Text

To Environ Qualification of Safety-Related Electrical Equipment
	ML18045A852
Person / Time
Site:	Palisades
Issue date:	10/30/1980
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18045A851	List: ML18045A850; ML18045A852;
References
	NUDOCS 8011050503
	Download: ML18045A852 (44)
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Remove (These Are Duplicates of Pages 248c Thru 248i)

TABLE OF CHANGES Remove Original Pages and Replace With

.Attached Revised Pages Add the Following Pages nu1080-0499a-43 Affected Page Appendix I Appendix I Appendix I 248j Thru 248p 3

4 Ba 9a 90 92 93 94 95 328 385 386 387 388 388a 388b 388c 388d 498 527 130a 130b 130c 130d 130e Appendix III 61 62 63

Owner: Consumers Power Company Facility: Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No.:

Docket: 50-255 DOCUMENTATION REFERENCES (cont)

2.

Bendix Engineering Report No 2345 Dated September 2, 1977 - Environmental Testing of Nuclear Cable Sample Assembly L-33627-1

3. Qualification of Bendix Sealing Washer or 0-Rings, Part No 10-101378

4.

Viking Industries Inc Engineering Information and Price Proposal for Electrical Penetrations per Bechtel Specification 5935-E-20

5.

Viking Industries Inc Dwgs for Receptacle Assemblies

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16-0016-0000, 16-0017-0000 and 16-0022-0000

6.

7,

8.

Rockbestos Report "Qualification of Firewall Type SR Class lE Electric Cables" dated March Consumers Power Company Electrical Connector Potting Procedure No SPS-E-2 dated May 23, 1978 Fundamentals of Nuclear Hardening of Electronic Equipment by L W Rickets 9-Letter from C A St Onge, Bechtel Power Corp, to R Marusich, Consumers Power Company, Dated October 3, 1980 Revision:

Date:

NOTES (cont) of N2H4.

Glass Seals and Wires Inside the Canister Are Not SUbject to Chemical Spray

2.

Connector Assembly Inside Containment Along With Potting Compound, Sealing Washer or 0-Ring and Bulkhead Connector Glass Seal Will Be Subject to

~

3.

4.

Radiation as Follows:

Gamma:

2 x 107 Rads Beta:

2 x 108 Rads @ Surface, 2 x 107 Rads @ ~03", 2 x 106 Rads

@.07" Wires Inside the Canister Will Be Subject-to 1 x 107 Rads Gamma Radiation Only Only the Connector Assembly Inside Containment Along With Potting Compound and Sealing Washer or 0-Ring Is Subject to 1003 RH.

Gla*ss Seals and Wires Inside the canister Do Not See any Moisture For Connector Assembly Inside Containment Along With Potting Compound, Sealing Washer or 0-Ri§g and Bulkhead Connector Glass Seal: *1.1 x 10 Rads Gamma.

For Wires Inside the Canister:

1 x 107 Rads Gamma G*0858*02A

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Type P4 PS P6 Penetration Size 12" Diam 60" Long 12" Diam 75" Long 12" Diam 60" Long 12" Diam 60" Long 12" Diam 75" llong Tag Location No Elev ZllO 617'-0" Elev Z210 630'-0" Elev Zlll 613'-f)"

Elev Zll2 613'-0" Elev Z211 630'-0" Canister Connector and Wire Details Total Connectors Conductors Number of Used in per Wire Size Connectprs Class lE Ckt Connector and Type 3

1 3

l/C 111/0 AWG, 19 (No 1)

Strand, Tinned Copper With Sili-con-Rubber Insula-3 3

3 tion - Rockbestos (No 1, 2 and Type SR-ML

3)

Rock therm 24 2

3 l/C 1112 AWG, 7 (No 8 and 9)

Strand,* Tinned Copper With Sili-con-Rubber Insula-24 5

3 tion - Rockbestos (No 3, 8, 9, Type SR-ML 11, 16 and 17)

Rocktherm 24 7

3 l/C 1112 AWG, 7 (No 3, 6, 7, Strand, Tinned 8, 9, 11, 12 Copper With Sili-and 18) con-Rubber Insula-tion - Rockbestos Type SR-ML Rocktherm TABLE 2-1

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sheet 2 (Contd) 2.0 Various connectors of the subject penetrations are used in Class lE circuits inside the containment and are listed in Table 2-1 above.

These connector assemblies inside containment.are potted (with the exception of two - see Section 2.4) with Bendix potting compound and use silicon rubber sealing washer or 0-ring (Bendix Part No 10-101378) between receptacle and connector plug.

2.1 ELECTRICAL PENETRATION ASSEMBLIES The electrical penetration assemblies comprise of cylindrical canisters, hermetically sealed at both ends.

The canisters are manufactured from 12" pipes and are either 60" or 75" long, depending upon which penetration area of cont~inment building they are installed.

Recessed back from each end of the. canister is a plate which is machined to receive male pin electrical bulkhead connectors.

The bulkhead connector bodies are steel and are attached to the plate by brazing.

The bulkhead connector pin support and dielectric material is glass.

The pins of the bulkhead connectors on each end of the canister are joined by silicon rubber insulated conductors of the conductor size suitable for the service of each bulkhead corinector.

The conductors are supported by fiber glass discs internally in the canister at 12-inch intervals.

The junctions between the bulkhead connector pins and the insulated conductors were protected by heat shrink tubing to prevent relative movement of the conductors (during assembly) and facilitate initial assembly.

The heat shrink tubing has no role to play during normal or accident conditions and a postulated failure of heat shrink tubing will have no impact on the functional capability or the integrity of the penetration assemblies.

The rear face of the bulkhead connector assemblies were coated with RTV compound to hold the heat shrink tubing in place during initial assembly.

During normal or accident conditions, RTV has no bearing on the functional capability or the integrity of the penetration assemblies.

The mating half of the connectors (removable connectors attached to external cabling inside containment) are potted with Bendix potting compound.

The connectors are sealed at the mating end by an 0-ring (sealing ring) and by a compressible pin insert.

The sealing ring provides an environmental seal at the mating end.

On the removable connectors, the environmental seal is provided by the potting compound, which completely encapsulates the connector cable interface, sealing around the cables and around the. connector shell.

2.2 The qualification information of the subject electrical penetrations is based on the following documents and discussioR:

2.2.1 Document Reference 1 includes a Wyle Laboratories Test Report No 43913-2 dated February 25, 1978 of the actual type testing performed on four potted connector assemblies (typical of the subject penetrations) under simulated LOCA conditions that may occur during a postulated Design Basis Event.

nul080-0014a-43 4

Rev 1, 10/30/80

Sheet 2 (Contd)

The four connectors, two power and two control, are representative of those in use at Palisades Plant, being of the.same design, construction and material.

