E/P-0338 M-233-88 FISHER CONTROLS CO. 546 CONT SAFETY INJECTIDH TAHK T-82)

INSTRU E/P-0342 M-233-87 FISHER CONTROLS CO. 546 CONT SAFETY IHJECTION TANK T-82 4 INSTRU E/P-0346 M-233-87 FISHER CONTROLS CO. 546 C0HT SAFETY INJECTION TAHK T-825 INSTRU E/P-0347 M-233-88 FISHER CONTROLS CO. 546 CONT SAFETY IHJECTIDH TAHK T-82C INSTRU LT -0358 M-206-97 FISCHER & PORTER CO. 10B2495JB CONT CONTAIHMENT SUMP INSTRU LT -0359 M-206-98 FISCHER & PORTER CO. 10B24655ECBB1 CONT CONTAINMENT SUMP INSTRU PT -0338 M-206-4 FISCHER & PORTER CO. 50EP1042A CONT SAFETY IHJECTION TAHK T-82D INSTRU PT -0342 M-206-1 FISCHER 1 PORTER CO. 50EP1041ACXAHS COHT SAFETY IHJECTION TANK T-82A IHSTRU PT -0346 M-206-2 FISCHER & PORTER CO. 50EP1042A C0HT SAFETY IHJECTION TAHK T-82B IHSTRU PT -0347 M-206-3 FISCHER 8 PORTER CO. 50EP1042A CONT SAFETY IHJECTION TAHK T-82C IHSTRU PT -0306 M-206-8 FISCHER 1 PORTER CD. 50EP1072A R123 SAFETY IHJ. PUMP DISCH. PRESS. CKT 2 IHSTRU E/P-3025 M-233-103MASONEILAH INTERHATI 8012 03/570 SHUTDOWH COOLING FLOW CONTROL MOTOR EMB-0137 RELIANCE' ELECTRIC CO 447063 LT 01/590 S.I.H P VALVE M03007 MOTOR EMB-0141 RELIANCE ELECTRIC CO Y220107A4 BU 01/590 S.I.L.P. VALVE M03008 MOTOR EMB-0147 RELIANCE ELECTRIC CO Y220107A4 BU 01/590 S.I.L.P. VALVE M03010 MOTOR EMB-0151 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H.P. MO-3063.

MOTOR EMB-0157 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H.P. MO-3011.

MOTOR EMB-0197 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H P VALVE M03009 MOTOR EMB-0237 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H.P. MD-3064.

MOTOR EMB-0241 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H.P. MO-3062.

MOTOR EMB-0247 RELIAHCE ELECTRIC CO Y274033A6PA 01/590 S.I.L.P. VALVE M03012 MOTOR EMB-0251 RELIANCE ELECTRIC CO Y220107A2 01/590 S.I.L.P. VALVE M03014 MOTOR EMB-0257 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H P VALVE M03066 MOTOR EMB-0261 RELIANCE ELECTRIC CO 447063 LT 01/590 S.I.H P VALVE M03068 MOTOR EMB-0167 RELIANCE ELECTRIC CO 447063LT 01/607 PRIMARY LOOP C00LINC VALVE MD-3015 MOTOR EMB-0271 RELIANCE ELECTRIC CO 704799 FX 01/607 S.D. COOLING VALVE M03016 MOTOR EMA-1206 M- 1 GENER#L ELECTRIC CO. 5K818847A100 02/570 LOW PRESSURE SAFETY IHJECTION PUMP P-67A MOTOR EMA-1207 M- 1 WESTINGHOUSE ELECTRI 68F13512 02/570 HIGH PRESSURE SAFETY IHJECTIDH PUMP P-66A MOTOR EMA-1210 M- 8 LOUIS ALLIS CO COGS 02/570 CONTAIHMENT SPRAY PUMP P-54A MOTOR EMA-llll M- 1 GENERAL ELECTRIC CD. 5K818847A100 03/570 LOW PRESSURE SAFETY IHJECTION PUMP P-67B MOTOR EMA-1112 M- 8 LOUIS ALLIS CD COGS 03/570 CONTAIHMENT SPRAY PUMP P-54B MOTOR EMA-lll3 M- 1 WESTINGHOUSE ELECTRI 68F13512 03/570 HIGH PRESSURE SAFETY IHJECTION PUMP P-66B MOTOR EMA-1114 M- 8 LOUIS ALLIS CD COGS 03/570 CONTAIHMENT SPRAY PUMP P-54C MOTOR EMA-1209 M- 1 WESTINGHOUSE ELECTRI 68F13512 0 V570 HIGH PRESSURE SAFETY IHJECTION PUMP P-66C VALVE SV -0338 M-234-11 AUTOMATIC SWITCH COM WPHT 8300B61RF CONT SAFETY INJECTION TANK T-82D VALVES VALVE SV -0342 M-234-11 AUTOMATIC SWITCH COM WPHT 8300B61-RF CONT SAFETY IHJECTION TANK T-82A VALVES VALVE SV -0346 M 34-11 AUTOMATIC SWITCH COM WPHT-8300B61RF CONT SAFETY INJECTION TAHK T-82B VALVES VALVE SV -0347 M-234-11 AUIONATIC SWITCH COM WPHT 8300D61-RF CONT SAFETY INJECTION TAHK T-82C VALVE SV -3069 M-234 AUTOMATIC SWITCH COM WPHT 8300B61-RF CONT SAFETY IHJ.1SHUIDH COOLING VALVES CIRCUIT 2-VALVE SV -3001 M-234 AUTOMATIC SWITCH COM WPHT8300B61-RF R121B CONTAIHMENT SPRAY VALVES

~ VALVE SV -3002 M-234 AUTOMATIC SWITCH COM WPHT8300B61-RF R121B CONTAIHMEHT SPRAY VALVES VALVE SV -0438A M-336 AUTOMATIC SUITCH COM HTX8320A22X R238 10 DINE REMOVAL SYSTEM VALVES VALVE SV -0438B M-336 AUTOMATIC SWIfCH COM HTX 8320A-22V R238 IODINE REMOVAL SYSTEM VALVES VALVE SV -3029A N-241 AUTOMATIC SWITCH CON LB 8316C-36 02/570 SIRW TAHK LEVEL CONTROLLED VLVd. CIRCUIT 82:

VALVE SV -3029B M-241 AUTOMATIC SWITCH COM LB8316C44 02/5/0 SIRW TAHK LEVEL CONTROLLED VLVS. CIRCUIT #2 VALVE SV -3036 M-241 AUTOMATIC SWITCH COM LB8316C34 02/570 SAFETY INJ.SSHUTDH COOLING VALVES CIRCUIT 2 VALVE SV -3037 M-241 AUTOMATIC SWIICH COM LB 8316C-34 02/570 SAFETY INJ.3SHUTDH COOLING VALVES CIRCUIT 2-

,!~ VALVE SV -3071 M-241 AUTOMATIC SWITCH COM LB8316C44 02/570 SAFETY IHJ.&SHUTEN COOLING VALVES CIRCUIT 2

' VALVE SV -3018 M-241 AUTOMATIC SWITCH COM LB8316C44 03/570 SAFETY IHJ.&SHUTDH COOLING VALVES CIRCUITI VALVE SV -3027A M-241 AUTOMATIC SWITCH COM LB8316C34 03/570 SIRW TAHK LEVEL CONTROLLED VLVS. CIRCUIT ul VALVE SV - 027B M-241 AUTOMATIC SWITCH COM LB8316C36 03/570 SIRu TANK LEVEL CONTROLLED VLVS. CIRCUIT 81 VALVE SV -3030A M-241 AUTOMATIC SWITCH COM LB 8316C-36 03/570 SIRW TAHK LEVEL C0HTROLLED VLVS. CIRCUIT #1

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RPT. 51 PAL L55 VALVE CL ASS 1E AND SELECTED R00.15 BY SYSTEM 06/05/81 PACE 5 TYPE COMP ID REQ NO MANUFACTURER MODEL LOC SERVICE PAL ESS VALVE SV -3030B M-241 AUTOMATIC SWITCH CON LB8316C44 03/570 SIRW TAHK LEVEL CONTROLLED VLVS. CIRCUIT 81 VALVE SV -3031A M-241 AUTOllATIC SWITCH COM LB8316C36 03/570 SIRW TAHK LEVEL C0HTROLLED VLVS. CIRCUIT 81 VALVE SV -3031E M-241 AUT0t1ATIC SWITCH COM LB 8316C-46 03/570 SIEW TANK LEVEL CONTROLLED VLVS. CIRCUIT 51 VALVE SV -3055A M-241 AUTOMATIC SWITCH C0t1 LB 8316C-36 03/570 SHUTDOWN COOLING HEAT EXH. ISOLATING VALVE VALVE SV ~3055B M-241 AUTOMATIC SWITCH COM LB 8316C-34 03/570 SHUTDOWN COOLING HEAT EXH. ISOLATING VALVE VALVE SV -3056A M-241 AUTOMATIC SWITCH COM LB3316C36 03/570 SIRW TANK LEVEL C0HTROLLED VLVS. CIRCUIT 82 VALVE SV -3056B M-241 AUT0l1ATIC SWITCH C0ll LB8316C34 03/570 SIRW TAHK LEVEL CONTROLLED VLVS. CIRCUIT 82 VALVE SV -3057A M-241 AUiollATIC SWITCH C0ll LB8316C36 03/570 SIRW TAHK LEVEL COHlROLLED VLVS. CIRCUIT 82 VALVE SV -3057B M-241 AUT0!1ATIC SWITCH COM LB8316C46 03/570 SIRW TAHK LEVEL CONTROLLED VLVS. CIRCUIT 82 VALVE SV -3059 M-241 AUTOMATIC SWITCH COM LB8316C44 03/570 SAFETY INJ.8SHUTDH COOLING VALVES CIRCUITI VALVE SV -3070 M-241 AUTOMATIC SWITCH CON LB-8316C-44 03/570 SAFETY INJ.4SHUTDH COOLING VALVES CIRCUITI VALVE SV -3212A M-241 AUTOMATIC SWITCH COM LB-8316C-36 03/570 SAFETY IHJ.&SHUTbH COOLING VALVES CIRCUIT 2 VALVE SV -32128 M-241 AUTOMATIC SWITCH COM LB-8316C-34 03/570 SAFETY IHJ.SSHUTDH COOLING VALVES CIRCUIT 2 VALVE SV -3213A M-241 AUTOMATIC SWITCH COM LB8316C34 03/570 SAFETY IHJ.85HUTDH COOLING VALVES CIRCUIT 2 VALVE SV -3213B M-241 AUTOMATIC SWITCH COM LB-8316C-34 03/570- SAFETY IHJ.1SHUTDH COOLING VALVES CIRCUIT 2 VALVE SV -3223A M-241 AUTOMATIC SWITCH COM LB8316C34 03/57C SAFETY INJ.1SHUTDH COOLING VALVES CIRCUITl VALVE SV -3223B M-241 AUTOMATIC SWITCH COM LB8316C34 03/570 SAFETY IHJ.2SHUTDH COOLING VALVES CIRCUITl VALVJ SV -3224A M-241 AUTOMATIC SWITCH COM LB-8516C-36 03/570 SAFETY IHJ.tSHUTDH COOLING VALVES CIRCUIT 1 VALVE SV -3224B M-241 AUTOMATIC SWITCH COM LB-8316C-34 03/570 SAFETY IHJ.1SHUTDH COOLING VALVES CIRCUITI VALV0P V0P-3007 M- 1 LIMITORQUE CORP. SMB-00-15 CONT H P SAFE. IHJ TO REACT. COOL. LOOP 1A 3002 VALV0P V0P-3008 M- lHA LIMITORQUE CORP. SMB-3-100 C0HT L P SAFE. IHJ TO REACT. COOL. LOOP 1A 3002 VALV0P V0P-3009 M- 1HA LIMITORQUE CORP. SMB-00-15 CONT HP IHJECTION VALV0P V0P-3010 M- lHA LIMITORQUE CORP. SMB-3-Ic0 CONT LP INJECTION VALV0P V0P-3011 M- 1HA LIMITORQUE CORP. SMB-00-15 CONT HP IHJECTION VALV0P V0P-3012 M- lHA LIMITORQUE CORP. SMB-3-100 CONT LP IHJECTION VALV0P V0P-3013 M- 1HA LIMITORQUE CORP. Sf1B- 0 0 - 15 CONT HP IHJECTION VALV0P V6P-3014 M- 1HA LIMITORQUE CORP. SMB-3-100 CONT LP IHJ. TO REACTOR COOLANT LOOP 2B 3003 VALV0P V0P-3015 M- lHA LIl1ITORQUE CORP. SMB-2-60 CONT SHUTDOWN COOLIHG FROM PRIMARY LOOP 2 3004 VALV0P V0P-3016 M- 1HA LIMITORQUE CORP. SMB-2-60 CONT SHUTD!! CLG WTR. RETURN O O O

