Text

Forwards Info Re Findings Identified by NRC During Environ Qualification Insp Conducted During Wk of 871019,per 871029 Discussions Between a Johnson & K Petersen.Addl Info on Raychem Splices Also Encl
	ML20236Y234
Person / Time
Site:	Wolf Creek
Issue date:	11/20/1987
From:	Withers B; WOLF CREEK NUCLEAR OPERATING CORP.
To:	Martin R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	WM-87-0309, WM-87-309, NUDOCS 8712110189
	Download: ML20236Y234 (90)
	v • d • e

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LF CREEK W@ NUCLEAR OPERATING Bart D. Wuhers l.

P,eeld.nt and

. cni.e ex.cutiv. ome.'

November 20, 1987-j WM 87-0309 Mr. R.. D. Martin, Regional ' Administrator ij i

U.'8. Nuclear Regulatory Commission.

I l-Region IV NOV 2. 71987

..!j1 611 Ryan Plaza Drive, Suite 1000

. Arlington, Texas 76011

__M

Subject:

Docket No 50-1882:

Environmental Qualification Inspection l

Dear Mr. Martin:

The attachment to this letter provides information concerning the finding 8 l

identified by the NRC during the Environmental' Qualification Inspection i

conducted at Wolf Crsek Generating Station the week of October 19, 1987.

It is being provided.as.a result of discussions.on October 29, 1987 between Mr. A.. Johnson of.MRC Region IV and Mr.

K.

Petersen of Wolf Creek Nuclear Operating Corporation.

Additional information on'Raychem splices is' also being provided as requested in discussions'between Mr. A. Johnson and Mr.'K.

Petersen on November 13, 1987.

l If you have any questions concerning this submittal, please contact me or Mr. O. L. Maynard of my staff.

Very truly yours, l

2 i

A Bart D. Withers G

President and l

Chief Executive Officer BDW/jad 1

Attachment

'l ocs J. E. Cummins (NRC), w/a j

A. R. Johnson (NRC), w/a J

. W. O'Connor (NRC), 2 w/a j

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j9 PO. Box 411/ BurHngton, KS 66839 / Phone: (316) 364-8831 1-h i

.,, ne.~,.,., mcm

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Attachment to WM 87-0309 Page 1 of 89 November 20, 1987 WOLP CREEK NUCLEAR OPERATING CORPORATION WOLP CREEK GENERATING STATION DOCKET NO. 50-482 ADDITIONAL INFORMATION CONCERNING l

NRC ENVIRONMENTAL QUALIFICATION INSPECTION PINDINGS i

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Prepared by:

K. R. Petersen D. R. Prichard t

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i Attachment to WM 87-0309 l

Page 2 of 89 i

November 20, 1987 i

l Contents l

Responses to NRC Environmental Qualification 3

j Inspection Findings

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Additional Information Concerning Raychem Splices 19 References 20 Appendix A Justification for Continued Operation 22 Limitorque Operators Appendix B Justification for Continued Operation 58 Dual Voltage Limitorque Operators l

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Attachment to WM 87-0309 Page 3 of 89 November 20, 1987 RESPONSES TO NRC ENVIRONMENTAL QUALIFICATION INSPECTION PINDINGS FINDING 1A The documented configuration in the Equipment Qualification Work Package (EQWP)

E-01013 for Raychem splice installation did not match field installation.

The bend radius of some Raychem splices was less than the allowable bend radius of 5 times the splice 0.D.

as documented in EQWP E-01013 RESPONSR TO PINDING 1A Wyle Laboratories Qualification Test Report No.

17859-02P (Reference 1) documents the testing of a number of configurations of splices from various suppliers.

Included in this test were Raychem WCSF-N splices with seal length significantly less than 2 inches (as little as 1/2 inch seal length on some test samples) and bend radius to approximately 1.2 times the 0.D of the splice.

This report was obtained through membership in the Nuclear Utility Group on Equipment Qualification (NUGEQ) and has not been included in this letter.

However, it is available for review at WCGS.

The Raychem splices were aged by Arrhenius method to greater than 40-years life at the WCGS maximum ambient temperature of 120 P.

Irradiation to a level of 200.09 megarade gamma, using a Cobalt 60 source, envelops the maximum WCGS 40-year normal plus accident total integrated dose of 199.2 megarada.

The accident test temperature and pressure profiles envelop with margin the WCGS LOCA temperature profile and the LOCA and MSLB pressure profiles.

The WCGS MSLB temperature profile exceeds the tes; temperature profile for a short period of time (about 300 seconds).

However, the peak surface temperature of the Raychem splices during an MSLB is expected to be approximately equal to the peak surface temperature for cable during an MSLB (342 o F) as indicated in USAR Pigure 3.11(B)-7A.

The peak test temperature 0

(362 F) exceeds with margin the peak surface temperature of the Raychem splice during an MSLB.

Chemical spray with boron concentration of 3000 ppm and pH of 10.5 was applied for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during the accident test.

The test spray boron concentration exceeds the WCGS spray boron concentration of 2050 ppm.

However, at WCGS, the normal spray pH during the injection phase (less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) is 9.5 to 10.5 and could reach a pH value of 11.0 pH for 1 minute i

during the initial stage.

Assuming a single failure in the containment l

spray system, this period could last up to 30 minutes.

For the remainder of the recirculation phase (23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ),

the spray would have a pH range of 8.0 to 9.0.

Since the effects of chemical corrosion are related not only to pH

e Attachment to WM 87-0309 Page 4 of 89 November 20, 1987 magnitude but also to duration of exposure, the test exposure at a pH value of 10.5 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months adequately demonstrates the corrosive effects that would be imposed on the splices by the WCGS containment spray system.

ExtrapolationbgArrheniusmethodshowsthataccidenttestingextendedto46 hours at 250 F qualifies the aplices to more than 6 months during post-l accident conditions.

Leakage current measurements for the tested splices were recorded during the accident testing.

No measdrable leakage currents were obtained during the accident testing for those Raychem splices qualified by this testing which are conservatively representative of the installations at WCGS relative to seal length and bend radius.

Anomalies which occurred during the test were related to test specimens l

which are not representative of splices installed at WCGS.

It is concluded that Wyle Test Report No.

17859-02P satisfactorily demonstrates qualification for Raychem WCSP-N splices with seal length less than 2 inches (down to 1/2 inch) and bend radius outside of the Raychem installation criteria (down to approximately 1.2 times splice 0.D.).

The bend radii lese than 5 times the 0.D.

were due to the small physical sice of the terminal boxes for transmitters.

A calculation based on conformance of the Raychem splices to the inside dimensions of the terminal boxes yielded the smallest bend radius configuration at WCGS to be approximately 1.43 times splice 0.D.

EQWP E-01013 will be revised to reflect the test report results and the results of other ongoing programs addressing Raychem splices as appropriate prior to January 1, 1988.

FINDING 1B 1

The documented configuration in the EQWP E-01013 for Raychem splice installation did not match field installation.

The Raychem splice seal length was less than the required seal length of 2 inches as documented in EQWP E-01013 RESPONSE TO PINDING 1B W le Laboratory Qualification Test Report No.

17859-02P (Reference 1) y satisfactorily demonstrates the environmental qualification for Raychem WCSP-N splices with seal length as short as 1/2 inch.

This test report is I

summarized in response to Finding 1A.

Valkdown of approximately 150 of the Raychem splices in harsh environments revealed one splice with a seal length less than 1/2 inch which has been replaced.

Evaluation of the previously installed configuration is being conducted in accordance with station procedures.

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Attschment to WM 87-0309 Page 5 of 89 November 20, 1987 FINDING 10 The documented configuration in the EQWP E-01013 for Raychem splice installation did not match field installation in that adhesive was either missing or not visible from the end of the shrink tubing as required by the qualification documentation.

RBSPONS8 TO PINDING 10 i

A walkdown of approximately 150 of the Raychem splices in harsh environments revealed two splices that had adhesive missing from the end of the shrink tubing and two splices were identified as not having the tubing fully shrunk.

In addition, one splice was missing a shim.

The splices have been replaced.

Evaluation of the previously installed configurations are being conducted in accordance with station procedures.