The connectors and cable were assembled by Wyle Lab personnel to procedures given in the Viking Instruction Manual - T398, Rev A.

The connector assemblies were then potted with Bendix potting compound No 9-4954~1 per Consumers Power Company procedures (Reference 7) which encapsulates the rear of the connector and a portion of the cable*to provide an adequate seal at the cable entry to the connector.

Red silicon rubber sealing washer or 0-rings were substituted for original 0-rings to provide a satisfactory seal between the receptacle and connector plug.

During the type testing, the connector assemblies were subjected to LOCA environment of 295°F, 62.7 psia, 100% relative humidity and chemical sprays at the rate of 0.15 gal/min/ft 2

The connector assemblies were kept energized with rated currents and voltages for the 24-hour duration of the LOCA test.

Three of the four connector assemblies tes:ted, s:atisfied the requirements specified.

The fourth connector assembly failed due to a pin to connector shell ground.

The failed connector was a Viking*part No.980-0016-031, three conduct.or, No 12 wire, 480 V ac connector..

An imperfection in the potting, beneath the potting boot, provided a leak path for steam or water to enter the grommet area where a split in the grommet material produced a leak path directly to the pins.

This particular connector utilized a small diameter, relatively long, 3/4" x 10", potting boot, ma~ing it difficult to insure complete filling of the boot.

This situation can be avoided by including the following steps in the application procedure:

a.

Heat the connector and potting boot with a heat lamp while potting to prevent the potting from thickening.

b.

Use a succession of short potting boots rather than one long boot to insure proper filling.

c.

Inspect. the cured potting for flaws and repair if necessary, In actual*practice, it was found that the preheating of the potting boot and connector was sufficient to eliminate the void problem without resorting to short potting boots.

Potting of the rear of the connector and the 0-ring seal between the receptacle and connector plug gave satisfactory performance during the environmental testing.

2.2.2 Document Reference 2 includes a Bendix Engineering Report No 2345 dated September 2, 1977, for Environmental Testing of Nuclear Cable Sample Assembly L-33627-1.

nu1080-0014a-43 5

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I Sheet 2 (Contd)

Heat age test at 150°C for 228 days (5,475 hours0.0055 days 0.132 hours 7.853836e-4 weeks 1.807375e-4 months ) included in this report adequately supports the.qualification of 40-year life at 90°C for the Bendix potting compound No 9-9454-1 which has been used for potting the Palisades connectors~ The report also confirms that the potting compound can successfully withstand the effects of gamma radiation up to 1.1 x 10 8 rad.

2.2.3 Document Reference 3 includes Bendix Engineering Report No 2405, portions of Wyle Laboratories Report 43117-1, May 9, 1978, Material Specifications 3163 and 3372 for the qualification of Bendix sealing washer or'O-ring part No 10-101378.

2.2.4 Document Reference.4,includes Viking Industries proposal (Design Type 1239X-100) for the subject electrical penetrations which confirms that wires used inside the canister are insulated with silicon rubber and that the bulkhead connector pin support and the dielectric material is fused glass~

2.2.5 Document Reference 5 lists Viking Industries Inc "Receptacle Assembly Drawings" made for Palisades penetrations.

These drawings indicate that fused glass has been used as bulkhead connector pin support and dielectric material for the subject penetrations.

2.2.6 Document Reference 6 includes a Rockbestos report on qualification of Firewall Type SR Class lE electric cables which are similar to the silicon rubber insulated wires used inside the canisters.

During this

qualification testing, the cables were irradiated to 2 x 10 8 rad gamma, thermally aged at 180°C for 1,400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months to simulate 40-year life at 125°C and then subjected to LOCA environment at 340°F, 114 psig, 100% RH and chemical spray.

The cable specimens were kept energized with rated voltages and currents for the 30-days' duration of the test.

During post-LOCA mandrel test, the cable specimens successfully withstood 80 V/mil dielectric test.

2.2.7 Document Reference 7 includes a Consumers Power Company Electrical Connector Potting Procedure No SPS-E-2 dated May 23, 1978.

2.2.8 Document Reference 8, Page 128, includes Table 3.6 on Radiation Dose Limits of Materials.

2.2.9 Document Reference 9 includes corrosion properties of materials.

2.3 DISCUSSIONS 2.3.1 SERVICE CONDITIONS INSIDE CONTAINMENT DURING LOCA - TEMPERATURE AND PRESSURE STEAM CONDITIONS This qualification is described separat~ly for various components of the complete electrical penetration:

nu1080-0014a-43 6

Sheet 2 (Contd)

a.

Connector assembly, which also includes the potting compound of the sealing washer or 0-ring.

Document Reference 3 indicates that the LOCA environment simulated during type testing for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months envelops the required service conditions (except for peak pressure value of 51 psig) as given in FSAR and Section. II.. D.1.

Peak pressure value achieved during type test was 48 psig:

However, in view of the fact that peak temperature of 295°F was maintained for 300 seconds during LOCA test as against requirement of 278°F for 46 seconds~ it is concluded that marginal difference of 3 psig will have 'no effect on the qualification.

Analysis of containment parameters shows.that following a LOCA, temperature and pressure conditions return to normal in about 10 days.

Therefore, the containment spray is not likely to continue beyond 11 days.

Even though the test duration was limited to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ' it is.. concluded that the potting compound is qualifi.ed, based on' the follow:lng~ reasons:

1.

Analys:*is indicates that epoxy compollhds cfo not. react with spr*ay:

chemic~ls. in 1oW; conce~F,;-:~tions.

2..Postulated fail~z:e.s in potting can, o.ccur.. dµe to high temperatures and/or high."pressures~:. Since peak. pressure and.*

temperature was attained during the.initial part* of the test and no failure occurred, it is extremely unlikely that failure.

will occur later under reduced pressure and temperature conditioning.

b.

Canister which includes glass seal and wires*with silicon rubber insulation.

Document References 4, 5 and 6 confirm that glass seal used around bulkhead connector pins and the silicon rubber insulated wires used for. these penetrations have been separately qualified-to envelop the.service conditions as given in FSAR and Section II.D.l.

2.3.2 RADIATION Document References 1, 2 and 3 indicate that the connector assemblies, including potting compound and sealing ring (0-r.ing) have been qualified to 1.1 x 10 8 rad gamma-against the requirement of 2 x 10 7 rad gamma and 2 x 10 8 rad beta at the outer surface.

It is concluded that the Palisades requirements are satisfied based on the following evaluation:

a.