{ (D RPT.51 PAL (},3INSTRU CLASS lE AHD SELECTED Rm ,) BY SYSTEN 06/05/81 ( ,) PAGE 6 TYPE COMP ID REQ HD MANUFACTURER MODEL LOC SERVICE PAL FWS INSTRU FT -0701 M- 1 FISCHER 3 PORTER Co. 10B2466AAAB1 CONT STEAM GEH. E-50A-FEEDWATER FLOW INSTRU FT -0703 N- 1 FISCHER & PORTER CD. 10B2466AAABI CONT STEAM GEN. E-50B-FEEDWATER FLOW

INSTRU LT -0701 M- 1 FISCHER 1 PORTER Cn. 13D2465BA CONT STEAM GEH. E-50A-DOWH COMER

< INSTRU LT -0702 M- 1 FISCHER 3 PORTER CU. 13D2465BA CONT STEAM GEN. E-50A IHSTRU LT -0703 M- 1 FISCHER & PORTER CD. 13D2465BA CONT STEAM GEN. E-508-DOWN COMER IHSTRU LT -0704 M- 1 FISCHER 1 PORTER CD. 13D2465BA CONT STEAM GEN. E-50B INSTRU LT -0751A M- 1 FOXBORD CO., THE 613DN COHT STEAM GENERATOR E-50A LOW LEVEL INSTRU LT -0751B M- 1 FOXBORD CO., THE 613DM CONT STEAM GENERATOR E-50A LOW LEVEL INSTRU LT -0751C M- 1 FOXBORO CO., THE 613DM CONT STEAM GENERATOR E-50A LOW LEVEL INSTRU LT -0751D M- 1 FOXBORO CO., THE 613DM CONT STEAM GEHERATOR E-50A LOW LEVEL IHSTRU LT -0752A M- 1 FOXBORD CO., THE 613DM CONT STEAM GEHERATOR E-50B LOW LEVEL INSTRU LT -0752B M- 1 FOXBORO CDs, IHE 613DM CONT STEAM GENERATOR E-50B LOW LEVEL INSTRU LT -0752C M- 1 FOXBORG CO., THE 613DM CONT STEAM GENERATOR E-50B LOW LEVEL INSTRU LT -0752D M- 1 FOXBORO CO., THE 613DM CONT STEAM GEHERATOR E-50B LOW LEVEL INSTRU PT -0751A M- 1 FOXBORO CO.. THE 611GM CONT STEAM GENERATOR E-50A LOW PRESSURE-CKT 1 IHSTRU PT -0751B M- 1 FOXBORO CO., THE 611GM CONT STEAM GENERATOR E-50A LOW PRESSURE-CKT 2 INSTRU PT -0751C H- 1 FOXBORO CO., THE 611GM COHT STEAM GEHERATOR E-50A LOW PRESSURE-CKT 3 INSTRU PT -0751D M- 1 FOXBORO CO., THE 611GM C0Hf STEAM GEHERATOR E-50A LOW PRESSURE-CKT 4 INSTRU PT -0752A M- 1 FOXBORO CO., THE 611GM CONT STEAM GENERATOR E-50B LOW PRESSURE-CKT 1 INSTRU PT -0752B M- 1 FOXBORO CO., THE 611GM COHT STEAM GENERATOR E-50B LOW PRESSURE-CKT 2 INSTRU PT -0752C M- 1 FOXBORD CU., THE 611GM CONT STEAM GENERATOR E-50B LOW PRESSURE-CKT 3 IHSTRU PT -0752D M- 1 FOXBORO CO., THE 611GM CONT STEAM GEHERATOR E-50B LOW PREStuRE-C'T 4 INSTRU E/P-0736 M-233-96 HONEYWELL CORPORATIO 685435 03/570 STEAM GEN. E-50B AUX. FEEDW4TER CONTRLL IHSTRU E/P-0737 M-233-97 HONEYWELL CORPORATIO 685435 03/570 STEAM GEH. E-50A AUX. FEEDWATER CONTROL i

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RPT. 51 PAL tiGS VALUE CLASS 1E AND SELECTED R0udS BY SYSTEM 06/05/81 PAGE 7 TYPE COMP ID REQ H0 MANUFACTURER MODEL LOC SERVICE PAL MGS i

i VALVE SV -1358 M-234 AUTOMATIC SWITCil COM WPitT-8300861-RF R150 HITROGEN ISOLATION VALVE 5

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RPT. 51 PAL ,

,j% INSTRU CLASS 1E AND SELECTED Rs ,,) BY SYSTEM 06/05/81 ,

PAGE 8-TYPE COMP ID REQ H0 MANUFACTURER MODEL LOC SERVICE PAL MSS INSTRU FT -0702 FISCHER & PORTER CD, 10B2466AAABI CONT STEAM GEN. E-50A-STEAM FLOW IHSTRU FT -0704 M- 1 FISCHER 1 PORTER CO. 10B2466AAAB1 CONT STEAM GEH. E-50B-STEAM FLOW INSTRU PT -0702 M- 1 FISCHER & PORTER CD. 50EP1031B C0HT STEAM GEH. E-50A INSTRU PT -0704 M- 1 FISCHER & PORTER CO. 50EP1031B C0HT, STEAM GEH. E-50B VALVE SV -0522A M-234 HPX0320A26 R238 MAIH STEAM ISOLATION VALVE CIRCUIT HO.2 VALVE SV -0738 M-234 AUTOMATIC SWITCH COM WPHT8300B61-RF R238 STEAM GEN. E-50B TOP BLONDOWN ISOL. VALVE VALVE SV -0739 M-234 AUTOMATIC SWITCH C0ft WPHT8300B61-RF R238 STEAM GEH. E-50B TOP BLONDOWN ISOL. VALVE VALVE SV -0767 M-234 AUT0f1ATIC SWITCH COM WPHT-8300B61-RF R238 STEAM GEN. E-50A BOTTOM BLOWDH ISOL. VALVE VALVE SV -0768 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R238 STEAM GEH. E-50B BOTTOM BLOWDH ISOL. VALVE-VALVE SV -0770 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R238 STEAM GEN. E-50B BOTTOM BLOWDH ISOL. VALVE VALVE SV -0771 M-234 AUTOMATIC SWITCH COM WPHT-830GB61-RF R238 STEAM GEN. E-50A BOTTOM BLOWDH ISOL. VALVE ca 0

RPT. 51 PAL n.15 INSTRU CLASS 1E AND SELECTED R0uilS BY SYSTEM 06/05/81 PAGE 9 TYPE COMP ID REQ HO MANUFACTURER MODEL LOC SERVICE PAL HMS INSTRU HI - 5 M- 1RA GULF GENERAL ATOMIC, HP-6 CONT POWER RANGE SAFETY CHANNEL IHSTRU HI - 6 M- IRA GULF GENERAL ATOMIC, H?-6 CONT POWER RANGE SAFETY CHANNEL IHSTRU HI - 7 M- 1RA GULF GENEP,At A T 0tlI C , HP-6 CONT POWER RANGE SAFETY CHANHEL INSTRU HI - 8 M- IRA GULF GENERAL ATOMIC, HP-f- CONT POWER RANGE SAFETY CHAHHEL INSTRU HI - 9 GULF GENERAL AIDMIC, CONT POWER RANGE HEUTROH CHANNEL XHSTRU HI - 10 GULF GENERAL ATOMIC, CONT POWER RANGE HEUTROH CHAHHEL i

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s RPT. 51 PAL INSTRU CLASS 1E AND SELECTED RLs. BY SYSTEM 06/05/81 PAGE 10 TYPE COMP ID REQ HO MANUFACTURER' MODEL LOC SERVICE PA1 PCS .

INSTRU E/P-1057 FISHER CONTROLS CO. 546 CONT PRESSURIZER SPRAY INSTRU E/P-1059 FISHER CONTROLS CO. 546 CONT PRESSURIZER SPRAY INSTRU LT -0103 M- 1 FOXBORO CO., THE 613HM CONT PRESSURIZER WIDE RANGE LEVEL IND.