PINDING 2 The documented configuration of Minco resistance temperature detectors (RTDs) in SQWP ESE-42A does not match the installed configuration.

EQWP ESE-42A documents that the terminal boxes used as splice boxes for Minco RTD cables in the Reactor Vessel Level Instrumentation System are located above maximum postulated containment flood level, however, not all of the terminal boxes are mounted above flood level.

The EQWP does not document qualification for subnergance of the terminal boxes.

RESPONSE TO FINDING 2 The terminal boxes have been re10cated above flood level consistant with configuration documented in EQWP ESE-42A.

Evaluation of the previously installed configuration is being conducted in accordance with established station procedures.

j PINDING 3A Limitorque EQWPs fail to addreso compartment aging and degradation caused by j

existing space heaters located inside Limitorque motor operator limit switch compartments.

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Attachment to WM 87-0309 Page 6 of 89 November 20, 1987 RESPONSE TO PINDING 3A Limit switch compartment space heaters in Limitorque operators located inside containment will be removed prior to restart from the current refueling outage. In addition, a portion of limit switch compartment space heaters located in Limitorque operators outside containment will be removed, as time and schedule permits, prior to restart from the current refueling outage.

The remaining space heaters will be removed in conjunction wi th scheduled maintenance on the valves throughout cycle 3 All Limitorque limit switch compartment space heaters will be removed prior to restart from Refuel 3 During this work effort, the compartments will be examined for signs of aging and degradation.

Any problems found will be evaluated for effects on the operation of the Limitorque operator and any necessary actions will be taken.

A justification for continued operation with some compartment space heaters installed and energized is provided in Appendix A.

FINDING 3B The Limitorque EQWPs fail to address the safety classification of the space heaters located inside Limitorque operators.

In addition, the potential effects on the Limitorque operator due to the space heater Class 1E power supply is not documented in the EQWP.

RESPONSE TO PINDING 3B Information pertaining to the classification of the space heaters and potential effects on the Limitorque operator due to the space heater Class 1E power supply is provided in Appendix A.

PINDING 30 The Limitorque EQWPs should be revised to includo qualification documentation for the Limitorque space heaters.

RESPONSE TO PINDING 30 As stated in response to Finding 3A, all Limitorque limit switch compartment space heaters will be removed prior to restart from Refuel 3 Qualification documentation for the Limitorque space heaters in the EQWPs is no longer a concern.

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Attachment to VM 87-0309 Page 7 of 89 November 20, 1987 l

The limitorque EQWPs will be revised to reflect the new configuration (without space heat,ers) prior to January 1, 1988.

I PINDING 4 Limitorque EQWPs do not contain environmental qualification documentation for the nylon crimp terminals used on dual voltage Limitorque motors.

Licensee should clarify qualification documentation.

RESPONSE TO PINDING 4 1

A qualification test for Thomas & Betts (T&B) nylon crimp terminals used in 1

dual voltage Limitorque operators is being performed by Wyle Laboratories.

The qualification test is applicable to WCGS.

An 8-year intermediate qualification test for T&B terminals was completed successfully in late October, 1987 with a summary scheduled for issuance late November, 1987.

A 40-year qualification test is being conducted and is scheduled for completion and issuance of a final test report early in 1988.

The results of the test program will be incorporated in EQWP HE-4 and the BOP Limitorque EQWP to document the qualification when the final test report is issued.

In the interim, a justification for continued operation with T&B nylon crimp terminals installed is provided in Appendix B.

FINDING S Limitorque EQWPs do not adequately demonstrate the qualification of the motors on Limitorque operators in undervoltage conditions.

Licensee should clarify qualification.

RESPONSE TO PINDING S Operation of Limitorque valve operators at 10% reduced voltage is taken into consideration by Limitorque when sizing the operator.

During normal sizing for a reduced voltage application, the motor size is increased to provide the required motor torque at the reduced voltage.

In addition, limitorque I

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s Attachment to WM 87-0309 Page 8 of 89 November 20, 1987 in qualification test B0212 (Reference 2) subjected the test actuator to degraded voltages and frequencies with no effect on actuator performance.

The results of the test are documented in the Limitorque EQWPs.

The normal operator sizing performed by Limitorque along with the successful testing at degraded voltage and frequency of Limitorque test B0212 provides adequate assurance of qualification at degraded voltages.

In addition to the environmental qualification concern noted above, a separate evaluation is being performed to determine the operator capability at a reduced voltage for the Limitorque operators qualified by EQWPs HE-1, HE-4 and B0P Limitorque.

The available thrust or torque for each qualified operator at 80% voltage (a value 10% beyond the tested reduced voltage) as compared to the required thrust or torque for each operator based on system parameters will be evaluated.

The schedule for completion of this task is March, 1988.

Results to date are provided in Table 1.

PINDING 6 EQWP E-028 contains Wyle Test Report 45603-1 for Marathon 1600 terminal blocks which documents an anomaly concerning blowing of fuses when the circuit was re-energized following a loss of power.

The EQWP does not address the anomaly and its affect on the qualification of Marathon 1600 terminal blocks.

RESPONSE TO PINDING 6 Anomaly #6 in Wyle Test Report 45603-1, (Reference 3,

page 4 of 330) discussed blown fuses in the leakage current circuit of the 132 VAC and 264 VAC circuits.

Due to the following, these fuse failures are not applicable to WCGS:

- The Marathon 1600 blocks are used in 125 VDC and 120 VAC circuits at WCGS. This eliminates the concern of the 264 VAC circuit failure in the Wyle test.

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- The test setup, shown in Figure 2 of the report, applied voltage and i

current to a serpentine arrangement and measured total leakage current from 6 terminal blocks to ground, of which 4 of the blocks are not used at WCGS.

Because of this test setup, it is not possible to determine positively the source of the leakage current, whether from the 1600 series, 1500 series or 142 series blocks.

Since the source of the leakage current is indeterminant, it is not possible to take credit for either the failure or success of this LOC A test, in regard to the 1600 series terminal blocks.

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Attachment to WM 87-0309 Page 9 of 89 November 20, 1987

- Th9 132 VAC terminal blocks in the test were allowed 12 amps leakage

current, and were fused slightly larger (page 175 of the W le l

y report).

Note the leakage current was a summation of the leakage from 54 possible paths to ground, or 0.222 amps per path.

Although discussion of the anomaly states that a voltage surge upon reapplication of power caused the fuses to blow, per discussion with Wyle Labs, the fuses were not examined during the power outage, but were only discovered to be blown upon restoration of power. Because of this, it is highly probable the fuses blew upon loss of power, when the essential instantaneous collapse of the field in the inductive voltage transformer (and current transformer which was carrying 33 amperes) generated high voltage levels (i.e.

V:fidt) which led to the fuse blowing anomaly.

At WCGS, the Marathon 1600 terminal blocks are used in either 125 VDC circuits or 120 VAC circuits of limited current.

For example, a typical circuit at WCGS is the BB-ZS-8702AA limit switch which is used as an interlock for assuring that the RHR loop 1 inlet isolation valve is closed before the containment sump to RHR pump suction isolation valve can be opened.

The limit switch (and therefore the Marathon 1600 terminal block) has current flow only when the sump to RHR pump suction valve is opening and even at that time, the continuous current draw is only 0.185 ampere. Note the circuit is fused at 2 amperes.

Further justification for the acceptability of Marathon 1600 terminal blocks for WCGS applications (with power being cycled) is contained in Wyle Test Report 17657 (Reference 4).

Although paragraph 2 3.1 states that voltage on I

test circuits 1, 2,

4 and 5 remained constant during the test, what was meant is that the voltage was maintained at a steady level "while it was l

being applied".

This is in contrast to circuits 3 and 6 which had their l

voltage varied during the test.

As noted in paragraph 2.3.4 and in Figures II-9, II-10, II-33 and II-34 for the Marathon 1600 blocks switches 02 and S3 were initially opened at the start of the LOCA, closed at 25 seconde into the LOCA, opened at 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and finally closed at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months into the LOCA.

The test configuration, which is essentially identical to the WCGS solenoid configuration, performed acceptably during the test.