Test radiation of 1.1 x 10 8 rad gamma exceeds the requirement of 2 x 10 7 rad gamma.

nul080-0014a-43 7

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I Sheet 2 (Contd)

b. *Penetration sleeve subassembly which covers the connector assembly inside the containment provides adequate shielding from beta radiation.

Table 3.6 on "Radiation Dose Limits of Materials" in Reference Document 8 indicates that no measurable changes/degradations occur in the properties of fused glass when exposed to radiation levels of 1 x 10 9 rads gamma which exceeds. the requirement of 2.2 x 10 8 rads (combined gamma and beta) for the Palisades Plant.

Document Reference 6 by similarity confirms that silicon rubber insulation of wires inside the canister can withstand radiation doses up to 2 x 10 8 rads gamma which exce~ds the 1 x 10 7 rads gamma requirement.

2.3.3 CHEMICAL SPRAYS The LOCA test covered by Reference 1 indicates that the required chemical spray was continued only for 20 minutes during peak valves of temperature and pressure.

This meets the requirements of the Palisades Plant based on following evaluation:

a.

Analysis covered by Document Reference 9 indicates that spray chemicals, including hydrazine in low concentrations, have no effect on the potting compound and the sealing washer or 0-ring.

b.

In addition, hydrazine is highly unstable and will decompose rapidly when chemical spray is released into containment.

2.3.4 AGING Document References 2 and 3 provide evidence of 40-year life qualification for the potting compound and the sealing washer or 0-ring.

Document Reference 6, by similarity, confirms the 40-year life qualification for the silicon rubber insulated cables used inside the canisters.

Document References 4 and 5 provide evidence that boron-free soda-lime glass used by Viking Industries Inc for bulkhead connector pin support and the dielectric material has much higher threshold for nuclear radiation exposure (up to 1 x 10 9 rad) than other dielectric materials and has very high temperature withstand capabilities (suitable for operation at 575°F for 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months ).

Therefore, it is concluded that the glass seal is not susceptible to degradation due to thermal aging and is considered to be q~alified for 40-years' life requirement at the Palisades Plant.

nu1080-0014a-43 8

Sheet 2 (Contd) 2.4 SAFETY-RELATED CONNECTOR ASSEMBLIES WHICH ARE NOT POTTED There are two connector.assemblies which are safety related and not potted.

These will be potted by June 1982.

These are the circuits for the shutdown cooling isolation valves.

These valves are motor operated.

and have tag numbers of M0-3015 and M0-3016.

These valves are used during small LOCAs in order to go into shutdown cooling.

The proce-dures state that, at five hours after the LOCA began, if one HPSI pump can maintain pressure above 250 psig, go on shutdown cooling.

However~

should the connectors at the penetration fail due to the lack of potting, a short circuit may develop such that these valves are inoperable.

The procedures state that, if the shutdown cooling system is not available, to continue cooling with the. steam generator indefinitely.* The procedures also refer to the feedwater system operating procedure which describes five different sources of water to the condensate storage tank.

None of the sources or their valves is in a hostile area.

Should the primary circuit breaker also fail when the short circuit develops, the fault current may be such as to damage the penetration.

However, at five hours (1.8 x 10 4 seconds) after a small LOCA (0.02 ft 2 is about the size that one HPSI can maintain the.

primary* coolant pressure above 250 psig), the containment pressure will be very close to atmospheric.

The resulting release would be extremely*

small because of the small pressure differential between containment and atmosphere and the fact that this small break would not result. in core uncovery which would minimize fuel failures.

nul080-0014a-43 8a Rev 1, 10/30/80

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Component DORGR 1 DORGR lA DORGR lB Gamma &

Beta DORGR lC DORGR 1D DORGR 2 DORGR 2A DORGR 2B DORGR 2C Sheet 3 600 Volt Electrical Penetrations (Types P4, PS and P6)

Service Conditions Inside Containment for LOCA Conditions Temperature and Pressure Steam Conditions Temperature, pressure and humidity levels were maintained at 295°F, 62.7 psia and 100% for the required duration which meet or exceed the values given in Figures 7, 8 and 9 of the report and the 100% relative humidity requirement (see Sheet 2); therefore, the guidelines are met for these parameters.

Radiation For connector assembly inside containment along with potting compound, sealing washer or 0-ring and bulkhead connector glass seals, the qualified level is 1.1 x 10 8 rads gamma.

For wires*

inside canister, the qualified value is 2 x 10 8 rads gamma.

Therefore, the radiation guideline is met.

Submergence This equipment is located above the flood level elevation of 596'-o" and, therefore, the guideline is met.

Containment Sprays The chemical spray used in the test was 1,586 to 2,406 ppm boron and 75 ppm hydrazine which is more caustic than that used at Palisades; therefore, the guideline is met.

Service Conditions for a PWR Main Steam Line Break Inside Containment Temperature and Pressure Steam Conditions Use of LOCA conditions is acceptable because CP Co and NUREG-0458 recognize that, although the peak temper~ture and pressure for an MSLB inside containment is greater than that for a LOCA, its duration is short and the effect will be small.

Radiation Same statement as DORGR lB.

Submergence Same statement as DORGR lC.

nul080-0014a-43 9

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DORGR 2D DORGR S DORGR SA DORGR SB Sheet 3*ccontd)

Chemical Sprays Same statement as DORGR 10.

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

Qualification by Evaluation and/or Analysis The guideline is met as follows:

a.

Temperature, pressure, chemical spray, radiation and aging qualification of connector assemblies with potting compound and sealer washer or 0-ring was performed by evaluation (see Sheet 2).

b.

Temperature and radiation quaiification of glass seals and insulation. on wires inside canister was performed by analysis.

Qualification by Type Testing

1.

Simulated Service Conditions and Test Duration Temperature, pressure and relative humidity levels were maintained at 29S°F, 62.7 psia and 100% for the required duration.

This envelops the LOCA peak values for the required period of time as explained on Sheet 2; therefore, the guideline is met.

2.

Test Specimen Reference Document 1 confirms that the test specimens were identical.to the equipment installed at Palisades; therefore, the guideline is met.

3.

Test Sequence

a.

Pretest Inspection

b.

Function Test

c.

Accident (LOCA) Qualification

d.

Post-LOCA Test Functional

e.

Post-LOCA Test Inspection

4.

Test Specimen Aging References 2 through 6 as discussed on Sheet 2 document that aging quali-fication was demonstrated for 40 years plus LOCA (see Paragraph 2.3.4 of nu1080-0014a-43 10

Sheet 3 (Contd)

Sheet 2); therefore, this complies with the requirements of the guidelines.

5.

Functional Testing and Failure Critieria The connector assemblies were tested for insulation integrity and did not fail.