INSTRU PT -0102A M- 1 FOXBORO CO., THE 611GM CONT PRESSURIZER PRESS. S.I. CHANNEL - CKT 1 INSTRU PT -0102B M- 1 FOXBORO CO., THE 611GM CONT PRESSURIZER PRESS. S.I. CHANNEL - CKT 2 INSTRU PT -0102C M- 1 FOXBORO CO., THE 611GM CONT PRESSURIZER PRESS. S.I. CHAHHEL - CKT 3 INSTRO PT -0102D M- 1 FOXBORO CO., THE 611CM COHT PRESSURIZER PRESS. S.I. CHAHHEL - CKT 4 INSTRU P T -010 3 M- 1 FOXDORO CO., THE 611GH CONT PRESSURIZER WIDE RANGE PRESS. IND.

INSTRU TE -0111A M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. LOOP MEASUREMENT CHAHHEL 1 INSTRU TE -0111B M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. LOOP MEASUREMENT CHAHHEL 1 INSTRU TE -0111H M- 1 ROSEMAUNT, INC. 104VCX CONT PRI. LOOP MEASUREMENT CHAHHEL 1 INSTRU TE -0112CA M- 1 ROSEMuuMT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANHEL A INSTRU TE *3112CB M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANNEL B

'INSTRU TE -0112CC M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANNEL C INSTRU TE -0112CD M- 1 *0SEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL D INSTRU T E -0112H A M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL A INSIRU TE -0112HB M- 1 ROSEMOUNT, I N C .' 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANNEL B INSTRU TE -0112HC M- 1 ROSEMOUNT, IHC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL C INSTRU TE -0112HD M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL D INSTRU TE -0121A M- 1 ROSEMOUNT, IHC. 104VCX CONT PRI. LOOP MEASUREMENT CHANNEL 2 INSTRU TE -0121B M- 1 ROSEMOUNT, INC. IO4VCX CONT PRI. LOOP MEASUREMENT CHAHHEL 2 INSTRU TE -0121H M- 1 ROSEMOUHT, INC. 104VCX CONT PRI. LOOP MEASUREMENT CHAHHEL 2 INSTRU TE -0122CA M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL A INSTRU TE -0122CB M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANNEL B INSTRU TE -0122CC M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL C INSTRU TE -0122CD M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHANNEL D IHSTRU TE -0122HA M- 1 ROSEMOUNT, IHC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL A INSTRU TE -0122HB M- 1 ROSEMOUNT, INC. 104VCX COHT PRI. SYS. TEMP. PROTECTIVE CHANNEL B INSTRU TE -0122HC M- 1 ROSEMOUNT, INC. 104VCX CONT PRI. SYS. TEMP. PROTECTIVE CHAHHEL C IHSTRU TE -0122HD M- 1 ROSEMOUNT, INC. 104VCX CPNT PRI. SYS. TEMP. PROTECTIVE CHAHHEL D MOTOR EMB-0177 M-2418 RELIANCE ELECTRIC CO 444567-KT 01/649 PRESS. RELIEF ISOL.VLV.M01042A MOTOR EMB-0281 RELIANCE ELECTRIC CO 444567-KT 01/649 PRESS. RELIEF ISOL.VLV.M01043A VALVE SV -1901 M-211 AUTOMATIC SWITCH COM HT8320A22 CONT STEAM GENERATOR BLOUDOWN MONITORING VALVE SV -1902 M-211 AUTOMATIC SWITCH COM HT8320A22 CONT STEAM GENERATOR BLONDOWH MOHITORING VALVE SV -1903 "-211 AUTOMATIC SWITCH COM HT8320A22 CONT STEAM GENERATOR BLOUDOWN MONITORIHG VALVE SV -1904 211 AUTOMATIC SMITCH COM HT8320A22 CONT QUEHCH TAHK LIQUID PHASE VALVE SV -1905 n-211 AUTOMATIC SUITCH COM HT8320A22 CONT STEAM GENERATOR BLONDOMH NOHITORING VALVE SV -0155 M-234-2 AUTOMATIC SWITCH COM WPHT 8300861-RF R150 DEMINERALIZER WATER QUEHCH TANK VALVE VALVE SV -1910 M-211 AUTOMATIC SWITCH COM HT8320A22 R150 PRIMARY SYSTEM SAMPLING ISOLATION

, VALVE SV -1911 M-211 AUTOMATIC SWITCH COM HT8320A22 R150 PRIMARY SYSTEM SAMPLING ISOLATION VALV0P V0P-1042A M-241B PHILADELPHIA GEAR C0 SMB-000 CONT PER POWER RELIEF ISOL VALV0P V0P-1043A M-241B PHILADELPHIA GEAR C0 SMB-000 CONT PER POWER RELIEF ISOL

RPT. 51 PAL kIA INSTRU CLASS IE AND SELECiED R0url5 BY SYSfEM 06/05/31 PAGE 11 TYPE COMP ID REQ HO MANUFACTURER MODEL LOC SERVICE PAL RIA INSTRU RE -1805 M-217 VICTOREEN INSTRUMENT 848-4+E12749 CONT C0h;/IHMENT ISOLATION MONITOR INSTRU RE -1806 M-217 VICTOREEN IIISTRUMENT 848-4+E12749 CONT CON T a I HMEtiT ISOL AT I3H MOP 4ITOR Ills T R U RE -1807 M-217 VICTOREEN I!4STRUMENT 848-4+E12749 CONT COHI AIHi!EHT ISOLATION MONITOR INSTRU RE -1808 M-217 VICTOREEN INSTRUMENT 848-4+E12749 CONT CON T Alti:1ENT ISOLATION MOHFTOR em

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O 0 RPT. 51 PAL ( ,~I INSTRU CLASSIEANDSELECTEDR(a_JBYSYSTEM m 06/05/81 \_,/ PAGE 12-TYPE COMP ID REQ NO MANUFACTURER MODEL LOC SERVICE PA!. RMS INSTRU LT -1107 M-206-114FISCHER & PORTER CO. 1082466EC R123 SAFETY INJ. RM SUMP T-78B INSTRU LS -1105 M- 22BC SQUARE D CO CLASS 9038, TYPE AW-1 03/5?0 ENGINEERED SAFEGRD RD 1102 INSTRU LS -1108 M- 22BC SQUARE D CO CLASS 9038, TYPE AW-1 03/513 ENGINEERED SAFGRD RM SUMP T-78A WEST 1103 MOTOR EMB-0155 M- 22BC GENERAL ELECTRIC CO. SK143DL2348 02/570 INJECTION ROOM SUMP PUMP P-72B MOTOR EMB-0165 M- 22BC GENERAL ELECTRIC CO. SK143DL2348 03/570 INJECTION ROOM SUMP PUMP P-73B MOTOR EMB-0245 M- 22BC GENERAL ELECTRIC CO. SK143DL2348 03/570 INJECTION R0011 SUMP PUMP P-73A MOTOR EMB-0255 M- 22BC GENERAL ELECTRIC CO. SK143DL2348 03/570 INJECTION ROOM SUMP PUMP P-72A VALVE SV -1002 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R118 PRIMARY SYSTEM DRAIN TANK VALVE VALVE SV -1007 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF '

R118 PRIMARY SYSTEM DRAIN TANK VALVE VALVE SV -1036 M-234 AUT0f1ATIC SWITCH COM WPHT-8300B61-RF R118 CLEAN WASTE RECEIVER TANK ISOLATION VALVE SV -1038 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R118 CLEAN WASTE RECEIVER TANK ISOLATION VALVE SV -1044 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R118 CLEAN WASTE RECEIVER TAHK PUMP ISOLATION VALVE SV -1045 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R118 CLEAN WASTE RECEIVER TANK PUMP ISOLATION VALVE SV -1001 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R150 PRI. SYSTEM DRAIN TANK ISOLATION VALVE VALVE SV -1004 M-234 AUTOMATIC SWITCH COM Nf4T-8300B61RF R150 CLEAN WASTE RECEIVER TK. ISOL. VALVE VALVE SV -1037 M-234 AUTOMATIC SWITCH COM WPHT8300B61-RF R150 CLEAN WASTE RECEIVER TK. ISOL. VALVE VALVE SV -1064 M-234 AUTOMATIC SWITCH COM WPHT-8300861RF R150 CLEAH WASTE RECEIVER TAHK VENT VALVE SV -1065 M-234 AUTOMATIC SWITCH COM WPHT-8300B61RF R150 CLEAN WASTE RECEIVER TAMK VEHI VALVE SV -1103 M-234 AUTOMATIC SWITCH COM WPHT-8300861-RF 02/570 CONTAINMENT SUMP DRAIH ISOLATION VALVE VALVE SV -1104 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF 02/570 CONTAIHMENT SUt1P DRAIN ISOLATION VALVE i

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RPT. 51 PAL dCS VALVE CLASS 1E AND SELECTED R0udS BY SYSTEM 06/05/81 PAGE 13 TYPE COMP ID REO HD MAHUFACTURER MODEL LOC SERVICE PAL SCS VALVE SV -0939 M-234 AUTOMATIC SWITCH COM WPHT-8300B61RF R123 SHIELD COOLING SURGE TANK VALVE 9 O 9

3 RPT. 51 PAL f a VALVE CLASS 1E AND SELECTED R y BY SYSTEM 06/05/81 Q PAGE 14 TYPE COMP ID REQ HO MANUFACTURER MODEL LOC SERVICE PAL SWS VALVE SV -0861 M-240 AUTOMATIC SWITCH COM HP-831654E CONT CONTAIHMENT AIR COOLER VHX-1 0808 VALVE SV -0862 M-240 AUTOMATIC SWITCH COM HP-831654E CONT CONTAINMENT AIR COOLER VHX-1 0806 VALVE SV -0864 M-240 AUTOMATIC SWITCH COM HP-831654E CONT CONT A.C. VHX2 SERV WIR OH-OFF CONTRO 0809 VALVE SV -0865 M-240 AUTOMATIC SWITCH COM HP-831654E COHT COHT A.C. VHX2 SERV WTR OH-OFF CONTRO 0809.