Note that coils in the solenoid circuits, due to their inductive nature, would be more likely to cause surge problems than pure resistive loads, therefore, the acceptable l

results for these circuits are also applicable to non-inductive loads. Wyle Test Report 17657 is proprietary, therefore it is not included in this letter.

However, it is available for review at WCGS.

i EQWP E-028 will be revised prior to January 1,

1988 to reflect this in fo rma tion.

FINDING 7A Equipment Evaluation Worksheet (EEW) of EQWP ESE-49A includes an accuracy requirement of +10%.

EQWP should clarify the 10% accuracy requirement.

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s Attachment to WM 87-0309 Page 10 of 89 November 20, 1987 RESPONSE TO 7A A 10% accuracy requirement documented in EQWP ESE-49A is inconsistent with the intent of the test and should not have been included in the report.

The EQWP will be revised to delete the 10% accuracy requirement prior to January 1,

1988.

FINDING 7B A test report in EQWP ESE-49A on RVLIS hydraulic isolator documents a problem with qualification of the hydraulic isolator for harsh environment applications.

RESPONSE TO PINDING 7B The Barton differential pressure indicating switch (DPIS) is qualified only for hydraulic isolation as documented in EQWP ESE-49A.

The switching mechanism of the DPIS does not perform a safety-related function and is not qualified for harsh environment applications at WCGS.

FINDING 70 Performance requirements for the RVLIS hydraulic isolator documen ted in EQWP ESE-49A do not address sensing line errors.

RESPONSE TO PINDING 70 The performance requirements, Section 3.2 of Reference 7, address the performance of the DPIS as a hydraulic isolator.

It includes sensing line errora and consideration for use of the DPIS in other applications (where its switching function is utilized).

Reference 5 is included in EQWP ESE-49A.

PINDING 7D EQWP ESE-49A test report for RVLIS hydraulic isolator did not include performance data.

RESPONSE TO 7D Cons!. stent with Reference 6, data taken during the qualification testing of the DPIS is ave 'lable for audit at Westinghouse. This data was recorded via strip chart recorders.

Due to the voluminous esture of the raw data and the fact that most of the data taken was to be used to support qualification of the DPIS in other applications, the data was not included in the report.

The summary statements found in Section 7.0 of Reference 5 are based on review of the test data.

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Attachment to WM 87-0309 Page 11 of 89 November 20, 1987

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l Data relevant to DPIS performance as a hydraulic isolator was taken from the output of the differential pressure (DP) transmitter in Loop B of Figure 6 (Reference 5).

A non-zero output from the DP transmitter would indicate the l

occurrence of sensing line errors unique to either of the Loop B test l

specimens.

Additionally, the DPISs were examined for evidence of loss of i

pressure boundary integrity.

PINDING 7E Licensee should provide an auditable link between the tested and installed configuration of the RVLIS hydraulic isolator.

RESPONSE TO PINDING 78 Investigation into this finding revealed a documentation inconsistency. The Equipment Qualification Data Package (Reference 7) documents the testing of Barton DPIS Model 581-4 whereas the Equipment Qualification Test Report (Reference 5) and EQWP ESE-49A documents Model 581.

The hydca"lic isolator of both Model 581 and Model 581-4 is identical.

Improvements male by Barton in the switching mechanism are incorporated in Model 581-4.

Westinghouse has confirmed that Barton DPIS Model 581-4 was tested.

EQWP ESE-49A will be revised to reflect the correct model number prior to January 1, 1988.

The installation of Barton DPIS Model 581-4 was field verified.

l PINDING 7P The test?d configuration of the RVLIS hydraulic isolator as documented in EQWP ESE-49A did not match the installed configuration.

RESPONSE TO 7F The test configuration typifies the plant-installed configuration for the equipment tested.

As a hydraulic isolator, the DPIS is located in the sensing line between a transmitter and the process measured.

For measurement of pressurizer level (RVLIS function), two DPISs are used; one each in both of the transmitters process connections, as shown in Reference 5, Figure 6 (see Loop B).

In responding to this finding, an error in Reference 5, Section 3 2, page 5 was discovered.

With regard to Section 3 2, the first sentence of the second ytragraph should read as follows:

"During the test, adherence to this requirement is verified by monitoring the output of the reference transmitter receiving the pressure signal (see Figure 6, Loop B)".

EQWP ESE-49A will be revised to reflect this information prior to January 1,

1988.

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Attachment to'WM 87-0309 Page 12 of 89 November 20, 1987 The purpose of the Loop A test configuration was to gather performance data relevant to the DPISs performance in other applications. It was intended to l

confirm that process variable measurement by the DPIS was independent of l

variations in process fluid volume.

The data taken for this configuration was via the indicating switch electrical output and, therefore, is considered to be relevant to the DPIS's performance of functions other than l

as a hydraulic isolator.

FINDING 8A EQWP ESE-10 documents a design modification made to Tobar transmitters as a l

result of environmental qualification testing.

Licensee should verify that the modification was incorporated on the Tobar transmitters installed at WCGS.

RESPONSE TO PINDING 8A The modifications which added silicon to the Veritrak Model 76PH2 transmitters qualified by WCAP-8687 Supplement 2-E01B Revision 1 (Reference

8) was incorporated in all Westinghouse-supplied Tobar transmitters.

In

addition, transmitters provided by Tobar directly to end users are also qualified to the same test report, i

PINDING 8B E04P ESE-10 documents the testing of Tobar transmitter model number 32PA1/32PG1.

The installed model number documented on the data plate is 32PA1212-84002.

Licensee should clarify the difference.

RBSPONSE TO PINDING 8B j

i Westinghouse and Tobar have verified that the 32PA1 refers to the j

transmitters series (i.e.

a Nuclear, absolute pressure, "A" qualification J

1evel transmitter) while the additional numbers refer to application / range

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specific information.

Hence, the qualification test for 32PA1/32PG1

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transmitters is applicable to the field installed transmitters.

EQWP ESE-10 will be revised to clarify the model number prior to January 1,

1988.

PINDING 9 WCGS utilizes Kulka terminal blocks in control circuits inside containment.

EQWP E-035B for Kulka terminal blocks does not address justification for use of the blocks in control circuits.

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i Attachment to WM 87-0309-I Page 13 of 89 November 20, 1987 l

r RESPONSE TO PINDING 9 Kulka terminal blocks located in the electrical penetrations and terminal boxes are qualified by E04P E-035B.

They are t; sed in the control circuits l

of inside containment safety-related equipment qualified,tr the follpwing l

EQWPs:

HE-1 (Limitorque Operators), HE-2 ( ASCO Val.ves)/ lAF-10A (Target liock Valves), J-603A (Valcor Valves), M-237 (Bettis Actuato rO and 30P Limitorque (which includes M-223A, M-2230, M-224B, M-225, M-2310' ana M-237 (Limt*Arquo only)). A total of 76 plant components are involved.

O The Conax Qualification Report on Kulka Terminal Blocks (Re feren'ca 9) documents a maximum leakage current of 0.16 milliamps at 539 volts'during LOCA testing.

The effects of this leakage current have been evaluttod for the equipment noted above.

Limitorque operators (EQWP HE-1 and BOP Limitorque EQWP):

The motor starters for the Limitorque operator are either l ho 1 or size 2'.

Size f,.,

the worst case, requiren 1.26 ampere to pick up lts coil, and draws 0.165 ampere during continuous. operation.

Leakage cum entn of 0.16 milliamp, (o r 0.00016 ampere) will not affect the operation of the ntarter coils.

9-f ASCO Series 8316 Control Valves (EQWP HE-2):. ASCO series 8316 contrS1 valves have power removed free them on a containment isolation sign K.

Therefore leakage current during an accident condition is not a concern.

I Target Rock 79AB Series _ Control valves (EQWP HE-10A):

These' solenoid -

valves, which are used in head vent, excess letdown and accumulator vent applications, draw 0.8 amps at 125VDC.

Leakage currents of 0.16 milliamps

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will have no affect on these valvos.

Bettis Actuators (E0WP M-237):

Bettis actuators control the containment minipurge isolation valves.

Thu isolation valves a n closed by removing power from ASCO solenoid valves Mich are appurtenances,to the Settis actuators.