This complies with the requirements of the guidelines.

6.

Installation Interfaces Mounting arrangement of the test specimens during qualification testing were similar to the installed equipment at the Palisades Plant.

This complies with the requirements of the guidelines.

DORGR 6 DORGR 7 DORGR 8 Margin The guidelines are met with respect to temperature,. relative*

humidity, radiation and aging; therefore, margin is not a consid-eration.

Pressure qualification was performed by evaluation with consideration of a slight margin factor as discussed on Sheet 2; therefore, the guideline with respect to pressure is also met.

Aging qualification was performed as discussed on Sheet 2 (Para-graph 2.3.4) and in accordance with References 2 through 6; therefore, the guideline is met.

Documentation References 1 through 9 form the documentation.

nul080-0014a-43 11

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Sheet 4 Component Amphenol Connectors (In Junction Boxes J320, J324, J325, J329, J326 and J321).

This equipment was qualified in the original CP Co submittal with no objection by Franklin Research Center.

nu1080-0499b-43 89

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Owner: Consumers Power Company Facility: Palisades Docket: 50*255 EQUIPMENT DESCRIPTION Parameter System:

Operating Service Water and Time Reactor Protect Sys Plant 1.0. Number:

Temperature See Note 2

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Component:

Junction Boxes and Pressure Te1l!i-p1tJJc1u~Jrpcks (PSIA}

Terminal Board -

Westin~house Mode Number:

Relative No 805432 Humldily (%)

Purchase Order Number:

Chemlcal Spray Function I Service:

See Note 3 Radiation (Rad)

Accuracy: Spec:

Aging Demo:

r

icrea 11lrc: t nsi e on ainment Bevatlon: Va.rious Submergence Flood Level Elevation 595'-0" Above Flood Level:

Yes:

No: X EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Date:

ENVIRONMENT DOCUMENTATION REFERENCES QUALIFICATION Accident Ouallficatioo Accident Qua!

METHOD 4 Hours Section Test and 1 Hour III.B 1, 2 Analysis See figures 7 & 8 286 (Peak)

Section Test and III.D.l 1, 2 Anal vs is See Figure 9 Section 105.7 rrr. D. l 2

Test and Analysis Section 100 100 Test and II. D.l 1, 2 Analvsis 2640 ppm boric 3ection Note 1 Test and acid II.D. 2 1, 2 & 4 Analysis

1. 8 x 10 6 5 x 106 3ection Test and II;D.5 3

Analysis Section

.4o Years + LOCA 4o Years + LOCA Test and tr. D. 8 1

Analysis Yes See Sheet 2 DOCUMENTATION REFERENCES NOTES OUTSTANDING ITEMS

1.

Report on Terminal Block/Junction Box Environmental

1.

1750 to 2000 ppm boric acid with -50. to 100 ppm N2H4...

Testing, by Northeast Utilities Service Company, dated 2.

J-350, J-355 and J-521 with Westinghouse TB's March 27, 1978.

.No 805432.

2.

Test Report on.the effect of a LOCA on an electrical performance of four terminal blocks, by Westinghouse Corporation. a~ted September 13. 1977.

G-0858-01 A A

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Owner: Consumers Power Company FacRlty: Palisades EQUIPMENT QUALIFICATION REPORT.

Docket: 50-255 DOCUMENTATION REFERENCES (cont)

3.

Test report by A P Colaiaco of Westinghouse Note Junction PT-0102

4.

Letter from C A St Onge of Bechtel to i

R Ma.rusich of CP Co dated October 3, 1980.

~-~

Component Sheet No.:

Revision:

Date:

NOTES (cont)

Boxes for Containment Air Coolers and G*0858*02A

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 terminal blocks rated at 600 volts and 40 amperes.

They are located below the flood level elevation of 596 1 -0 11 and will be submerged.

The junction box and terminal blocks are used in Class lE 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 150°C (302°F) for 171 hours0.00198 days 0.0475 hours 2.827381e-4 weeks 6.50655e-5 months .

This simulates a lire of 40-year for an ambient of 70°C (158°F).

After thermal aging the specimen was subjected to 5 x 10 6 rads and a chemical spray test with 2640 ppm of boric acid at 286°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 the terminal block terminals were e~e~giz~d 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 material 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 containment.

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 connected.

2.

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

nu0980-0589a-43 92 Rev 1, 10/30/80

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.1 Sheet 2 (Contd)

f.

They will become submerged during the LOCA.

However, the function will be able to be carried out prior to submergence.

See Pages 322 and 531.

g.

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.

nu0980-0589a-43 93 Rev 1, 10/30/80

Component DORGR 1 DORGR lA DORGR lB Gamma Beta DORGR lC DORGR 1D DORGR 2 DORGR 2A DORGR 2B Sheet 3 Junction Boxes (J-350, -355 & -521) and Terminal Blocks (No;805432)

Service Conditions Inside Containment for LOCA Conditions Temperature and Pressure Steam Conditions The requirements of the DOR guidelines are complied with.

The testing was run at temperature and pressure steam conditions which exceed that given in FSAR and Section II.D.1.

See Sheet 2.

Radiation The requirements of the DOR guidelines are complied with as the JB and TB were tested to 5 x 10 6 R and need only withstand 1.8 x 10 6 R.

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

Submergence These boxes will get submerged; however, their function.will be accomplished prior to submergence.

See Sheet 2.

Containment Sprays The requirements of the DOR guidelines are complied with as the test included contaiment sprays more harsh as the ones used at Palisades.

Also see Sheet 2 for discussion.

Service Conditions for a PWR Main Steam Line Break Inside Containment 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 lA for details of LOCA qualification.

Radiation The requirements of DOR guidelines are complied with.

Refer to response in DORGR lB.

nu0980-0589b-43 94 Rev 1, 10/$0/80

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Sheet 3 (Contd)

DORGR 2C Submergence See DORGR lC.

DORGR 2D Chemical Sprays The requirements of DOR guidelines are complied with.

Refer to response in DORGR lD.

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

DORGR SA Qualification by Evaluation and/or Analysis The requirements of the DOR 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 the test specimens were similar to the ones at Palisades.

3.

Test Sequence The requirements of the DOR 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.

nu0980-0S89b-43 9S Rev 1, 10/30/80

Sheet 3 (Contd)

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.

6.

Installation Interfaces The requirements of DOR guidelines are complied with.

See Sheet 2.

The terminal blocks are mounted inside to junction box as in the case of test specimen.

DORGR 6 DORGR 7 DORGR*8 Margin The guidelines of the DOR are complied with.

See Sheet 2.

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

Aging The requirements of DOR guidelines are cociplied 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. ~imulate 40-year, life..