VALVE SV -0867 M-240 AUTOMATIC SWITCH COM HP-831654E CONT SERVICE WATER DISCHARGE-RECIRC. FAN V-4A VALVE SV -0869 M-240 AUTOMATIC SWITCH COM HP-831654E COHT SERVICE WATER IHLET-RECIRC. FAN V-4A VALVE SV -0870 M-240 AUTOMATIC SWITCH COM HP-831654E CONT CONT A.C. VHX3 SER WTR OH-OFF CONTROL 0810 VALVE SV -0873 M-240 AUTOMATIC SWITCH COM HP-831654E CONT CONT A.C. VHX3 SER WTR OH-OFF CONTROL 0811 VALVE SV -0823A MAGNETROL, INC. 18AR43A R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -08238 MAGHETROL, INC. 18A43A R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0825 M-234 AUTOMATIC SWITCH COM WPHT-8300B61-RF R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0826A MAGNETROL, INC. ' JAR 43A R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0826B MAGNETROL, INC. 18T43A R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0844 M-240 AUTOMATIC SWITCH COM LM831614 R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0845 M-240 AUTOMATIC SWITCH CON LB831614 R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0846 M-240 AUTOMATIC SWITCH COM FT8316C-14 R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0857 M-240 AUTOMATIC SWITCH COM LB831614 R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0876 M-240 AUTOMATIC SWITCH COM LB-831614 R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0877 M-240 AUT0t1ATIC SWITCH COM LB-831614 R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0878 M-234 AUTOMATIC SWITCH COM WPilT8300861-RF R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0879 M-234 AUTOMATIC SWITCH COM WHPT-8300B61-RF R123 SERVICE WATER VALVES CIRCUIT 2 VALVE SV -0880 M-234 AUTOMATIC SWITCH COM WHPT-8300B61-RF R123 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0824 M-240 AUTOMATIC SWITCH COM LB831614 R238 SERVICE WATER VALVES CIRCUIT 1 VALVE SV -0847 M-240 AUTOMATIC SWITCH C0ft LBS31614 R238 SERVICE WATER VALVES CIRCUIT 1 a

RPT, 51 PAL DAS INSTRU CLASS lE AND SELECTED R0udS BY SYSTEM 06/05/81 PAGE 15 TYPE COMP ID' REQ HO MANUFACTURER MODEL LOC SERVICE PAL VAS INSTRU PS -1801 M-274-23 UNITED ELECTRIC CONT J302(553) Rll8 CONT.HP8HR SIRW TK. LOW LEV.DET. CHANNEL N01 INSTRU PS -1801A FIELD UNITED ELECTRIC CONT J302(553) R118 CONT.ISOL.H.P. OR H.R.

INSTRU PS -1803 M-274-24 UNITED ELECTRIC CONT J302(553) R118 CONT.HPSHR SIRW TK. LOW LEV.DET. CHANNEL NO3 INSTRU PS -1803A FIELD UNITED ELECTRIC CONT J302(553) R118 CONT.ISOL.H.P. OR H.R.

IHSTRU PT -1805 M-206-52 FISCHER 1 PORTER CD. 50EP1071ACXAHS R118 CONTAIHMENT BLDG PRESS.

INSTRU PT -1814 M-206-54 FISCHER 3 PORTER CO. 50EP1071ACXAHS R118 CONTAIHMENT BLDG INSTRU PS -1802 M-274-23 UNITED ELECTRIC CONT J302(553) R123 CONT.HP1HR SIRW TK. LOW LEV.DET.CHAHHEL H02 INSTRU PS -1802A FIELD UNITED ELECTRIC COHT J302(553) R123 CONT.ISOL.H.P. OR H.R.

IH3TRU PS -1804 M-274-24 UNITED ELECTRIC CONT J302(553) R123 CONT.HP&HR SIRW TK. LOW LEV.DET. CHANNEL N04 INSTRU PS -1804A FIELD UNITED ELECTRIC CONT J302(553) R123 CONTAINMENT PRESSURE 1801 INSTRU PT -1812 M-206-53 FISCHER & PORTER CD. 50EP1071ACXAHS R123 CONTAIHMENT BLDG PRESS.

INSTRU PT -1815 M-206-55 FISCHER 3 PORTER CD. 50EP1071ACXANS R123 CONTAIHMENT BLDG INSTRU TS -1856 M- 55 JOHHSON CONTROLS IHC T-7170 02/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27C INSTRU TS -1857 M- 55 JOHHSON CONTROLS INC T-7170 02/570 EHGINEERED SAFEGUARDS ROOM COOLER V-27C INSTRU TS -1858 M- 55 JOHHSON CONTROLS IHC T-7170 02/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27D INSTRU TS -1859 M- 55 JOHHSON CONTROLS INC T-7170 02/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27D INSTRU 15 -1849 M- 55 JOHHSON CONTROLS INC T-7170 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27A INSTRU TS -1850 M- 55 JOHHSON CONTROLS INC T-7170 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27A INSTRU 15 -1851 M- 55 JOHHSON CONTROLS INC T-7170 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27B INSTRU TS -1852 M- 55 JOHHSON CONTROLS IHC T-7170 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27B MOTOR EMB-1208 M- 59 GENERAL ELECTRIC CO. 5K405YK232 01/590 CONTAIHMENT COOLER RECIRC. FAN V-1A MOTOR EMB-1209 M- 59 GENERAL ELECTRIC CO. SK405YK232 01/590 CONTAINMENT COOLER RECIRC. FAH V-2A MOTOR EMB-1210 M- 59 GEHERAL ELECTRIC CO. SK405YK232 01/590 CONTAINMENT COOLER RECIRC. FAH V-3A MOTOR EMB-0131 M- 59 GENERAL ELECTRIC CO. 5 K 256 YK 161 02/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27A MOTOR EMB-0211 M- 5 9 GENERAL ELECTRIC CO. SK256YK161 02/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27B MOTOR EMB-0133 M- 59 GFHERAL ELECTRIC CO. 5 K 256 YK 161 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27C MOTOR EMB-0221 M- 59 GtNERAL ELECTRIC CO. 5 K 256 YK 161 03/570 ENGINEERED SAFEGUARDS ROOM COOLER V-27D VALVE SV -1501 M-234 AUTOMATIC SWITCH COM WP-HT8300B61RF R150 CONTAIHMENT BLDG. STEAM DISCHARGE VALVE SV -1502 M-234 AUTOMATIC SWITCH COM WP-HT8300B61RF R150 CONTAINMENT BLDG. STEAM DISCHARGE VALVE SV -1503 M-234 AUTOMATIC SWITCH COM WP-HT8300B61RF R150 CONTAIHMENT STEAM HEAT ISOLATION VALVE VALVE SV -1813 M-239 AU'0MATIC SWITCH CON LB831624 R150 CONTA8 AIR RM. PURGE ISOL. VALVE CIRCUIT NC.2 VALVE SV -1814 M-239 AUTOMATIC SWITCH COM LB831624 R150 CONTAZAIR RM. PURGE ISOL. VALVE CIRCUIT N0.1 O G G

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RPT. 51 PAL RECOMB CLASS IE AND SELECTED R BY SYSTEM 06/05/81 . PAGE 16 TYPE COMP ID REQ HO MANUFACTURER MODEL LOC SERVICE PAL WGS, RECOMB M - 69A M-296 WESTINGHOUSE ELECTRI 546-CXR-190931-BH 01/659 HYDROGEN RECOMBINER RECOMB M - 698 M-296 WESTINGHOUSE ELECTRI 546-CXR-190931-3H 01/659 HYDROGEH RECOMBINER VALVE SV -1101 M-234 AUTOMATIC SWITCH COM WPHT-8300B61RF R150 CONTAIHMENT WASTE GAS IHLET VALVE SV -1102 M-234 AUTOMATIC SWITCH COM WPHT-8300B61RF R150 CONTAINMENT WASTE GAS IHLET a

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RPT. 54 PAL aHSTRU CLASS 1E AND SELECTED R0ud5 BY TYPE 06/05/81 PAGE )