Since power is removed from tne ASCO valves during recident conditions (similar to the EQWP HE-2 ASC0 valves) leakage correnu during accident conditions are not,a concern.

t Valcor 52600 Series Control Valves (EQVP J-603A):

These valves are used as

peocess cample line valves and as containment isolation valves.

Per Inatraction Manual J603A-00000 for these valves, the solenoids draw 1.5 s

ampere at 120VAC.

Im kage; current of 0.16 milliamps will not affect the operation of these valves.

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.In summary, the leakage currents of Kulka terminal blocks qualified by E AP j

E-035B are sufficiently small during LOCA conditions so'as to not affect A safety-related control circuits inside containment at VGS.

EQ4P E-935B will be revised to reflect this information prior to January 1,

1938.

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l Attachment to WM 87-0309 Page 14 of 89 l

November 20, 1987

,PINDING 10 Main Peedwater Isolation Valves (MPIV) were leaking oil.

Licensee should investigate the possible damage to other MPIV equipment.

RBSPONSE TO PINDING 10 The oil used in the MPIVs is Pyrquel EHC, a fire resistant hydraulic fluid manufactured by Stauffer Chemical Company.

Due to fluid leaks in the MSIVs and MPIVs, an extensive analysis was performed in 1985 which included an examination of the safety-related components on and near the MSIV/MPIVs for any harmful effects which could have been caused by contact with the Pyrquel oil.

Also included in the analysis was technical information provided by Stauffer regarding the compatibility of the Pyrquel oil with commonly used materials.

The result of this analysis demonstrated that the safety-related materials used in the MPIV/MSIVs or in the area of the MSIV/MPIVs which could be exposed to the Pyrquel oil are compatible with it.

Note that the coating on the flex conduit does not serve a safety-related function.

The conduit connections and the terminal boxes to which they attach are not environmentally sealed, so the degradation of the coating due to its noncompatibility with Pyrquel oil does not constitute a safety concern.

PINDING 11 Coil housing on ASCO valve EM-HY-8964 w..a excessively loose.

Licensee should repair.

RESPONSE TO PINDING 11 The top of the solenoid and spring en valve EM-HY-8964 have been replaced.

l The excessive looseness of the housing is considered an isolated case.

The housing on ASCO valves are typically loose to some degree, however, this does not affect the operability of the valves.

PINDING 12 Licensee should investigate whether repair on a Limitorque operator EM-HV-8821A had been evaluated as acceptable.

A wire with smashed insulation was apparently repaired using black electrical tape.

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Attachment to WM 87-0309 Page 15 of 89 November 20, 1987 t

RESPONSE TO PINDING 12 Ir.v9stigation revoaled an open work request on EM-HV-8821A.

Du ring the vctve inspection 10/10/87, a motor lead was f$und to have damaged lusufation j

with bard coppe :. showing.

A revleien to the work request was issued 10/12/87 to replace the damaged motor lesi; Pending completion cf the

repair, bladk electrical tape was wrapped around the damaged wire for personnel safety.

2' FINDTgG 13

,i S h'e licensee had written work requests to change out grease on EJ-HV-8804A

',and EJ-HV-8804B Limitorque operators.

The work requests were to be done in 4

' ' ' conjunction with other work activities pending on the valves yet-to be scheduled.

Licensee should ensure that grease 2teange out is completed.

RESPONSE TO PINDING 13 Grease change out on the identifie1 Limitorque operators will be completed prior to startup from the current refueling outase.

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FINDINC 14 Containment sump level transmitter LF-LE-9A had a loose splice box connection which was leaking fluid.

Licensee should repair.

RESPONSE TO FINDING 14 Repair on transmitter LF-LE-9A has beerscompleted.

Similar splice lores will be inspected and repaired, if required, prior to'startup from the current refueling oute.ge.

,e PINDING 15

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i Procedure KGP-1311 Reviaion 0 controls licensees prog ram on handling industry technical inforna tion such as IE Info nta tion No cices,

INPO Significant Operating Experience Reports and NSSS Tect nical Bulletins.

The person responsible for initial screening of tr e Ir,G ds try ' Technical Tcformation Program (ITIP) document is not required to have environmental qualification training.

RESPONSE TO PIND1NG 15 Environmental Qualification training will be provided to personnel performin6 initial screening of ITf? documents by June 30, 1988, f

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r-.

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I Attachment to WM 87-0309 l

Page 16 of 89 4

November 20, 1987 j

l i

i FINDING 16 The licensee has not documented the qualification of equipment affected by main steam line break (MSLB) outside containment with superheated steam in the associated Equipment Qualification Work Packages.

RESPONSE TO PINDING 16 I

Analysis results have been presented to the NRO which documents that the equipment which is exposed to the environmental conditions of an MSLB with superheat effects in the steam tunnel which must function to mitigate the postulated MSLB event and/or to bring the plant to a safe shutdown condition will perform its safety function in the environmental conditions following an MSLB including superheated steam effects.

This analysis documented in Reference 10, 11, and 12 is currently under review by NRR.

l l

l w_-___-____-_---_

Attachment to WM 87-0309 Page 17 of 89 November 20, 1987 j

TABLE 1 UNDERVOLTAGE OPERATION OF LIMITORQUE OPERATORS NSSS SCOPE - INSIDS CONTAINMENT I

REQUIRED OPERATOR OPERATOR CAPABILITY VALVE NUMBER THRUST AT 80% VOLTAGE BB-HV-8000A 13,911 LES 18,630 LBS BB-HV-8000B 13,911 LBS 18,002 LBS NSSS SCOPE - OUTSIDE CONTAINMENT REQUIRED OPERATOR OPERATOR CAPABILITY VALVE NUMBER THRUST AT 80% VOLTAGE BG-HV-8105 14,695 LBS 19,092 LBS BG-HV-8106 14,695 LBS 18,912 LBS BG-HV-8110 10,900 LBS 42,150 LBS BG-HV-8111 10,900 LBS 42,150 LBS BG-LOV-0112B 7234 LBS 14,655 LBS BG-LOV-0112C 7234 LBS 13,738 LBS BN-HV-8806A 7234 LBS 14,152 LBS BN-HV-8806B 7234 LBS 13,704 LBS BN-HV-8813 10,900 LBS 42,150 LBS BN-LCV-0112D 7234 LBS 14,225 LBS BN-LCV-0112E 7234 LBS 12,580 LBS EJ-HV-8811A 13,478 LBS 41,031 LBS EJ-HV-8811B 13,478 LBS 41,203 LBS EM-HV-8801A 13,119 LBS 19,307 LBS EM-HV-8801B 13,119 LES 18,670 LBS EM-HV-8803A 13,119 LBS 19,039 LBS EM-HV-8803B 13,119 LBS 15,789 LBS EM-HV-8814A 10,900 LBS 42,150 LBS Di-HV-8814B 10,900 LBS 42,150 LBS EM-HV-8821A 15,712 LBS 19,205 LBS EM-HV-8821B 15,712 LBS 19,345 LBS EM-HV-8835 6,068 LBS 13,407 LBS EM-HV-8923A 5,782 LBS 7,678 LBS EM-HV-8923B 5,782 LBS 7,677 LBS

Attachment to WM 87-0309 Page 18 of 89 November 20, 1987 TABLE 1 (Continued)

BOP SCOPd - INSIDS CONTAINMENT Required Operator Operator Capability Valve Number Thrust or Torque At 60% Voltage BB-HV-0013 8364 LBS 18,545 LBS BB-HV-0014 8364 LBS 18,545 LBS BB-HV-0015 8364 LBS 18,545 LBS BB-HV-0016 8364 LBS 18,545 LBS EF-HV-0033 8549 IN-LBS 21,222 IN-LBS EF-HV-0034 8549 IN-LBS 21,222 IN-LBS EF-HV-0045 8549 IN-LBS 21,222 IN-LBS EF-HV-0046 8549 IN-LBS 21,222 IN-LBS EG-HV-0060 6036 LBS 18,382 LBS EG-HV-0062 7215 LBS 18,115 LBS GS-HV-0020 1110 IN-LBS 2361 IN-LBS KA-HV-0030 2420 LBS 6637 LBS LP-PV-0095 1340 LBS 13,773 LBS BOP S00PE - OUTSIDE CONTAINMENT Required Operator Operator Capability Valve Number Thrust or Torque At 80% Voltage BN-HV-0003 2480 LBS 7288 LBS BN-HV-0004 2480 LBS 7288 LBS l