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

nu0980-0589b-43 96

-~ ----- - -- ------ -

Owner: Consumers Power Company Facility: Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Docket* 50 255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES QUALIFICATION EQUIPMENT DESCRIPTION Accident Oual METHOD Parameter Accident Qualification System:

Operating 3 Hours See Sheet 2 See See Evalu.a ti on Engineered Safe-Time Sheet 2 Sheet 2 guard System Plant.l.D. Number:

Temperature See Figures 7 & 8 See Sheet 2 Section See Evaluation See Note 1 l°F)

II.D.l Sheet 2 Component:

Solenoid Valve Pressure

.See Figure 9 See Sheet 2 Section See Evaluation Mllflufaclurer:

(PSIA)

II.D.l Sheet 2 ASCO Model Number:

Relative 100 See Sheet 2 Section See Evaluation WPHT8300B61-RF Humidity(%)

II.D.l Sheet 2 Purchase Order Number:

1750 to 2000.ppm See Sheet 2 Section See Evaluation Chemical Spray Boric Acid With II.D.2 Sheet 2 Function/Service:

50-100 pp_m N2H4 Safety Injection Radiation 2.5 x 106 7.0 x 106 Section 1

Evaluation

['ank Valves (Rad)

II.D.5 Accuracy: SJ>ec:

Aging 4o Years See Sheet 2 Section See Evaluation Demo:

Location:

+ LOCA II.D.8 Sheet 2 Lnside Containment Submergence Not Subject to Etevalloil:

Submergence

)08'-6"

~IOO<J Level Elevation 5 96 ' -0" Above Flood Level:

Yes: x No:

DOCUMENTATION REFERENCES NOTES

1.

The Effects of Nuclear Radiation on Elastomeric and Plastic Components and Materials, R W King, et al, REIC Report #2.1

1.

SV-3069, -0338, -0342, -0346 and -0347 OUTSTANDING ITEMS G-0858-01A

Sheet 2 ASCO Solenoid Valveg ASCO SV-30~ -0338, -0342 SV-0346,. -034 7 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 Engineering NSSS Response to Small LOCAs, show that SI tanks are required only for breaks 0.1 ft 2 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 3 of SI tank liquid compared to 1,103 ft 3 in the tank.

This is an acceptable loss.

For the large LOCA, this loss will be significantly less as the safety injection signal occurs at one second.

If these* s.olenoid valves fail in.:the long term,* HPSI flow may be diverted to the Primary Coolant System Drain Tank instead of to the Primary Coolant 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 postulated.

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, since the core does not uncover, the radiation le.vels 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.

nul080-000la-43 328' Rev 1, 10/30/80

0 -

w 0 -

00 0

Owner: Consumers Power Company Facility: Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Docket: 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION QUALIFICATION Parameter Accident Qualification Accident Oual METHOD rvstem:

Operating Eng neering Time safeguards system 1 Hour Section TTT D

Plant l.D. Number:

Temperature See Note 1 (Of)

See Section Com~nt*

Figures 7 & 8 See Sheet 2 II. D. l See Sheet.2 Evaluation Electro...- neumatic Tra1M:dMcffJ Pressure See an ac rer:

(PSIA)

Section Fischer Controls Co Figure 9 See Sheet 2 II. D. l See Sheet 2 Evaluation Model Number:

Relative Section E/P-546 Humidity (%)

100 See Sheet 2 II.D.l See Sheet 2 Evaluation Purchase Order Number:

M-233 Chemlcal 1750 to 2000 ppm Spray Boric Acid with See Sheet 2 Section Function/Service:

50 to 100 nnm N,..ll II.D.2 See Sheet 2 Evaluation Safety Injection Tanl Radiation 6

T-82A,B,C,D Valves (Red) 2.5 x 10 See Sheet 2 Section II.D.5 See Sheet 2 Evaluation Accuracy: Spec:

Aging Demo:

40 Years + LOCA See Sheet 2 Section location:

II.D. 8 Bee Sheet 2 Evaluation Inside Containment Submergence Not Subject to Elevation:

Submergence IJ08 I -6 11 Flood level Elevation 596'-0" AbOve Flood level:

Yes: x No:

DOCUMENTATION REFERENCES NOTES

1.

Laboratory Report, "Operational Tests of the Fischer Type 546 Electropneumatic Transducer for Nuclear Reactor Containment Vessel Service," June 12, 1973~

2.

Letter from H Douglas Waldron, Harley Company, to W C Cooper, Consumers Power Comoanv. Januarv ?4 1Q78 OUTSTANDING ITEMS

.t

" *e

~..

l G-0858*01A

Owner: Consumers Power Company Facility: Palisades EQUIPMENT-QUALIFICATION-REPORT------ -------C 1-sh N omponen ee o~:- -------*---

w CP (J'\\

0 -

w 0 -

CP 0

Docket: 50-255 DOCUMENTATION REFERENCES (cont)

3.

Telephone contact between S McLagon, Fischer Controls, and J Lewis, Wyle Laboratories, on September 12, 1980.

4.

Final Report on Consulting Services for Engineering Support on E/P-1057 and E/P-1059, Nuclear Environmental Qualification Report, Wyle Laboratories.

. ; :~

Revision:

Date:

NOTES (cont)

G-0858-02

e Fis6her C~~trols E/P 0338, 0342, 0346, 0347 Sheet 2 Component Fischer Controls Electropneumatic Transducers The transducers have been qualified by an environmental test described in Reference 1.

The test sequence was as follows.

Steam was admitted to the test chamber and brought to an equilibrium condition of 75 psig and 320°F.

The time required was 10 to 30 seconds.

This temperature and pressure were h~ld for one hour.

The conditions in the chamber were reduced to 41 psig and 288°F and held for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; then cooled to ambient.

During the test, the transducer was exercised at one hour and several times during the reduced pressure and temperature phase.

Reference 2 provides the review and conclu-sion by Fischer Controls that the transducers will withstand 2.x 10 7 rad.

Chemical spray will not affect the transducer as it is enclosed in a metal housing.

Reference 3 documents the fact that only the coil windings need be qualified for proper operation.

The coil windings are Formvar (Reference 3),

and they have a qualified life of greater than 40 years (Reference 4).

nu1080-0499c-43 387 Rev 1, 10/30/80

I I

I Fisc~er Controls E/P 0338, 0342, 0346, 0347 Sheet 3 Component ~~~F~i~s~c~h~e~r:...._:C~o~n~t~r~o~l~s:...._:E~l~e~c~t~r~o~p~n:;,;;_;;_eum~~a~t~i~c--=T~r~a-n_s_d_u_c_e_r_s_*~~~~~~~~~

DORGR 1 DORGR lA DORGR lB Gamma Beta DORGR lC DORGR 1D DORGR 2 DORGR 2A DORGR 2B Service Conditions Inside Containment for LOCA Conditions Temperature and Pressure Steam Conditions Figures 7, 8 and 9 define.the required service conditions for temperature and pressure.