TYPE COMP ID Q(AE/B/POCSX) PID REQ H0 MANUFACTURER LOC MODEL SERIAL PAL INSTRU E/P-0338 Q -1/Q/-H-H- M-203 D-4 M-233-88 FISHER CONTROLS CO. CONT 546 INSTRU E/P-0342 Q -1/Q/-N-H- M-203 D-7 M-233-87 FISHER CONTROLS CO. CONT 546 IHSTRU E/P-0346 4 -1/Q/-N-N- M-203 D-6 M-233-87 FISHER CONTROLS CO. CONT 546 INSTRU E/P-0347 Q -1/Q/-N-H- M-203 D-5 M-233-88 FISHER CONTROLS CO. CONT 546 IhdTRU E/P-0735 Q -1/Q/-Q-Q- M-207 STMGEHE50B M-233-96 HONEYWELL CORPORATIO 03/570 685435 INSTRU E/P-0717 Q -1/0/-Q-Q- M-207 STMGENE50B M-233-97 HONEYWELL CORPORATIO 03/570 685435 INSTRU E/P-1057 Q -1/Q/-H-H- it-201 E-4 FISHER CONTROLS CO. CONT 546 INSTRU E/P-1059 Q -1/Q/-N-H- M-201 E-5 FISHER C0HIROLS CO. CONT 546 INSTRU E/P-3025 Q -1/Q/-Q- - M-204 D-7 M-233-103MA50HEILAH INTERHATI 03/570 8012 INSTRU FT -0701 Q -1/Q/-H-N- M-207 STMGENE50B M- 1 FISCHER 3 PORTER CD. CONT 10B2466AAABI IMSTRU FT -0702 0 -1/0/-N-N- M-207 STNGENE50A FISCHER 3 PORTER CO. CONT 10B2466AAABI IHSTRU FT -0703 Q -1/Q/-N-N- M-207 HEATER E6A M- 1 FISCHER 1 PORTER Co. CONT 1032466AAABI INSTRU FT -0704 Q -1/Q/-N-N- M-207 STMGENE50B M- 1 FISCHER 3 PORTER CO. CONT 10B2466AAAB1 INSTRU LS -1105 Q -1/Q/-N-N- M-211 SUMP-PUMPS M- 22BC SQUARE D CO 03/570 CLASS 9038, TYPE AW-1 INSTRU LS -1108 Q -1/Q/-N-H- M-211 SUMP-PUMPS M- 22BC SQUARE D CD 03/570 CLASS 9038, TYPE AW-1 INSTRU LT -0103 Q -1/Q/-Q- - M-201 F-3 M- 1 FOXBORO CO., THE COHT 613HM INSTRU LT -0358 Q -1/Q/-N-H- M-204 C-2 M-206-97 FISCHER 1 PORTER CO. CONT 10B2495JB INSTRO LT -0359 Q -1/Q/-N-H- M-204 C-2 M-206-98 FISCHER 1 PORTER CO. CONT 10B24655ECBB1 INSTRU LT -0701 Q -1/Q/-N-N- M-207 STilGEHE50B M- 1 FISCHER 3 PORTER CO. CONT 13D2465BA INSTRU LT -0702 Q -1/Q/-N-H- M-207 SIMGENE50B M- 1 FISCHER & PORTER CO. CONT 13D2465BA INSTRU LT -0703 Q -1/Q/-H-H- M-207 STMGEHE50B M- 1 FISCHER 3 PORTER CO. CONT 13D2465BA INSTRU LT -0704 Q -1/Q/-N-H- M-207 STNGEHE50B M- 1 FISCHER 8 PORTER CO, CONT 13D2465BA INSTRU LT -0751A Q -1/Q/-Q- - M-207 STMGEHE50B M- 1 FOXBORO CO., THE CONT 613DM INSTRU LT -0751B Q -1/Q/ - M-207 STl1GEHE50B M- 1 FOXBORO CO., THE CONT 613DM INS 1RU LT -0751C Q -1/Q/-Q- - M-207 STMGEHE50B M- 1 FOXBORD CO., THE CONT 613DM INSTRU LT -0751D Q -1/0/-Q- - M-207 STMGENE50B M- 1 FOXBORO CO., THE CONT 613DM INSTRU LT -0752A Q -1/Q/ - M-207 F-6 M- 1 FOXBORD CO., THE C0HT 613Ctl INSTRU LT -0752B Q -1/Q/-Q- - M-207 STMGENE50B M- 1 FOXBORO CO., THE CONT 613DM INSTRU LT -0752C Q -1/Q/-Q- - M-207 STMGENE50B M- 1 FOXBORD CO., THE CONT 6130M INSTRU LT -0752D Q -1/0/-Q- - M-207 STMGENE50B M- 1 FOXBORD CO., THE CONT 613DM INSTRU LT -1107 Q -1/Q/-N-H- M-211 SUMP-PUMPS M-206-114FISCHER 4 PORTER CD. R123 10B2466EC 6807A1090A70 INSTRU HI - 5 Q -1/Q/-Q- - - M- IRA GULF GENERAL ATOMIC, CONT HP-6 INSTRU HI - 6 Q -1/Q/-Q- - - M- 1RA GULF GENERAL ATOMIC, CONT HP-6 INSTRU HI - 7 Q -1/Q/-Q- - - M- IRA GULF GENERAL ATOMIC, C0HT NP-6 INSTRU HI - 8 Q -1/Q/-Q- - - M- 1RA GULF GENERAL ATOMIC, CONT NP-6 INSTRU HI - >9 Q -1/Q/-N-N- - GULF GENERAL ATOMIC, CONT INSTRU HI - 10 Q -1/Q/-N-N- - GULF GEHERAL AT0f1IC, CONT INSTRU PS -1801 Q -1/Q/-Q- - U-218CHTACIRUFAH M-274-23 UNITED ELZCTRIC CONT Rll8 J302(553)

INSTRU PS -1801A Q -1/Q/-Q- - M-218CHTACIRUFAN FIELD UNITED ELECTRIC COHT R118 J302(553)

INSTRU PS -1802 Q -1/Q/-Q- - M-218CNTACIRUFAH M-274-23 UNITED ELECTRIC COHT R123 J302(553)

INSIRU PS -1802A Q -1/Q/-Q- - M-218CHTACIRUFAH FIELD UNITED ELECTRIC CONT R123 J302(553)

INSTRU PS -1803 Q -1/Q/-Q- - M-218CHIACIRUFAH M-274-24 UNITED ELECTRIC CONT R118 J302(553)

~~INSTRU PS -1803A Q -1/Q/-Q- - M-218CNTACIRUFAH FIELD UNITED ELECTRIC CONT R118 J302(553)

INSTRU PS -1804 Q -1/Q/-Q- - M-218CONTACIRFAH M-274-24 UNITED ELECTRIC COHT R123 J302(553)

INSTRU PS -1804A Q -1/Q/ - M-218CHTACIRUFAN FIELD UNITED ELECTRIC COHT R123 J302(553)

INSTRU PT -0102A Q -1/ Q e-Q- 2 01 F-4 M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0102B Q -1/Q/-Q- - M-201 F-4 M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0102C Q -1/Q/-Q- - M-201 F-3 M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0102D Q -1/Q/-Q- - M-201 F-3 M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0103 Q -1/0/ - M-201 F-3 (1- 1 FOXBORO CO., THE CONT 611GH

~2INSTRU PT -0306 Q -1/Q/-N-H- M-204 D-6 01-206-8 FISCHER & PORTER CO. R123 50EP1072A INSTRU PT -0338 Q -1/Q/-H-H- M-203 D-4 4-206-4 FISCHER & PORTER CO. CONT 50EP1042A INSTRU PT -0342 Q -1/0/-N-H- N-203 D-7 M-206-1 FISCHER 3 PORTER CO. CONT 50EP1041ACXANS INSTRU PT -0346 Q -1/Q/-H-N- M-203 D-6 M-206-2 FISCHER & PORTER CO. CONT 50EP1042A I

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t RPT. 54 PAL (_ jSTRU CLASS 1E AHD SELECTED R 3 BY TYPE 06/05/81 s_/ PAGE 2' TYPE COMP ID QCAE/B/POCSX) PID REQ HO MANUFACTURER LOC MODEL SERIAL PAL INSTRU PT -0347 Q -1/Q/-N-H- M-233 D-5 M-206-3 FISCHER 8 PORTER CO. CONT SOEP1042A INSTRU PT -0702 Q -1/Q/-N-N- M-207 STMGENE50A M- 1 FISCHER A PORTER CO. CONT 50EP1031B IHSTRU PT -0704 Q -1/Q/-H-N- M-207 STMGEHE50B M- 1 FISCHER 8 PORTER CO. CONT 50EP10318 INSTRU PT -0751A Q -1/Q/-Q- - M-207 STMGENE50B M- 1 FOXBORO CO., THE CONT 611GM IHSTRU PT -0751B Q -1/Q/-Q- - M-207 S1MGENE50B M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0751C Q -1/Q/-Q- - M-207 STMGENE508 (1- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0751D Q -1/Q/-Q- - M-207 STMGENE50B M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0752A Q -1/Q/-Q- - M-207 STMGENE508 M- 1 FOXBORO CO., THE CONT 611GM INSTRU PT -0752B Q -1/Q/-Q- - M-207 STMGENE50B M- 1 FOXBORO CO., THE CONT 611GM IHSTRU ST -0752C Q -1/Q/ - M-207 STMGEHE50B M- 1 FOXBORO CO., THE CONT 611GM IHSTRU PT -0752D Q -1/0/-Q- - M-207 STMGEHE50B M- 1 FOXBORO CO., THE CONT 611G11 INSirs PT -1805 Q -1/Q/-N-H- M-218CHTACIRUFAH M-206-52 FISCHER A PORTER CD. R118 50EP1071ACXAHS IHSTRU PT -1812 Q -1/Q/-H-H- M-218CHTACTRUFAH M-206-53 FISCHER & PORTER CO. R123 50EP1071ACXANS INSTRU PT -1814 Q -1/Q/-N-N- M-218CNTAC SUFAH M-206-54 FISCHER 8 PORTER CO. R118 50EP1071ACXANS INSTRU PT -1815 Q -1/Q/-N-H- M-218CHTAC.dUFAH M-206-55 FISCHER & PORTER CO. R123 50EP1071ACXANS INSTRU RE -1805 Q -1/Q/ - M-218H1,M-223D2 M-217 VICTOREEN INSTRUMENT CONT 848-4+E12749 155 INSTCU RE -1806 Q -1/Q/-Q- - M-218H1.M-223D2 M-217 VICTOREEN INSTRUMENT CONT 848-4+E12749 510 INSTRU RE -1807 Q -1/Q/-Q- - M-218H1,M-223C2 M-217 VICTOREEH IHSTRUMEHT CONT 848-4+E12749 INSTRU RE -1808 Q -1/Q/-Q- - M-218H2.M-223C2 M-217 VICT0REEN INSTRUMENT CONT 848-4+E12749 INSTRU TE -0111A Q -1/Q/-Q- - M-201 C-3 M- 1 ROSEMOUNT. INC. COHT 104VCX INSTRU TE -0111B Q -1/Q/-Q- - M-201 D-3 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -OlllH Q -1/0/-N-N- M-201 C-3 M- 1 ROSEMOUNT, IHC. CONT 104VCX INSTRU TE -0112CA Q -1/Q/-Q- - M-201 D-2 M- 1 ROSEMOUNT, INC. CONT 104VCX IHSTRU TE -Oll2CB Q -1/Q/-Q- - M-201 B-2 M- 1 ROSEMOUNT, IHC. CONT 104VCX INSTRU TE -0112CC Q -1/Q/-Q- - M-201 B-3 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0112CD Q -1/Q/-Q- - M-201 B-3 M- 1 ROSEMOUNT, INC. COHT 104VCX INSTRU TE -0112HA Q -1/Q/-Q- - M-201 C-2 M- 1 ROS E110UN T , IHC. CONT 104VCX INSTRU TE -01:2HB Q -1/Q/-Q- - M-201 C-2 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0112HC Q -1/Q/-Q- - M-201 C-3 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0112HD Q -1/Q/-Q- - M-201 C-3 M- 1 ROSEMOUNT, IHC. CONT IG4VCX INSTRH TE -0121A Q -1/Q/-Q- - M-201 B-6 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0121B Q -1/Q/-Q- - M-201 D-6 M- 1 ROS Et10UN T , INC. CONT 104VCX INSTRU TE -0121H Q -1/Q/-N-H- M-201 C-5 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0122CA Q -1/Q/-Q- - M-201 B-7 !1- 1 ROSEMOUNT, INC. COHT 104VCX INSTRU TE -0122CB Q -1/Q/ - M-201 D-7 M- 1 ROSEMOUNT, IHC. CONT 104VCX INSTRU TE -0122CC Q -1/Q/-Q- - M-201 A-6 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0122CD Q -1/Q/ - M-201 D-6 M- 1 ROSEHOUNT, IhC. CONT 104VCX INSTRU TE -0122HA Q -1/Q/-Q- - M-201 C-7 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0122HB Q -1/Q/-Q- - M-201 C-7 M- 1 ROSEMOUNT, INC. CONT 104VCX INSTRU TE -0122HC Q -1/0/-Q- - M-201 C-6 M- 1 ROS Ef10 UH T , IHC. CONT 104VCX INSTRU TE -0122HD Q -1/Q/-Q- - M-201 C-6 M- 1 ROSEMOUNT, INC. CONT 104VCX "INSTRU TS -1849 Q -1/9/-N-H- M-218 A-6 M- 55 JOHHSON CONTROLS INC 03/570 T-7170 IHSTRU TS -1850 Q -1/Q/-H-H- M-218 A-6 M- 55 JOHHSON CONTROLS INC 03/570 T-7170 IHSTRU TS -1851 Q -1/0/-N-N- M-218 A-6 M- 55 JOHHSON CONTROLS INC 03/570 T-7170 INSTRU TS -1852 Q -1/Q/-N-N- M-218 A-6 M- 55 JOHHSON CONTROLS IHC 03/570 T-7170 IHSTRU TS -1856 Q -1/Q/-H-H- M-218 A-6 M- 55 JOHHSON CONTROLS IHC 02/570 T-7170 INSTRU TS -1857 Q -1/Q/-H-H- Il-218 A-6 M- 55 JOHH50N CONTROLS IHC 02/570 T-7170 INSTRU TS -1858 Q -1/0/-N-H- M-218 A-6 M- 55 JOHHSOH CONTROLS IHC 02/570 T-7170 INSTRU TS -1859 Q -1/Q/-N-H- M-218 A-6 M- 55 JOHHSON CONTROLS INC 02/570 T-7170 SMOTOR EMA-IID9 Q -1/Q/-Q- - E- 3 F-6 M- 34 LOUIS ALLIS CD 03/590 COGX 8289252003 MOTOR EMA-llll Q -1/Q/-Q- - E- 3 F-5 M- 1 GEHERAL ELECTRIC CD. 03/570 SK818847A100 FD8367477 MOTOR EMA-lll2 Q -1/Q/-Q- - E- 3 F-5 N- 8 LOUIS ALLIS CD 03/570 COGS 8289086003 MOTOR EMA-lll3 Q -1/Q/-Q- - E- 3 F-4 M- 1 WESTINGHOUSE ELECTRI 03/570 68F13512 35-68 4