EF-HV-0031 8549 IN-LBS 21,222 IN-LBS EF-HV-0032 8549 IN-LBS 21,222 IN-LBS EF-HV-0047 4118 IN-LBS 8489 IN-LBS i

EF-HV-0048 4118 IN-LBS 8489 IN-LBS EF-HV-0049 8549 IN-LBS 21,222 IN-LBS EF-HV-0050 8549 IN-LES

'1,222 IN-LBS EG-HV-0058 6036 LBS

,J,382 LBS EG-HV-0059 6036 LES 18,382 LBS j

EG-HV-0061 2018 LBS 6833 LBS l

EG-HV-0071 5777 LBS 13,296 LBS

)

l EN-HV-0001 2910 LBS 9,027 LES l

EN-HV-0006 7840 LBS 14,774 LBS 1

EN-HV-0007 2910 LBS 9,027 LBS 1

EN-HV-0012 7840 LBS 14,774 LBS l

EN-HV-0015 890 LBS 3630 LBS EN-HV-0016 890 LBS 3630 LBS j

GS-HV-0021 1110 IN-LBS 2361 IN-LBS j

KC-HV-0253 2236 LBS 6833 LBS l

LP-HV-0105 3619 LBS 6834 LBS LF-H V-0106 3619 LBS 6834 LBS 1

(

Attachment to WM 87-0309 Paga 19 of 89 November 20, 1907 ADDITIONAL INFORMATION CONCERNING RAYCHEM SPLICBS In the process of reworking Raychem splices to address the findings identified in the EQ inspection, some Raychem splices appeared to be installed in a

manner different from manufacturer's instructions.

Destructive examination revealed that the installed configuration differod from the configuration detailed in the product installation guide in that the Raychem tubing was too small for the size of bolted connection used.

WCN00 reported this condition on November 18, 1987 pursuant to 10 CPR 50.72.

The Licensee Event Report or its supplement, if necessary, will contain a detailed description of the condition, root cause and the corrective actions.

I Raychem splices are utilized in three areas:

instrumentation circuits, control circuits and power circuits.

- Instrumentation Circuits:

A 100% walkdown of Raychem splices on instrumentation circuits is being conducted to verify that the Raychem splices are acceptable per Raychem recommendations.

- Control Circuits:

A large bolted configuration which utilized too small sizing of Raychem tubing was qualified as documented in Wyle Test Report 17859-02B (Reference 13).

A leakage current of 13 mil 11 amperes was measured during the test.

Due to the leakage

current, the results of the test are applicable only to the control circuits at WCGS.

A copy of Test Report 17859-02B was obtained through membership in the Nuclear Utility Group on Equipment Qualification and has not been included in this letter.

However, it is available for review at WCGS.

A sample plan bar / on the total population of Raychem splices in control circuit is being developed.

An acceptance criteria based on the Wyle Laboratories tested configuration described in Reference 13 will be utilized to determine the acceptance of the control circuit splices.

- Power Circuits:

Power circuits have been determined to be outside the scope of this program since the power circuit terminations were qualified in a different configuration.

Plant personnel who have been trained in the correct installation of Raychem splices will be performing the inspec tions as well as replacing those splices that are not acceptable.

Attachment to WM 87-0309 Page 20 of 89 November 20, 1987

References:

p 1.

" Qualification Test Program on Raychem Nuclear Cable Splices, Okonite Tape Splices, and Kerite Splices as Installed on Various Wire Insulations at Commonwealth Edison Company's Zion, Byron and Braidwood Nuclear Generating Stations", Wyle Laboratories Test Report No. 17859-02P, Revision A 2.

" nuclear Power Station Qualification Test Report in Limitorque Valve Actuators with Type LR Motor for Westinghouse PWR", Report No. B0212, April, 1985 3

Wyle Laborato:Les Test for Marathon Special Products, Report No. 45603-1, February 18, 1982.

4.

" Measurement of Leakage Current on Marathon Series NUC 1600, 1600DJ and 6000DJ Terminal Blocks During a loss of Coolant Accident for Commonwealth Edison Company", Wyle Laboratories Test Report No. 17657, December 21, 1983 5.

"Bquipment Qualification Test Report: Differential Pressure Indicating Switch - Group A (Environmental and Seismic Testing)", WCAP-8687 Supplement 2-E49A, Revision 1 (Proprietary).

6.

Federal Register (48 FR 2729) January 21, 1983, Final Rule on

" Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants", Item 9 of " Comments On The Proposed Rule".

7.

"Bquipment Qualification Data Package:

Differential Pressure Indicating Switch - Group A", WCAP-8587, Supplement 1, EQWP-ESE-49A, Revision 1 (Non-Proprietary).

8.

" Equipment Qualification Test Report: Veritrak Pressure Transmitters-Qualification Group A", WCAP-8687, Supplement 2, E01B Revision 1 (Proprietary) 9 Conax Qualification Test Raport on Kulka Terminal Blocks, Document Number IPS 675, 1981

10. Letter SLNRC 86-06 dated April 4, 1986 from N. A. Petrick, SNUPPS, to H. R. Denton, NRC

Attachment to VM 87-0309 f

Page 21 of 89 November 20, 1987 l

l

11. Letter ET 87-0070 dated February 20, 1987 from J. A. Bailey, VCN00, to NRC-i l

12. Letter VM 87-0253 dated October 2, 1987 from B. D. Withers, WCNOC, to NRC.

I

13. " Qualification Test Program on Raychem Nuolear Cable Splices, Okonite Tape Splices, Kerite Tape Splices, Scotch Tape Splices.and Amp Butt Splices as Installed on Various Vire Insulations at Commonwealth Edison Company's LaSalle, Dresden, and Quad Cities Generating Stations",

Vyle Laboratories Test Report No. 17859-02B, Revision A, August, 1987 i

Attachment to WM 87-0309 Pcgo 22 of 89 November 20, 1987 Appendix A JUSTIFICATION POR CONTINUED OPERATION FOR LIMITORQUE OPERATORS Equipment Limitorque operators outside containment with limit switch compartment space heaters.

Qualification Concerns Compartment components aging and degradation caused by existing space heaters.

JCO:

The operation through restart from Refuel 3 of the Limitorque operators outside containment with limit switch compartment space heaters installed is justified for the following reasons:

(1)

During 1986, replacement of all field wiring in safety related Limitorque operators was performed.

Inspection of the removed wiring (several thousand wires) did not produce any physical evidence of degradation.

It is certain that some of these wires would have been in close proximity to energized limit switch compartment space heatere for a number of years while in storage and installed prior to plant startup.

Based on the lack of evidence of degradation for the wires removed in 1986, WCNOC has a high degree of confidence that the currently installed wiring (in place since 1986) will not experience degradation due to energized compartment space heaters before all the heaters are removed prior to startup following Refuel 3 (2)

The only harsh environment accident parameter for outside containment Limitorque operators is radiation.

Worst case accident radiation dose would be 18.75 megarads which is considerably less than the minimum qualified radiation level for Limitorque wiring of 197.7 megarade.

(3)

Test data demonstrates that the limit switch compartment space heater has the capability of withstanding a LOCA without failure even though the space heater was not energized during the qualification test as it would have negated the qualification l

test being performed at that time (Reference 1).

The LOCA test l

profile envelopes the WCGS LOCA profile and, with consideration l

of surface temperature, envelopes the MSLB profile (Reference 1, l

Figure 3).

Limitorque operators outside containment are l

classified as NUREG-0588 Appendix B Category "C"

or "D"

for HELB.

Attachment to WM 87-0309 Page 23 of 89 November 20, 1987 Reference 2 further describes the space heaters as constructed of non-organic materials, and as such, not susceptibl e to thermal or radiation aging.