The humidity requirement is 100%.

The environmental test enveloped these conditions for 13*hours, so the guidelines are met.

Radiation*

The radiation to which qualification must be shown is 2 x 10 7 rads.

The transducer will withstand 2 x 10 7.rads; therefore, the guidelines are met.

Beta radiation does not effect this enclosed transducer.

Submergence These components are located above the flood level elevation of 569'-0"; therefore, the guidelines are met.

Containment Sprays The transducer is enclosed and, therefore, the effects of the chemical spray are negligible.

Service Conditions for a PWR Main Steam Line Break.Inside Containment Temperature and Pressure Steam Conditions Use of LOCA conditions is acceptable 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 small.

Radiation See DORGR lB.

nu1080-0499c-43 388 Rev 1, 10/30/80

e 9

Fischer Controls E/P 0338, 0342, 0346, 0347 Sheet 3 (Contd)

DORGR 2C Submergence Same statement as in DORGR lC.

DORGR 20 Chemical Sprays See DORGR 1D.

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

DORGR SA Qualification by Evaluation and/or Analysis Qualification for temperature, pressure and humidity was by test.

Qualification for chemical spray, radiation and aging was by evaluation (see Sheet 2).

DORGR SB Qualification by Type Testing

1.

Simulated Service Conditions and Test Duration The test exceeded the required service conditions for the 13-hour duration of the test.

The short test is acceptable because the critical ag~ sensi-tive materials have a qualified life of greater than 40 years.

"~.

2.

Test Specimen The test specimen was the same model as installed at the Plant.

3.

Test Sequence The test sequence included two steps of pressure and temperature (see Sheet 2).

4.

Test Specimen Aging Aging was not. part of the test (see Sheet 2 and DORGR 7).

S.

Functional Testing and Failure Criteria The transducer was operated during*thetest and did not fail.

6.

Installation Interfaces The installation is unknown.

nu1080-0499c-43 388a Rev 1, 10/30/80

I DORGR 6*

DORGR 7 DORGR 8 Fischer Controls E/P oj3s, 0342, 0346, 0347 Sheet 3 (Contd)

Margin No additional margin factors are needed as the transducer met the guidelines.

The critical components have been shown to have a qualified life of greater than 40 years.

Documentation References 1 through 4 form the documentation.

nu1080.-0499c-43 388b Rev 1, 10/30/80

Fischer Controls E/P 0338, 0346, 0347 Sheet 4 Component Fischer Controls Electropneumatic Transducers This equipment was not included in the November 1978 CP Co submittal and was, therefore, not addressed by the Franklin Research Center report.

nu1080-0499c-43 388c Rev 1, 10/30/80

-~ --*-

DOR GUIDELINE REQUIREMENTS DORGR 7 - AGING DORGR 8 - DOCUMENTATION

~----

-- ---- - -- OOR c;-uroE-i.;rNEs- -vs-ouAL"lF-IGA-T-ION-- _____ _

EQUIPMENT Amphenol Penetration Penetration Penetratiom Types Pl, Types P4, P3, P4, PS, Conn P2 Penetration PS, P6, P6, Cl, C2, Pene-J320~ J324, tration J32S, J329, Types P4, l 1, 13 11' 12' 13' PS, P6 Nl J326 & J321 INl x

x x

x IJ]3 IS 350' 355 & 521 &

rr'B' s No ao5432 :x 0\\

0

DOR GUIDELINE REQUIREMENTS DORGR 1 - SERVICE CONDITIONS INSIDE CONTAINMENT FOR A LOCA DORGR lA - TEMPERATURE AND PRESSURE STEAM CONDITIONS DORGR lB - RADIATION DORGR lC - SUBMERGENCE DORGR lD - CONTAINMENT SPRAYS DORGR 2 - SERVICE CONDITIONS.FOR*A PWR MAIN STEAM LINE BREAK (MSLB)

INSIDE CONTAINMENT DORGR 2A - TEMPERATURE AND PRESSURE STEAM CONDITIONS DORGR 28 - RADIATION DORGR 2C - SUBMERGENCE DORGR 2D - CHEHiCAL SPRAYS DORGR 3 - SERVICE CONDITIONS OUTSIDE OF CONTAINMENT DOR GUIDELINES VS QUALIFICATION EQUIPMENT Cable Code 804 i

\\

I

\\ \\ I

\\ I

\\ /

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J\\

1 I \\

/ \\

I \\

I

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DOR GUIDELINE REQUIREMENTS

>RGR-3A - AREAS SUBJECT TO A SEVERE

~VIRONMENT AS A RESULT OF A HIGH

\\IFJU:V 1 TNF RJllO'A ll' (1-fFl._'

ORGR 3B - AREAS *WHERE FLUIDS ARE ECIRCULATED FROM INSIDE CONTAIN-ENT TO ACCOMPLISH LONG-TERM CORE OOLING FOLLOWING A LOCA

~.:-

ORGR 381 - TEMPERATURE AND RELATIVE

.UHIDITY ORGR 382 - RADIATION ORGR 3C -

AREAS~NORHALLY HAIN-

'AINED AT ROOM CONDITIONS ORGR 4 - QUALIFICATION METHODS IORGR 4A - SELECTION OF

!UALIFICATION METHOD

>ORGR 48 - QUALIFICATION BY

~ESTING

>ORGR 5 - QUALIFICATION BY A COM-

~!NATION OF METHODS (TEST, EVALUA-r10N-AN~1.ys1s)

JORGR 6 - MARGIN I

--- DOR GUIDELINES VS QUALIFICATION EQUIPMENT Cable Code so4 x

x x

x I\\

I

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x x

d :i>-

(1) 'O

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- ----- ---*---DOR-* **GUIDE-LI-NES_vs QUALIFICATION EQUIPMENT DOR GUIDELINE REQUIREMENTS Cable Code S04

>ORGR. 7 - AGING x

I DORGR 8 - DOCUMENTATION x

/

I I

e GE EMB-0131, -0133, -0211 and -0221 Sheet 4 Component --~-R_o_o~m~A_i_r~C_o_o~l~e~r_M_o_t_o_r_s.;,_,;E~M~B~--0_1_3_1~,.__-_0~1~3~3~,.__-_0~2~1~1;._:a~n_d~-~0~2~2~1'--~~

I Franklin Research Center has not reviewed this equipment for qualification.