RPT. 54 PAL r.0 T O R CLASS lE AND SELECTED R0udS BY TYPE 06/05/81 PAGE {

TYPE COMP ID Q(AE/B/POCSX) PID REQ NO MANUFACTURER LOC MODEL SERIAL PAL MOTOR EMA-lll4 Q -1/Q/-Q- - E- 3 F-4 M- 8 LOUIS ALLIS CD 03/570 COGS 8289086001 MOTOR EMA-1116 0 -1/0/ - 8289252 M- 34 LOUIS ALLIS CD 03/590 COGX 8239252001 MOTOR EMA-1206 0 -1/Q/-Q- - E- 3 D-7 M- 1 GENERAL ELECTRIC CO. 02/570 5K818847A100 FD8367478 MOTOR EMA-1207 Q -1/Q/ - E- 3D6 M- 1 WESTINGHOUSE ELECTRI 02/570 68F13512 15-68 MOTOR EMA-1208 Q -1/Q/-Q- - E- 3 D-6 M- 34 LOUIS ALLIS CO 03/590 COGX 8289252002 MOTOR EMA-1209 Q -l/Q/-Q- - E- 3 D-5 M- 1 WESTINGHOUSE ELECTRI 03/570 68F13512 25-68 MOTOR EMA-1210 0 -1/Q/-Q- - E- 3 D-5 M- 8 LOUIS ALLIS CD 02/570 COGS 8289086002 MOTOR EMB-0131 Q -1/0/-Q- - E- 5-1 H-5 M- 5 9 GENERAL ELECTRIC CD. 02/570 5 K 256 YK 161 6032003 MOTOR EM3-0133 Q -1/Q/-Q- - E- 5-1 H-5 M- 59 GEHERAL ELECTRIC CD. 03/570 5 K 256 YK 161 6032006 MOTOR EMB-0137 Q -1/Q/-Q- - E- 5 H-4 RELIAHCE ELECTRIC CO 01/590 447063 LT MOTOR EMB-0141 Q -1/4/ - E- 5 H-4 RELIANCE ELECTRIC CO 01/590 Y220107A4 BU MOTOR EMB-0147 Q -1/Q/-Q- - E- 5 H-3 RELIAHCE ELECTRIC CD 01/590 Y220107A4 BU MOTOR EMB-0151 Q -1/Q/-Q- - E- 5 H-3 RELIANCE ELECTRIC CD 01/590 447063 LT MOTOR EMB-0155 Q -1/Q/-Q- - E- 5 F-8 M- 22BC GENERAL ELECTRIC CO. 02/570 5K143DL2348 MOTOR EMB-0157 Q -1/Q/-Q- - E- 5 F-8 RELIANCE ELECTRIC C0 01/590 447063 LT MOTOR EMB-0165 Q -1/Q/-Q- - E- 5 F-7 M- 22BC GtHERAL ELECTRIC CO. 03/570 SK143DL2348 HHJ830445 MOTOR EMB-0167 Q -1/Q/ - E- 5 F-7 RELIANCE ELECTRIC CD 01/607 447061LT MOTOR EMB-0177 Q -1/Q/ .'- - E- 5 F-5 M-241B RELIANCE ELECTRIC CD 01/649 444567-KT MOIOR Et1B-019 7 Q -1/0/ - E- ~5 F-3 RELIANCE ELECTRIC CO 01/590 447063 L1 MOTOR EMB-0211 Q -1/Q/-Q- - E- 5-1 D-8 M- 59 GENERAL ELECTRIC CO. 02/570 SK256YK161 6032004 MOTOR EMB-0221 Q -1/Q/ - E- 5-1 D-7 M- 59 GENERAL ELECTRIC CO. 03/570 5 K 256 YK 161 6032005 MOTOR EMB-0237 Q -1/Q/-Q- - E- 5-1 D-4 RELI ANCE EL ECTRIC CO 01/590 447063 LT MOTOR EMB-0241 0 -1/Q/-Q- - E- 5-1 D-4 RELIANCE ELECTRIC CD 01/590 447063 LT MOTOR EMB-0245 0 -1/0/-Q- - E- 5-1 D-4 M- 22BC GENERAL ELECTRIC CO. 03/570- SK143DL2348 MOTOR EMB-0247 Q -1/Q/ - E- 5-1 D .1 RELIANCE ELECTRIC CD 01/593 Y274033A6PA MOTOR EMB-0251 Q -1/0/-Q- - E- 5-1 D-3 RELIANCE ELECTRIC CD 01/590 Y220107A2 NOTOR EMB-0255 Q -1/Q/-Q- - E- 5-1 D-2 M- 22BC GENERAL ELECTRIC CO. 03/570 5K143DL2348 MOTOR EMB-0257 Q -1/Q/-Q- - - RELIANCE ELECTRIC CO 01/590 447063 LT MOTOR EMB-0261 Q -1/Q/-Q- - E- 5-1 D-2 RELIANCE ELECTRIC CD 01/590 447063 LT MOTOR EMB-0271 0 -1/0/ - E- 5-1 B-7 RELIANCE ELECTRIC CO 01/507 704799 FX MOTOR EMB-0281 Q -1/Q/-Q- - E- 5-1 B-6 RELIANCE ELECTRIO CD 01/649 444567-KT MOTOR EMB-1208 Q -1/0/ - E- 4 E-5 M- 59 GENERAL F.LECTRIC CO. 01/590 SK405YK232 LE 453034 MOTOR EMB-1209 Q -1/Q/-Q- - E- 4 E-5 M- 59 GENERAL ELECTRIC CO. 01/590 5K405YK232 LE 453035 MOTOR EMB-1210 Q -1/Q/-Q- - E- 4 E-5 M- 59 GENERAL ELECTRIC CO. 01/590 SK405YK232 LE453036 PEHETR EZ -0101 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES P1 23-0048-0000 -

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PEHEIR EZ -0104 Q 1/ /Q--Q- E- 20 VIKIHG INDUSTRIES P1 23-0051-0000 -

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PEHETR EZ -0109 Q 1/ /Q--Q- E- 20 VIKING IHDUSTRIES P3 23-0023-0000 -

PEHETR EZ -0110 // -

E- 20 VIKING INDUSTRIES P4 23-0024-0000 -

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PEHETR EZ -0210 Q 1/ /Q--Q- E- 4 E-5 E- 20 VIKlHG INDUSTRIES P4 23-0025-0000 -

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RPT. 54 PAL (_,hETR CLASS IE AND SELECTED R s, )SYTTPE 06/05/31 PAGE 4 TYPE COMP ID Q(AE/B/POCSX) PID REQ HO MANUFACTURER LOC MODEL SERIAL PAL PEHETR EZ -0221 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES C-1B 23-0030-0000 -

PEHETR EZ -0222 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES C-1B 23-0031-0000 -

PEHETR EZ -0223 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES C-2 23-0032-0000 -

PEHETR EZ -0224 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES C-2 23-0033-0000 -

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PEHETR EZ -0243 Q 1/ /Q--Q- E- 20 VIKI.4G INDUSTRIES I-1B 23-0039-0000 -

PEHETR EZ -0244 Q 1/ /Q--Q- '