Operability in a high humidity environment was demonstrated by Limitorque by pouring water over an energized heater and by additional MSLB testing in a steam environment as documented in Reference 3 The limit switch compartment space heaters were energized throughout the testing documented in Reference 3 The above testing demonstrates that the Limitorque operators limit switch compartment space heaters would not fail in a detrimental manner during or following a design basis accident and are, therefore, acceptable for use through restart from 2

Refuel 3 at the Wolf Creek Generating Station.

(4)

Limitorque limit switch compartment space heaters are provided to prevent moisture accumulation within the operators during storage.

The space heaters perform no safety function although the heaters are powered from safety-related power supplies.

The Limitorque testing described above documents that during or following a DBA no failures, including failures affecting p over cupply, were identified.

Referencess 1.

Limitorque Research and Development Laboratory - Report #B0121 2.

" Clarification of Information Related to the Environmental Qualification of Limitorque Motorized Valve Operators",

April, 1986, prepared by Nuclear Utility Group on Equipment Qualification (Excerpts only) 3

" Qualification Test of a Limitorque Valve Actuator in a Steam Environment", Report No. F-03271, February, 1972 (Copies of the above references have been attached for your convenience.)

i l

1

Attachment-to WM 87-0309 Pago 24 of 89 November 20, 1987 1

Appendir A Reference 1 LIMITORQUE P.ESEARCH AND DEVELOPfiENT LABORATORY REPORT fB0121 l

i i

i

I Attachment to WM 87-0309 Page 25 of 89 November 20, 1987 LIMITORQUE RESEARCH AND DEVELOPMENT LABORATORY REPORT #B0121 Project #681041 I

l WARD LEOt!ARD !! EATER ENVIRONMENTAL (L.O.C.A.) AND SEISMIC AGING TESTS

Background

A typical Ward Leonard limit switch compartment heater was to be selected for tests to prove operability following seismic aging and simulated Loss of Coolant Accident (L.O.C.A.) tests.

Sample Identification One (1) Ward Leonard heater I.D.- #30/25F 750 WL8005 Proceduros The test sample was mounted in a Limitorque SHB-O valve actuator in a typical fashion and wired as shown in Figure 1.

Before testing, baseline parameters were recorded as indicated in the data summary (Appendix A). The SMB-0 (used only as a vehicle for the test sample) was then subjected to seismic simulation consis-ting of sinusoidal dwells of ten second duration each from 6Hz to 3 5112 (dwelling at each integer frequency) with an acceleration of 6.0g at each frequency.

A check against baseline measurements was made following seismic aging.

The test sample was then subjected to a 30-day Loss of Coolant Accident simulation (as shown in Figure 2).

Resistance measure-ments made at specified intervals (see Appendix A) were recorded and the heater was energized for ten minutes just prior to con-cluding the 30 'sy profile.

Test Results: See appendix A

==

Conclusion:==

Based on data and information in this report, the Ward Leonard limit switch compartment heater (as identified) has the capability of withstanding a L.O.C.A. condition in inside containment service.

Charles H. Cox Assistant Chief Test Engineer

i Attachment to WM 87-0309 Page 26 of 89 November 20, 1987 APPE!* DIX A L.3.C. A. DAT/ SLT.01ARY L.

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Attachment to UM 87-0309 Pagn 30 of 89 l

November 20, 1987 i

I l

Appendix A Reference 2 CLARIFICATION OF INFORMATION RELATED TO THE ENVIRONMENTAL QUALIFICATION OF LIMITORQUE MOTORIZRD VALVE OPERATORS (Excerpts Only)

April, 1986 prepared by Nuclear ' Utility Group on Equipment Qualification i

Attachment to WM 87-0309 Page 31 of 89 November 20, 1987 l

i l

\\

~

CLARIFICATION OF INFORMATION

'RELATED TO TH E i

ENVIRONMENTAL" QUALIFICATION

'OF LIMITORQUE MOTORIZED

' ~

VALVE OPERATORS Prepared by:

NUCLEAR UTILITY GROUP.ON EQUIPMENT QUALIFICATION APRIL 1986

e Attachment to WM 87-0309 Page 32 of 89 Novemoer 20,.1987 LIH! TORQUE Page 37 23.

Limit Switch Compartment Heaters:

Limitorque did not have Limit Switch Compartment (LSC) heaters installed during any environmental qualification tests.

Limitorque

has, however, conducted screenine tests and evaluations of the heaters.

The heaters previded by Limitorque are principally of a vire-wound / ceramic construction, although some are of a carbon-film / ceramic construction. The heaters are stud mounted with wiring bolted to two contact ears located at i

the opposite ends of the resister. Limitorque had no data on the temperature rise created by energized heaters.10 In November 1978, a Limitorque test was conducted by applying proper voltage to a Ward Leonard space heater allowing the surface temperature to stabilize (measured at 250 degrees F),

and a glass of tap water was poured over the heater (temperature measured at 68 degrees F).

This was repeate,d a second time, once again without ill effect.

When inspected at the conclusion of i

the test, no damage was noted.

I

(

{

10/A review of B0058 suggests that for most applications an acceptable qualii'ied life (40 years) with substantial margin should still be available for units with minor temperature increases above typical plant ambient conditions. See B0058, I

Section 3.2, Thermal Aging.

Attachment to WM 87-0309 Paga 33 of 89 November 20, 1987 Appendix A Reference 3 QUALIFICATION TEST OF A LIMITORQUE VALVE ACTUATOR IN A STEAM ENVIRONMENT Report No. F-03271 February, 1972

)

~

Attachment to WM 87-0309 l

Page 34 of 89 November 20, 1987 I

l PROPRIETARY INFORMATION nn-ws v.-:;w wj$d(%

rsure

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" ~ I'E!!"E Repo$t

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i QUALIFICATION TEST OF LIMITORQUE VALYE ACTUATOR IN A STEAM ENVIRONMENT February 1972 Prepared for i

Limitorque Corporation l

(Affiliated with Philadelphia Gear Corporation)

King of Prussia. Pennsylvania Under Limitorque Shop Order No. 360160 PROPRIETARY INFORMATION E FRANKUN INSTITUTE RESEARCH LABOR ATORIES

Attachment to WM 87-0309 l

Page 35 of 89 November 20, 1987 F-C3271 TABLE OF CONTENTS Pace

.. n 1.

I N130 0U CT l 0 N......................... 1-1 2.

IDENTIFICATION OF VALVE ACTUATOR............... 2-1 j

3.

ST EAM ENV I RONME NT TEST.................... 3-1 3.1 Te s t A rra ng eme n t.................... 3-I 32 Tes t P rocedure and Resul ts............... 3-5 4.

CONCLU$10N.......................... 4-1 5.

CERTIFICATlow................,........ 5-1 APPENDIX A - SAMPLE OF THRU!T MEASUREMENT RECORD.........

A APPENDIX B - LIST OF INSTRUMENTS USED IN OBTAINING TEST DATA...

5 LIST OF FIGURES Fig. No.

- Pace i

Part of Test Facility,* Showing Thrust Device Mounted I

on Test Chamber....................

3-2 2

Valve Actuator Mounted laside Test Chamber Before S t a rt o f Te s t.....................

3-3 3

Test' Profile......................

3 6

'1 4

Appearance of Valve Actuator at Conclusion of Test...

3 8

-l 5

Close-Up View of Valve Actuator Following Test.....

3-3 6

Overall Vlow of Valve Actuator af ter Renovel from T e s t C ha mbs r......................

3 10 7

Close-Up View of Switch Compartment Following Test...

3-11 LIST OF TABLES T&ble 1 - Valve Actuator cycling Data.............

3-7 Table 2 - Insulation Resistance of Power and Control Leads...

3-13 I

e I

Tiilhe rxara mstmm nrsrucx.uennemas

'l

Attachment to WM 87-0309

'a Page 36 of 89 November 20, 1987 F.C3271 1.

INTRODUCTION

,o A Limitorque 51G-0-25 valve actuator was subjected to a qualification test to determine the acceptability of this model of valve actuator for service in a stesa environment. The test consisted of a 12-hour esposure to an environment of saturated vapor, beginning with the introduction of stesa and,a temperature rise to about 212'F. followed af ter 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

by a temperature drop to about 155'F. The pressure vae maintained at 7 inches water sage throughout the test. The performeece of the actuator was monitored by cyclias under load and measurement of insulattee re-sistance on all power and control leads periodically during the test.*

Richard L. Fayne and Joseph 31deau, representing the General Electric j

Company. Atomic Power Equipment Department, were present during part of the test to monitor its performance.