nu0980-0531a-43 497

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CX>

0 Owner: Consumers Power Company Facility: Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Docket: 50-255 Date:

. ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION

~ *-* _,_ -~--*,. __.,' -*-

QUALIFICATION OUTSTANDING Parameter Accident Qualification Accident Qual METHOD ITEMS System:

Operating

- *- Days 33 Section HVAC Time 30_Days See Sheet 2 III.B See Sheet 2 Test and evaluation Plant l.D. Number:

Temperature EMB-l20g,~1209*,-1210 (Of) 283 minimum Section Test and

-110 See Figures 7 & 8 See Sheet 2 II.D. l See Sheet 2 evaluation Component:

Air cooler fan Pressure mo tori;

- * *

Millfufacturer; (PSIA) 70 Section Test and General !lectric See Figure 9, See Sheet 2 II.D. l See Sheet 2 evaluation Model Number:

Relative Humidity(%)

100 Section Test and 5K405YK232 100 See Sheet 2.

II.D.l See Sheet 2 evaluation Purchase Order Number:

Chemlcal exposed to Section Test and 5935-M-59 Spray Not Function I Service:

chemical spray See Sheet 2 II.D.2 See Sheet 2 evaluation Cool containment Radiation 108 environment (Rad) 2 x 107 1 x Section Test and See Sheet 2 II.D.5 See Sheet 2 evaluation Accuracy:

Spec:*,

j Aging 22.8 Years + LOCA Demo:'.*

Section Test and Location:

40 years + LOCA See Sheet 2 II.D.8 See Sheet 2 evaluation Inside containment Submergence Elevation:

. Not subject to See Note 1 submergence Flood Level 596!-0" Elevation Above Flood Level:

Yes:

No:

DOCUMENTATION REFERENCES NOTES

,'i.

Environment Test Report 51542-3, Wyle Laboratories.

1.

Field measurement has not been made, but drawings confirm that the motors are well above elevation

2.

Letter, D. Kennedy (Buffalo Forge Co.) to 596'-0".

D. Moeggenberg (CPCo), dated 4/17/79, attached to*

letter, R.E. Wischhusen (Buffalo Forge Co.) to

\\

D. Moeggenber~ __ {~PCo), dated 4/17 /79.

G-0858-01A e

\\JI I\\)

0\\

-~-

Owner: Consumers Power Company Facility:.Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Docket: 50*255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES EQUIPMENT DESCRIPTION QUALIFICATION Poremeler Accident Qualilicalion Accident Ou el METHOD System:

Operating 30 Days See Sheet 2 Section See

!Evaluation Primary Coolant Time System III.B Sheet 2 Plant t.D.- Number:

Temperature PT-0103

("Fl See Figures 7 & 8 See*Sheet 2 Section See Evaluation P

Com~nent:

II.D.1 Sheet 2 ress re Transmitter Pressure Manufacturer:

(PSIA)

See Figure 9 See Sheet 2 Section See IEv~luation Foxboro II.D. l Sheet 2 Model Number:

Relative 611GH Humidity 1%1 100 See Sheet 2 Section See Evaluation II.D.l Sheet 2 Purchase Order Number:

M-1 Chemical 1,750 to 2,000 ppn See Sheet 2 Section.

See Evaluation Spray Bork Acid With II.D*2 Sheet 2 Function/ Service:

50-100 ppm N2H4 Pressuri:zer T-72 Radiation 2 x 107 Pressure Indication (Radl See Sheet 2 Section See II.D.5 Sheet 2 Accuracy:

Spec:

Aging Demo:

40 Years Plus LOCA See Sheet 2 Section See location:

II.D.8 Sheet 2 Inside Co~tainment Submergence Elevatlon:

Yes See Sheet 2 Section See Evaluation 591'-0" II.D.3 Sheet 2 Flood Level Elevation 596'-0" Above Flood level:

Ves:

No: x DOCUMENTATION REFERENCES NOTES

1.

Qualification Test Report for.Rosemount Pressure Transmitter Model 11J3A.

Rmt Rpt 3788, Rev A, March 1980.

OUTSTANDING ITEMS GOA~ff.OIA e:

9cboro PT-0103 Sheet 2

component Foxboro Pressure Transmitter 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 beeri 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 period.

c.

Radiation at 0.5 M*rad/h until 44 Mrad. is reach~d (4.4 :K' 10 6).

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 agency 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 atmosph.ere is.

1.1 x 10 7 TID for 30 days.

The transmitter is mounted on a 2-ft thick' wall very close to 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 radioaetivity will affect the valve).

nul080-0499d-43 527 Rev 1, 10/30/80

Sheet 4 Component General Electric Cables (Codes XZ2, XZ6, 142, 145)

The Franklin Research Center Technical Evaluation Report dated May 30, 1980 addressed deficiencies in the qualification of various equipment at Palisades Plant.

Out of the four cable codes covered by this component sheet, the report addressed Cable Code ~Z2 only, specifically concerning deficiency of submergence qualification.

This cable is qualified for submergence by evaluation of the type tests as discussed in Sheet 2, This evaluation was not part of the previous submittal.

nu0980-0585a-43 130

-, f

0 -

w 0 -

CX>

0 Owner: Consumers Power Company Facility: Palisades EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Docket* 50-255 Date:

ENVIRONMENT DOCUMENTATION REFERENCES OUAUACATION OUTSTANDING EQUIPMENT DESCRIPTION Accident Oual METHOD ITEMS Parameter Accident Qualification System:

Operating 12 Months Section 2, 3 Analysis Miscellaneous Time 30 Days Electrical III.B Plant 1.0. Number:

Temperature Cable Code S04 (OF) 135 250 Section 2, 3 Analysis Component:

II.D. 8 See Note 1 Pressure Manufacturer:

(PSIA) 14.7 14.7 Section 1, 2, 3 Analysis General Electric II. D.8 Model Number:

Relative 100 100 Section 3

!Analysis Humidity (%)

II.D.8 Purchase Order Number:

5935-E-21BC Chemical None j~*

Spray Function/Service:

Transmit Electrical Radiation 1 x 107 7

Signals/Power (Rad) 5 x 10 Section 1

~nalysis II. D. 7 Accuracy:

Spec:

Aging Demo:

40 Years 40 Years Section 2, 3

~nalysis lrcfitlon* ESF Rooms II.D.8 Outs e Containment and Room 123 Submergence Elevation:

Not Subject To Various Submergence Flood level Elevation Above Flood level:

Yes: X No:

(

DOCUMENTATION REFERENCES NOTES

1.