E- 20 VIKING INDUSTRIES I-2 23-0040-0000 -

PEHETR EZ -0245 Q 1/ /Q--Q- E- 20 VIKING INDUSTRIES I-2 23-0041-0000 -

PEHETR EZ -0246 Q 1/ /Q--Q- I -3B 23-0047-0000 -

RECOMB M - 69A Q 1/Q/ - - M-224D3,M-218H5 N-296 WESTINGHOUSE ELECTRI 01/659 54 u -CXR-19 0 9 31-BN 12 RECOMB M - 69B Q 1/Q/ - - M-224D2,M-218H5 M-296 UESTINGHOUSE ELECTRI 01/659 54 6- CXR-190 9 31-LH 13 VALVE SV -0155 Q 1/Q/ - M-201 H-7 M-234-2 AUTOMATIC SWITCH COM R150 WPHT 8300B61-RF 81170R2 VALVE SV -0338 Q -1/Q/ - M-203 D-4 M-234-ll AUTOMATIC SWITCH COM CONT WPHT 8300B61RF 81170R2 VALVE SV -0342 Q -1/Q/ - M-203 D-7 M-234-11 AUTOMATIC SWITCH COM CONT WPHT 8300B61-RF 81170R2 VALVE SV -0346 Q -1/0/ - M-203 D-6 M-234-ll A"TCM*T?C SWITCH COM CONT WPHT-8300B61RF 81170R2 VALVE SV -0347 Q -1/Q/ - M-203 D-5 M-234-ll AUTOMATIC ~" ITCH COM CONT WPHT 8300B61-RF 81170R2 VALVE SV -0438A Q 1/Q/ - M-204 F-1 M-336 AUTOMATIC SWITCH COM R238 HTX8320A22X 83104E1 VALVE SV -0438B Q 1/Q/ - M-204 F-1 M-336 AUTOMATIC SWITCH COM R238 HTY 8320A-22V 83104E2 VALVE SV -0522A Q -1/Q/-QHQ- M-205 F-8 M-234 R238 HPX0320A26 30506B VALVE SV -0738 Q 1/Q/ - M-226 FLASH T-29 M-234 AUTOMATIC SWITCH COM R238 WPHT8300B61-RF 81170R2 VALVE SV -0739 Q 1/0/ - M-226 FLASH T-29 M-234 AUTOMATIC SWITCH COM R238 WPHT8300B61-RF 81170R2 VALVE SV -0767 Q 1/Q/ - M-226 FLASH T-29 M-234 AUTOMATIC SUITCH COM R238 WPHT-8300D61-RF 21514T VALVE SV -0768 Q 1/0/ - M-226 FLASH T-29 M-234 AUTOMATIC SUITCH COM R238 WPHT-8300B61-RF 21514T VALVE SV -0770 Q 1/0/ - M-226 FLASH T-29 M-234 AUTOMATIC SUITCH COM R238 WPHT-8300B61-RF 81170R2 VALVE SV -0771 Q 1/Q/ - M-226 FLASH T-29 M-234 AUTOMATIC SWITCH COM R238 WPHT-8300B61-RF 81170R2 VALVE SV -0823A Q 1/0/ - M-208 D-4 MAGNETROL, INC. R123 18AR43A VALVE SV -0823B Q 1/Q/ - M-208 D-4 MAGHETROL, INC. R123 18A43A VALVE SV -0824 Q 1/0/ - M-208 B-5 M-240 AUTOMATIC SWITCH COM R238 LB831614 VALVE SV -0825 Q 1/Q/ - H-208 C-3 M-234 AUTOMATIC SWITCH COM R123 WPHT-8500861-RF 81170R2 VALVE SV -0826A Q 1/Q/ - M-208 COMCOLHETX MAGNETROL, INC. R123 18AR43A VALVE SV -0826B Q 1/Q/ - M-208 COMCOLHETX MAGHETROL, INC. R123 18A43A VALVE SV -0844 Q 1/Q/HHHH- M-208 E,F-1,2 M-240 AUTOMATIC SWITCH COM R123 LM831614 24662T VALVE SV -0845 Q 1/0/HHHH- M-208 E,F-1,2 M-240 AUTOMATIC SWITCH COM R123 LB8T1614 2482T VALVE SV -0846 Q 1/Q/HHHH- M-208 E F-1,2 M-240 AUTOMATIC SWITCH COM R123 F18316C-14 1200D

~ VALVE SV -0847 Q 1/Q/ - M-208 COMCOLHETX H-240 AUTOMATIC SWITCH COM R238 LC831614 2482T VALVE SV -0857 Q 1/Q/HHHH- M-208 E.F-1,2 M-240 AUTOMATIC SWITCH COM R123 LB831614 2482T VALVE SV -0861 Q 1/Q/ - M-208 CONTAIRCOL M-240 AUTOMATIC SWITCH COM CONT HP-831654E 2482T VALVE SV -0862 Q 1/Q/HHHH- M-208 CONTAIRCOL M-240 AUTOMATIC SWITCH COM CONT HP-831654E 2482T VALVE SV -0864 0 1/0/ - M-208 CONTAIRCOL M-240 AUIONATIC SWITCH COM CONT HP-831654E 2482T VALVE SV -0865 Q 1/Q/HHHH- M-208 CONTAIRCOL M-240 AUTOMATIC SWITCH COM CONT HP-831654E 2482T VALVE SV -0867 0 1/Q/ - M-208 CONTAIRCOL M-240 AUTOMATIC SUITCH COM CONT HP-831654E 2482T VALVE SV -0869 Q 1/Q/HHHH- M-208 CONTAIRCOL M-240 AUTOMATIC SUITCH COM CONT HP-831654E 2482T CVALVE SV -0870 Q 1/Q/HHHH- M-208 COHTAIRCOL M-240 AUTOMATIC SWITCH COM C0HT HP-831654E 2482T VALVE SV -0873 Q 1/Q/ - M-208 CONTAIRCOL M-240 AUTOMATIC SWITCH COM CONT HP-831654E 2482T VALVE SV -0376 Q 1/Q/HHHH- N-208 E F-1,2 M-240 AUTOMATIC SWITCH COM R123 LB-831614 2482T VALVE SV -0877 Q 1/Q/HHHH- M-208 E,F-1,2 M-240 AUTOMATIC SWITCH COM R123 LB-83161' 2482T

RrT. 54 PAL VALVE CLA35 IE AND SELECTED R0udS BY TYPE 06/05/81 PAGE 5 TYPE COMP ID Q(AE/B/POCSX) PID REQ fl0 MANUFACTURER LOC MODEL SERIAL PAL VALVE SV -0878 Q 1/Q/ - M-208 B,C-1.2 M-234 AUTOMATIC SWITCil COM R123 WPHT8300B61-RF 81170R2 VALVE SV -0879 Q 1/Q/HHHH- M-208 COMCOLHETX M-234 AUTOMATIC SWITCH COM R123 WHPT-8300B61-RF 81170R2 VALVE SV -0880 Q 1/0/ - M-208 COMCOLilETX M-234 AUTOMATIC SUITCH COM R123 MHPT-8300B61-RF 81170R2 VALVE SV -0910 Q 1/Q/ - M-209 F-3-5 P -24 0 AUT0f1ATIC SUITCH COM R123 LB-831614 2482T VALVE SV -0911 Q 1/Q/ - H-209 B.C-5 M-240 AUT0f1ATIC SWITCH COM R123 LB-831614 2482T VALVE SV -0913 Q 1/Q/ - M-209 PMPCOOLSYS M-234 AUT0f1ATIC SWITCil COM R123 WPHT-8300B61-RF 81170R2 VALVE SV -0937 Q 1/Q/ - M-209 G-H-3.4 M-240 AUTOMATIC SWITCH COM R123 LB-831614 2482T VALVE SV -0938 0 1/Q/ - M-209 G.H-3,4 M-240 AUT0f1ATIC SWITCH COM R123 LB-831614 2482T VALVE SV -0939 Q H1/0/HHHH- M 421FUELP00LSYS M-234 AUT0f1ATIC SWITCH COM R123 WPHT-8300B61RF 81170R2 VALVE SV -0940 Q 1/Q/ - M-209 B.C-5 M-240 (Ul0f1ATIC SWITCH COM R123 LB-831614 2482T VALVE SV -0944A Q 1/Q/ - M-209 CilRPf1PC00L M-354 AUT0f1ATIC SUITCH COM R123 THT-8344-Al 77684A VALVE SV -0945 0 1/Q/ - M-209C0!!PCOLilETX M-24 0 AUT0!!ATIC SWITCH COM R123 L8831614 2482T VALVE SV -0946 Q 1/Q/ - M-209COMPCOLilETX M-240 AUTOMATIC SWITCil C0f1 R123 LS831614 2482T VALVE SV -0947 Q 1/Q/ - M-20 9 PflPC00L SYS M-234 AUT0f1ATIC SWITCH COM 03/570 WPHT-8300B61-RF 81170R2 VALVE SV -0948 0 1/0/ - M-209 PMPC00LSYS f1-234 AUT0f1ATIC SUITCH COM 03/570 WPHT-8300B61-RF 81170R2 VALVE SV -0949 Q 1/Q/HHHH- M-209 PflPC00LSYS M-234 AU10f1ATIC SWITCH COM 03/570 WPHT-8300861-RF 81170R2 VALVE SV -0950 Q 1/Q/ - M-209B.C-5 N-234 AUTOMATIC SWITCH C0!1 03/570 WPitT-8300B61-RF 81170R2 VALVE SV -0951 Q 1/Q/ - M-209 B.C-5 M-234 AUTOMATIC SWITCH COM 03/570 UPitT-8300B61-RF 81170R2 VALVE SV -1031 Q 1/Q/ - M-210 G-7 M-234 AUTOMATIC SWITCH Colt R150 WPilT-8300B61-RF 81170R2 VALVE SV -1002 Q 1/0/ - M-210 F-7 M-234 AUT0!1ATIC SUITCH C0f1 R118 UPitT-8300B61-RF 81170R2 VALVE SV -1004 Q 1/0/ - M-210 H-5 M-234 AUT0f1ATIC SUITCH COM R150 WPHT-8300B61RF 81170R2 VALVE SV -1007 Q 1/Q/ - M-210 F-7 M-234 AUT0f1ATIC SWITCH COM R118 WPHT-8300B61-RF 81170R2 VALUE SV -1036 Q 1/Q/ - M-210 E-1 M-234 AUTOMATIC SWITCH COM Rll8 UPHT-8300861-RF 81170R2 VALVE SV -1037 Q 1/Q/ - M-210 E-1 M-234 AUT0f1ATIC SWITCH C0ft R150 WPHT8300B61-RF 81170R2 VALVE SV -1038 Q 1/0/ - M-210 E-1 M-234 AUTOMATIC SUITCH C0f1 R118 WPHT-8300B61-RF 81170R2 VALVE SV -1044 Q 1/Q/ - M-210 E-2 M-234 AUiOf1ATIC SWITCH C0f1 Ril8 UPHT-8300861-RF 81170R2 VALVE SV -1045 Q 1/Q/ - M-210 E-2 (1-234 AUT0f1ATIC SWITCH C0f1 Rll8 UPHT-8300261-RF Ell 70R2 VALVE SV -1064 Q 1/Q/ - t1-210 G-1 M-234 AUIOTIATIC SWITCH C0ff R150 WPHT-8300B61RF 81170R2 VALVE SV -1065 Q 1/0/ - M-210 G-1 M-234 Aul0flATIC SWITCH COM RISO WPHT-8300B61RF 81170R2 VALVE SV -1101 Q 1/Q/HQH - M-211 TAHK T-67 M-234 AUT0!!ATIC SUITCH C0f1 R150 WPitT-8300B61RF 81170R2 VALVE SV -1102 Q 1/Q/HQH - M-211 TAtlK T-67 M-234 AUTOMATIC SWITCH COM R150 WPitT-8300B61RF 81170R2 VALVE SV -1103 Q 1/Q/ - M-211 E-7 M-234 AUI0flATIC SWITCH COM 02/570 HPHT-8300861-RF 8117nR2 VALVE SV -1104 Q 1/Q/ - M-211 E-7 M-234 AU10f1ATIC SUITCH COM 02/570 WPl! T-8 3 0 0 B 61 -R F all70R2 VALVE SV -1358 Q 1/Q/ - N-222 132 SYSTEM M-234 AU10f1ATIC SWITCil COM R150 HPHT-8300861-RF 215147 VALVE SV -1501 0 1/Q/ - M-215 G.H-1,2 f1-234 AUT0f1ATIC SUITCH CCM R150 UP-HT8300B61RF 81270R2 VALVE SV -1502 Q 1/0/ - M-215 G,ll-1.2 (1-234 AUT0!1ATIC SWITCil C0f1 R150 WP-HT8300B61RF 81170R2 VALVE SV -1503 Q 1/Q/ - M-215 G.ll-1,2 M-234 AUT0flATIC SUITCH C0f1 R150 WP-HT8300B61RF 81170R2 VALVE SV -1813 Q 1/0/ - M-218 PURGE ' 8 PLY f1-239 AUI0llATIC SUITCH C0f1 R150 LB831624 80166R1 VALVE SV