1-1 Txt rRAxc.m mstmnt RE3EARCH LASCRATCR23

Attachment to WM 87-0309 Pago 37 of 89-November 20, 1987 F-C3271 2.

1 IDENTIFICATION OF YALVE ACTUATOR The valve actuator tested was a standard limitorkue Valve Cos.tts1 without any special materials of construction used for high-temperature da7well service. The non-metallic parts of the geared limit and torque limit switches were made of standard Duras material. 0-ring seals and gaskets were of standard Buna-N and the lubricant was Eumble Nebula EF1.

The valme actuator, motor and actor-brake composants of the unit tested were identified by the following information on the same plates VALVE ACTUATOR MOTOR-8 RAKE

LIMITORQUE RELIANCE DUIT MASTER UNI 1RAKI TYPE:

SMB IDENTIFICATION No.: E31 SIZE:

0 70LTS:

230/460 CRDER:

350MOA AMP 0.32/0.16 SERIAL: 142841 TORQUE:

3 ft-lb VALVE: 203-AT040' FNASE:

1 CTCLES:

60 l

Casse 3 insulation was used in l

l the setor brake.

]

MOTOR LIMITORQUE MA.WTACTURER: Reliance Electric Co.

IDENTIFICATION NO.: 463401 JV TORQUE MOTOR HF 10 lbs INSULATION: Class B SIA17 10 lb-fa RUN 2 lb.ft TYPES F

TRAME:

F 36 l

FMASE:

3 RPM:

3400 KZ:

60

. VOLTS:

230/460 AMPS 4.8/2.4 j

R13E AT RUN T0xQUE: 13 Min. 73'c l

I 2-1 Txt rnAxtuN DGTmnE RISEARCH LASCRATOR23 4

Y fL

Attachment to WM 87-0309 Page 38 of 89

~

November 20, 1987 F.C3271 a

3.

STEAM ENVIRONMENT TEST 3.1 Test Arrangement The test was conducted in FIEL's Qualification Test facilities (Figure 1). The valve actuator was mounted inside a test chamber as shown in Figure 2.

The velve actuator stem wee connected to a thrust-asasuring dev'ica (part of which is visible at the lef t of the test

. chamber in Figure 1) through a flange connection, at the left of Figure 2.

Power control and thermocouple leads were passed to the outside of the test chamber through conduits ruaning between the switch compartment and the top of the test chamber, as saa be seen la Figure 2.

Control switches and position indicating lights, which were wired to the geared limit evitches, were mounted on a panel outside the test chamber.

The Limitorque operator was wired so.that the closing torque switch stopped operation in the open directies.. Provision was made for measur-ing the pressure and temperature inside the test chamber, the pressure inside the switch compartment and the temperatures in the actuator actor housing, the evitch compartment and the steam condensate which collected in the bottom of the test chamber (below the draia level).

The desired environmental conditions were obtained by bubbling steam through a layer of water (and steam condeasste) La the bottoa of the test chamber. The pressure was controlled mainly by exhausting the staan through a tube partly submerged la a water reservoir outside the test chamberg,the pressure within the test chamber was thus approximately equal to the depth of the open end of the exhaust tube below the surf ace of the water la the reservoir. The temperature was controlled partly by adjusting the steen flow rate and partly by the use of electrical

~

heeters attached to the outer surface of the test chamber.

1 3-1 ss -- -- ----

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Part of Test Facility Showir.g Thrust Device Mounted on Test Chamber The instrument in the foreground is the Sanborn Recorder used to measure thrust.

{

3-2 THE TRANnDt DCTmTft EDIAACH LUCRATCE:ES 1

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The thrust device is outside the test chamber, et the left.

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Page 41 of 894 November 20, 1987 l

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A thrsat, device was used to asamures tlc thgdst dowloped by tiw!

,f E

l valve actuator'ston at the end of its oloss cycle. This device comeisted j

t.

of a longitudiwA12y sluttede steel cylinder, closed at sine end, and equipped with a temperature-compensated strata gene la the middle of one

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. side.. When the,ats.m seated against the c.1ceed sta of the cnind.tr at the end of a ens cycle, the thrust was indicated df the strate gese.

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The electrical output of the strain sage bridge ciccuit was recorded j

with 4 tenborn recorder, calibrated ta read pesads of thrust. A sample thrust measurement record La shown is Appendia A.

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To elf" 24 ate any possibility that *:h/ gasket ht.tpaea the valve actuator housing and switch comtetgJtems cover was sealing the interior from the test environment. a 3/16-Inch section was purposely cut out of 3

the gaskat. This was done to damenstrate that the valve actuator would S. -

r==atn functional even though the integrity of the gesOc and of sta11ar protective components (such as seals e4 electried,toedults) were damaged.

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Attachment to WM 87-0309 Page 42 of 89 November 20, 1987 I

F-C3271 3.2 Test Procedure and Results The test profile is illustrated in Figure 3.

The, pressure was.

maintained at approximately 7 inches of water sage throughout the test.

The temperature in the test chenbar increased to about jt10*F within one -

hour, and it was maintained at approminately 212'T for the remainder of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Then the temperature was permitted to drop gradually to about 155'F. where it was held until the end of the test. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from the start. A 25-U/120-V space heater in the switch compartment was kept constantly energized. During the first six hours of the test.,the temperatures in the test chamber and inside the switch compartment were approximately the semet during the last six hours, the switch.coopertsent temperature remained about 30*T higher then the temperature in the test chenbar.

j The valve actuator was cycled 12 times during the test, et the times indicated in Figure 3.

Each cycla was started with the actuator in the cices position, the valve stem was run to the open position and returned to the closs position. where it was lef t between cycles. The measurements made during each cycle are recorded in Table 1.

The voltage.'

1 current and power to the motor were measured d ring both the open and close portions of each cycle. The length of th stroke was 9-1/4 inches, and the travel time was about 44 seconds in both ben and eloss directions.

The thrust developed when the stes seated in the loading device, at the end of each eless stroke, varied between 9100 and 10.100 lb, Following the conclusion of the test, a visual inspection was conducted; and several photographs were taken of the valve actuator, beth before and af ter removal from the test chsaber. The photographs are shown in Figures 4 through 7.

Aside from some deterioration of the esterior paint coatings, j

the visual inspection of the valve actuator and evitch compartment did not reveal any deleterious effects.

Five times during the test, as indicated in Tigure 3. external connections to all power and control leeds were removed, and.the insula-tion resistance was seasured between each conductor and ground. De 3-5 et rai tuu,,t1mnt atttocu ti,e ito.it, i

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Attachmant to WM 87-0309 Pago 49 of 89 November 20, 1987 F.C3271 measurements wars made at 500 V dc. and are recorded in Table 2.

Sefore the steam exposure was initiated, all insulation resistances were infinite.

During the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the steam exposure, the resistances decreased, reaching values no lower than 750.000 ohne. As the. temperature was lowered -

during the remaining 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the test, the values of resistance increased by approximately en order of mainitude, the lowest value being 8.3 mgotas at the and of the test. Af ter the test chamber returned to mbient temperature, the insulation resistances measured at the heater and stator winding leads were infinita, and all other leads had resistances exceeding 100 megehns.

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Attachm::nt to WM 87-0309 Pago 51 of 89 November 20, 1987 l

F-C3271 i

1

4. CONCLUSION A Limitorque 51S-0 25 valve actuator was subject'edTo a Qualifi-cation Test consisting of a 12-hour exposure to a law-pressure secas environment. The actuator performed satisfactorily at all times when l

' operated periodically during the test. Visual inspection following the test did not reves1 any deleterious effecto, it is concluded that a valve actuator with the same construction as the model tested will perform satisfactorily ader the conditions simu-lated by the test.

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Attachmsnt to WM 87-0309 Pago 52 of 89 November 20, 1987 F-C3271 5.

CERTIFICATION The undersigned certify that this report e'on'Yitutes a true - -

^

s account of the test that was conducted and the results thereof.