IEEE Transactions Paper by R B Blodgett and R G Fisher 1.

l/C #4/0 AWG 5 kV cable.

on "Insulations and Jackets for Control and Power Cables in Therm~l Reactor Nuclear Generating Stations, 2.

This cable also experiences the effects of high energy June 23-28, 1968.

line break outside of containment, but is not re-quired to operate in this environment.

G-0858-0tA

i'.

-~-- -- -----------------

Owner: Consumers Power Company Facility: Palisades

-- ---- -EOUIPMENT-QUAtiFICATION-REPORT---- - -------*c-.

t-Sh t-N _._

1 omponen ee o..

I-'

0 -*

w 0 -

(X) 0 Docket: 50-255 DOCUMENTATION REFERENCES (cont)

2.

Paper by N D Kenney, T N Mitropoulos and W L Seamonds, "Electrical Characteristics of Butyl Insulation at 125°C," Second Symposium on Butyl Rubber for Wire and Cable Insulations, presented at AIEE Fall General Meeting, October 20, 1961, Sl38~ published June 1962, Pages 3-9.

3.

Paper by JC Carroll and J R'Maher, "Continued Evaluation of Butyl Rubber Insulated Cable,"

Second Symposium on Butyl Rubber for Wire and Cable Insulations," presented at AIEE Fall General Meeting, October 20, 1961, Sl38, published June

1962, Pages 10-13.

Revision:

Date:

NOTES (cont)

G*0858*02

Sheet 2 Component ~~-C_a_b_l_e~C_o_d_e~S_04~~~~~~~~~~~~~~~~~~~~~~~~~

1/C #4/0 Power Cable 5 kV With Butyl Rubber Insulation and PVC Jacket The subject cables are used in Class lE circuits outside the containment.

The qualification is based on the following documents and discussion:

A.

Per Page 534 in Document Reference 1, the butyl insulation can withstand radiation up to 5 x 10 6 R with no change in dielectric property.

This meets the environmental requirements on radiation.

B.

The cable can withstand a dose of 5 x 10 7 R with 20% reduction in dielectric property.

Th.e cable is rated for 5 kV and is conservatively used in a 2.4 kV system.

Thus, for the given operating voltage of 2.4 kV, even with a 20% reduction in dielectric property, dielectric failure is extremely unlikely at 5 x 10 7 R.

C.. Per Document Reference 2, cable with butyl insulation CCiil withstand 125°C (257°F) for four weeks with no change in dielectric property.

Also, the dielectric strength relatively remains constant after exposure*. to air oven aging test at 121 °C for-12 months.

D.

Per Document Reference 2, the physical prope~ty'of the cabie is w;i.thin acceptable limits after exposure to air oven test at 121°C for 28 months continuously-and for 60 month~ *with alternate seven days at room tell)j;>era-ture.

These ~ccelerated aging test parameters far exceed the 40-year life requirement for cable in an environinent where the normal ambient is only 22.2°C (72°F).

This approach is based on the ten degree half life rule per IEEE 101 (1974) and IEEE 117 (1974).

Document Reference 3 also supplements this data where the test was done at 121°C for 293 weeks.

E.

Per Document Reference 3, the cable passed the*-dielectric test after immersion in water for 160 weeks.

F.

No credit has been taken for the jacket furnished.

SUMMARY

1.

Paragraph A provides evidence for radiation qualification.

2.

Paragraphs C and D provide evidence for temperature and aging qualifica-tion.

3.

Paragraph E provides evidence for humidity qualification.

nu1080-0402a-43 130c Rev 1, 10/30/80

- ~*

i Sheet 3 Component Cable Code S04 DORGR j Service Conditions Outside of Containment DORGR 3B Areas Where Fluids Are Recirculated From Inside Containment To DORGR 5 DORGR SA DORGR 6 DORGR 7 DORGR 8

.. Accomplish Long-Term Core Cooling Following a LOCA The requirements for DOR guidelines are met.

As discussed in Sheet 2, the withstand value for the insulation exceeds the temperature and radiation environments at the Palisades Plant.

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

Qualification by Evaluation and/or Analysis Requirements of DOR guidelines are complied with.

The tempera-ture, humidity, radiation and aging qualifications are by analysis based on published test values.

See Sheet 2.

Margin The DOR. guidelines are complied with.

For all parameters, the published test values, based on which the analysis was done, exceed the requirements.

The DOR guidelines are complied with.

As discussed in Sheet 2, the air oven t.est at higher temperature and longer duration meets or exceeds the 40-year life requirement.

Documentation References 1, 2 and 3.

nu1080-0402a-43 130d Rev 1, 10/30/80

Sheet 4 This cable was not included in the November 1978 CP Co submittal and, there-fore, was not addressed in the Franklin Research Center report.

nu1080-0402a-43 130e Rev-1, 10/30/80

t I

. I I

w Owner: Consumers Power Company Facility: Palisades Docket: 50-255 EQUIPMENT QUALIFICATION REPORT Component Sheet No:

Revision:

Date:

ENVIRONMENT DOCUMENTATION REFERENCES QUALIFICATION EQUIPMENT DESCRIPTION Parameter Accident Qualllication Accident System:

Operating Miscellaneous Time Electrical 30 Days 30 Days Sec III.B Plant l.D. Number:

Temperature Cable Codes P08, P09

("Fl 135 345 Sec-II.D. 6 Component:

See Note 1 Pressure Manufacturer:

(PSIA) 14.7 126.7 Sec II.D.6 Okonite Company Modol Number:

Relative Humidity (%)

100 100 Sec II.D.6 Purchase Order Number:

5935-E-22-DC Chemic al Spray

.:None Function/ Service:

'*~

Transmit Electrical Radiation IRadl 7

2 x 108 Signals/Power 1 x 10 Sec II. D. 7 Accuracy: Spec:

Ag!ng Demo:

Location: m;F Rooms 40 Years Plus LOCA 40 Years Plus LOCA Sec II.D. 8 Outside Containment

(~O~atlon:

Submergence Not Subject Various to Submergence Flood Level Elevation Above Flood Level:

Yes: X No:

DOCUMENTATION REFERENCES

1.

Letter date.d J"une 4, 1979 from T A Kommers of Okonite.

L Electrical cables -

Company to J Griffith of Bechtel (San Francisco).

Electrical cables -

Ouel 2

1, 2 2

2 1, 2 1, 2 NOTES 3/c 1/8, 7 l/c /18, 7 OUTSTANDING METHOD ITEMS Test and Analysis Test and Analysis

.Lt:!8L auu Analysis Test and Analysis Test and Analysis Test and Analysis strand cable.

strand cable *..

\\.,

G*Ofl5A-Ot A i:*

~

...

ML18045A852

Text

SUMMARY

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