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-1814 Q 1/Q/ - M-218PURGF JPLY M-239 AUTOMATIC SUITCll COM R150 LB831624 80166R1 VALVE -1901 Q 1/Q/HHHH- M-219 H-8 M-211 AU T0i1ATIC SWITCil C0f1 C0!!T llT8320A22 20100T VALVE SV -1902 Q 1/Q/HHHH- M-219 11-1 M-211 AUT0flATIC SWITCil COM CONT HT8320A22 20100T VALVE SV -1903 0 1/0/H!1llH- M-219tiSSS S AtlPLH M-211 AUTOMATIC SWITCil COM CONT llT8320A22 20100T

~ VALVE SV -1904 Q 1/Q/tillHH- M-219 11-7 M-211 AUT0flATIC SUITCll COM CONT HT8320A22 20100T VALVE SV -1905 0 1/Q/titlHH- M-219 11-7 M-21) AUT0f1ATIC SUITCil COM CONT HT8320A22 20100T VALVE SV -1910 Q 1/Q/ - f1-219 F-7 tl-211 AUT0!1ATIC SWITCil C0t1 R150 HT8320A22 20100T VALVE SV -1911 Q 1/0/ - M-219 F-7 M-211 AUTOMATIC SUITCH COM RISO llT8320A22 20100T UALVE SV -2009 Q 1/0/- - M-202 11-6 M-234 AUT0i1ATIC SUITCil Call R150 WPHT8300861-RF 81170R2 VALVE SV -2083 Q 1/Q/ - M-202 G-6 M-234 AUTOMATIC SWITCH C0f1 R150 WPHT8300B61-RF 81170R' VALVE SV -2113 Q 1/Q/HHHH- f1-202 C-7 M-234 AUT0f1ATIC SWITCH COM C0llT WPXilV A2023 012F 521081%

VALVE SV -2115 Q 1/Q/HilHH- M-202 C-7 M- lHC AUTOMATIC SWITCH COM CONT WPXHVA2023012F 52108D3

,

VALVE SV -2117 Q 1/Q/HHHH- M-202 B-7 M- lHC AU10f1ATIC SWITCil C0f1 C0 tit liTX8320A16V 52109D VALVE SV -3001 Q -1/0/ - M-203 11-2 M-234 AUT0!1ATIC SWITCil C0f1 R121B WPilT8300B61-RF 21514T VALVE SV -3002 Q -1/Q/ - M-203 G-2 f1-234 AUT0f1ATIC SWITCH COM R121B WPHT8300B61-RF 21514T VALVE SV -3018 Q 1/0/ - M-225 B-8 M-241 AUTOMATIC SulTCH COM 03/570 LB8316C44 96234T2 O O O

f RPT. 54PALk_/bVE s CLASS lE AND SELECTED RL _/ BY TYPE 06/05/81 \s_/ PAGE 6 TYPE COMP ID Q(AE/B/POCSX) PID REQ HO MANUFACTURER LDC MODEL SERIAL PAL VALVE SV -3027A Q 1/Q/ - M-225 B-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C34 96284T4 VALVE SV -3027B Q 1/Q/ - M-225 B-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C36 96284T3 VALVE SV -3029A Q 1/Q/ - M-225 G-4 M-241 AUTOMATIC SUITCH COM 02/570 LB 8316C-36 96284T3 VALVE SV -30298 Q 1/Q/ - M-225 G-4 M-241 AUTOMATIC SWITCH COM 02/570 LB8316C44 85882A1

' VALVE SV -3030A Q 1/Q/ - M-225 G-6 M-241 AUTOMATIC SWITCH COM 03/570 LB 8316C-36 96284T3 VALVE SV -3030B .Q 1/Q/ - M-225 G-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C44 85882Al VALVE SV -3031A Q 1/Q/ - M-225 H-5 M-241 AUIOMATIC SUITCH COM 03/570 LB8316C36 96284T3 VALVE SV -3031B Q 1/Q/ - M-225 H-5 H-241 AUTOMATIC SWITCH COM 03/570 LB 8316C-46 85882A2 VALVE SV -3036 Q 1/0/ - M-225 F-4 M-241 AUTOMATIC SWITCH COM 02/570 LB8316C34 16284T2 VALVE SV -3037 Q 1/Q/ - M-225 E-4 M-241 AUTOMATIC SWITCH COM 02/570 LB 8316C-34 98284T4 3 VALVE SV -3055A Q 1/Q/ - M-225 F-6 M-241 AUTOMATIC SWITCH COM 03/570 LB 8316C-36 96284T3

, VALVE SV -3055B Q 1/Q/ - M-225 F-6 M-241 AUTOMATIC SWITCH COM 03/570 LB 8316C-34 96284T4 VALVE SV -3056A Q 1/Q/ - M-225 B-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C36 96284T3 VALVE SV -3056B Q 1/Q/ - M-225 E-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C34 96284T4 VALVE SV -3057A Q 1/Q/ - M-225 H-4 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C36 96284T4 VALVE SV -3057B Q 1/Q/ - M-225 H-4 M-241 AUTOMATIC SUITCH COM 03/570 LB8316C46 85582A2 VALVE SV -3059 Q 1/Q/ - M-225 B-8 M-241 AUI0MATIC SWITCH COM 03/570 LB8316C44 96284T2

< VALVE SV -3069 Q -1/Q/ - M-203 D-8 M-234 AUTOMATIC SWITCH COM CONT WPHT 8300B61-RF 81170R2 VALVE SV -3070 Q 1/Q/ - M-225 C-8 M-241 AUTOMATIC SUITCH COM 03/570 LB-8316C-44 96284T-2 VALVE SV -3071 Q 1/0/ - M-225 E-4 M-241 AUTOMATIC SWITCH COM 02/570 LB8316C44 96284T2

, VALVE SV -3212A Q 1/Q/ - M-225 D-6 M-241 AUTOMATIC SUITCH COM 03/570 LB-8316C-36 96284T3 VALVE SV -3212B Q 1/Q/ - M-225 D-6 M-241 AUTOMATIC SWITCH COM 03/570 LB-8316C-34 96284T4 VALVE SV -3213A Q 1/Q/ - M-225 C-6 M-241 AUTOMATIC SUITCH COM 03/570 LB8316C34 96284T4 VALVE SV -3213B Q 1/Q/ - M-225 C-6 N-241 AUTOMATIC SWITCH COM 03/570 LB-8316C-34 96284T1 VALVE SV -3223A Q 1/Q/ - M-225 E-6 M-241 AUTOMATIC SWITCH COM 03/570 LB8316C34 96284T4 VALVE SV -3223B Q 1/Q/ - M-225 E-6 M-241 %UTOMATIC SWITCH COM 03/570 LB8316C34 96284T3 VALVE SV -3224A Q 1/Q/ - M-225 E-6 M-241 "JTOMATIC SWITCH COM 03/570 LB-8316C-36 96284T3 VALVE SV -3224B Q 1/Q/ - M-225 E-6 M-241 AMTOMATIC SWITCH COM 03/570 LB-8316C-34 96284T4 VALV0P V0P-1042A Q 1/Q/HNHH- M-201 G-5 M-241B PHILADELPHIA GEAR CO CONT SMB-000 892G2A VALV0P V0P-1043A Q 1/Q/HHHH- M-201 G-5 M-241B PHILADELPHIA GEAR CO CONT SMB-000 89202A VALV0P V0P-3007 Q 1/Q/ - M-203 F-3 M- 1 LIMITORQUE CORP. CONT SMB-00-15 92381A VALVOP V0P-3008 Q 1/Q/ - M-203 E-2 M- lHA LIMITORQUE CORP. CONT SMB-3-100 95590A VALV0P V0P-3009 Q 1/Q/ - M-203 E-3 M- lHA LIMITORQUE CORP. CONT SMB-00-15 92383A VALV0P V0P-3010 Q 1/0/ - M-203 D-3 M- lHA LIMITORQUE CORP. CONT SMB-3-100 95588A VALV0P V0P-3011 Q 1/Q/ - M-203 C-3 M- 1HA LIMITORQUE CORP. CONT SMB-00-15 VALV0P V0P-3012 Q 1/0/ - M-203 C-3 M- IMA LIMITORQUE CORP. CONT SMB-3-100 VALV0P V0P-3013 Q 1/Q/ - M-203 B-3 M- INA i!MITORQUE CORP. CONT SMB-00-15 92379A VALV0P V0P-3014 Q 1/Q/ - M-203 A-3 M- IHA LIMITORQUE CORP. CONT SMB-3-100 95591A VALV0P V0P-3015 Q 1/Q/ - M-204 E-1 M- IHA LINITORQUE CORP. CONT SMB-2-60 90769A VALV0P V0P-3016 Q 1/Q/ - M-204 D-2 M- 1HA LIMITORQUE CORP. CONT SMB-2-60 90768A a

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ML19350E269

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