WJ

=m

5. F. Carfagno /

Senior Staff Physicist a r. M W.

L. E. Witcher Test Engineer t w. K W. M. SteigelaIFan Manager Nucisar Systems Laboratory i

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5-1 Txt rutrum mstmnt nestAnex LAnoAATORH3 r

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Attachment to WM 87-0309 Pago 53 of:89 November 20,-1987'

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t F.C3217 i

APPENDIX A 1 AMPLE OF THRUST MEASUREMENT RECORD 9

9 9

A Mr F1Uutic.pt DesTmnt RESEAACM LABORATORE5 J

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-0309 Pago'.55 of 89-NovemberS20, 1987 l

F.C3271 l

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APPENDIX 3 LIST OF INSTRUMENTS USED IN OSTAINING TEST DATA '

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~ Attachment to WM 87-0309

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Paga 56'~of 89 November 20, 1987 F-C3271 APPENDIX B LIST OF INSTRUMENTS USED IN 08TAINING TEST DATA 1.

Noneywell-Brown Electronik Multipoint Recorder. Hodatuo.

15305846-24-02-2-000-030-10 097. O to 300*F with Type T Therme-couples. (Calibrated 11/22/71.)

2 Sanborn Model 297, 2-channel Recorder, with Carrier Preamp Model 850-1100. (Calibrated 1/18'72.)

3 James C. Biddle Messer lasulation Teater. Design No. 690326 500 Vdc..(Calibrated 2/1/72.)

4 Weston Electric Instruneat Corp.. AC Amster. Metal 433. No.

30b 2 and No. 22645. (Calibrated 1/10/72.)

3.

sensitive Research Instrument Co. Alternating Current voltmeter.

Model A.

(Calibrated 12/21/71.)

6 Esterline Angus Graphic Wattneter. Model AW: Serial No. 157743;

1. 2. or 3 phase.

7 Weston Potential Transformers. Model 311. Estio 460/230/113 No. 3283 and No. 3284 8.

Trimount Instrument Co., 30-in. "U" Tube Manometer, with Nortaa lastrument Co. Unity oil.

9 Marian Instrument Co., 36-in. Manometer with Unity oil.

4 4

5-1 TMt DesTmtrt RtstAACH LASCRATOR!t3 1

l

'O

Attachment to WM 87-0309 Pago 57 of 89

)

1 November 20, 1987 I

The Tranklin Institute Basearch Laboratories (TIRL) was estab-lished in 1964 as the research division of The Tranklin Institute, which was founded in 1824.

As a 'ot-for-profit organization, independent of comane'r~cial and n

academic interests TIIL undertakes research development, and engineer-ing projects for both government agencies and private industry in the United States and abroad.

The Research Laboratories has a technical staff.sf approximately 300. It is organised into 17 Laboratories, grouped into five operating Departments: Materials Science and Engineering, Mechanical and Nuciaar Engineering, Chemistry, Electrical Engineering, Systems Science, and Science Information Services. The Laboratories also maintains a fs11 Support Services Department which includes a publications group, phoco-graphic laboratory, instrument repair and calibration shop.and a large machine shop.

4 0

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Attachmnnt to WM 87-0309 Pago 58 of 89 November 20, 1987 Appendix B JUSTIFICATION POR CONTINUED OPERATION POR DUAL VOLTAG8 LIMITORQUE OPERATORS Equipment: Dual voltage Limitorque operators Qualification Concern:

Use of Thomas & Betts (T&B) nylon crimp terminals in dual voltage Limitorque motors is currently in a test program.

The final results are not available.

JCO:

The use of Thomas & Betts nylon crimp terminals in dual voltage Limitorque motors successfully completed an 8-year intermediate qualification test by Wyle Laboratories.

A 40-year qualification test is currently being conducted. The qualification levels outlined in the Wyle Laboratories Qualification Plan 17954-1 (See Reference) were met or exceeded during the performance of the 8-year intermediate test.

The T&B nylon crimp terminals were subjected to 0

thermal aging of 212 P for 311 hours0.0036 days 0.0864 hours 5.142196e-4 weeks 1.183355e-4 months .

Using the activation energy of 1.17 eV results in a qualified life of 38 years by the Arrhenius method for the WCGS ambient of 104 P.

However, some bulk heat rise within the limitorque limit switch compartment has been present for the past 2.5 years due to the limit switch compartment space heaters being energized for a number of valve operators with dual voltage motors.

The worst case configuration would result in a temperature rise of approximately 32 P above ambient.

At a temperature of 136 P for the first 2.5 years and 104 P thereafter, a qualified life of I

14.7 years would result based on the Arrhenius method.

Irradiation to a level of 11 megarads, gamma, by a Cobalt 60 source, was performed.

This level of irradiation envelops the 40-year normal plus accident total integrated dose (T.I.D.) for the majority of the Limitorque operators with dual voltage motors.

An evaluation had been previously performed (included in EQWPs HE-4 and BOP Limitorque) to show that all Limitorque operators with dual voltage motors will have performed their safety function prior to receiving a 4 megarad T.I.D.

This evaluation is conservative relative to the 11 megarad T.I.D. applied during the T&B terminal testing.

,.._.____2_

Attachment to WM 87-0309 Page 59 of 89 November 20, 1987 No safety-related Limitorque operators with dual voltage motors are located inside containment at WCGS.

The safety-related Limitorque operators with dusi voltage motors located in the Auxiliary Building are NUREG 0588 Appendix E Category "C" or "D" for a HELB and MSLB.

Therefore, the only harsh environment parameter (post-LOCA) for the subject operators will be radiation.

Although the accident test profile performed during the qualification test sequence is not required to demonstrate qualification of the T&B crimp terminals for WCGS, the accident test performed does demonstrate that moisture intrusion into the operator limit switch compartment would not be detrimental to the operation of the crimp terminal.

No anomalies were observed during the 8-year interim test which would affect the qualification of the terminals.

I In summary, the 8-year interim test provides adequate justification for continued operation of the dual voltage Limitorque operators with T&B nylon crimp terminals at WCGS pending completion of the 40-year testing program, including preparation of the test report, which is currently scheduled for early 1988.

Reference:

" Qualification of AMP Product Corporation 53549-1 and 53550-1 Butt Splices and Thomas & Betts RB-4 and RC-6 Wire Joints for Use in Illinois Power Company Clinton-1 Nuclear Power Plant", Wyle Laboratories Qualification Plan 17954-1 (Excerpts only).

i (A copy of the qualification plan has been attached for your convenience.)

Attachment to WM 87-0309 Page 60 of 89-November 20, 1987 Appendir B

Reference:

QUALIFICATION OP AMP PRODUCT CORPORATION 53549-1 AND 53550-1 BL"rT SPLICES AND TH(MAS & BETTS RB-4 AND RC-6 WIRE JOINTS FOR USE IN ILLINOIS POWER COMPANY CLINTON-1 NUCLEAR POWER PLANT-Wyle Laboratories Qualification Plan 17954-1 I

(Excerpts Only) u_________._.._.___.._

I I,

Attachm:mt to WM 87-0309 Pago 61 of 89 November 20, 1987 QUALIFICATION ou^'. r'A N --

2795'-t WYUE LABORATUREs PLAN oATo s. u bor 17. in, ecomme asevens a mTame neoue

, O. SCA 900. a muNTavlLLt. ALA8Ama 1%ec7 TWA te100 7262226

7tLt. MON 8 (20S).37 49 t REVISION A - October 9, 1987 REVISION 3 -

October 16, 1987 QUALIFICATION OF AMP PRODUCT CORPORATION 53549-1 AND 53550-1 BUTT SPLICES AND THOMAS dc BETTS RB-4 AND RC-6 WIRE JOIN'E5 POR USE IN ILLINOIS POWER COMPANY CLINTON-1 NUCLEAR POWER PLMIT Apenovno aY:

WYr/J'7 PROJECT MAN R:

J. F.' Gleason/ /

APPROEED BY:

- 3 '*dIf

~

- APPROV!D BY:--

QUALITY ASSURANCg G. ti."1 FOM: ENVIRONMENTAL' QUAL!FICATION

~

Ilight APPA0VED BY:

9'/h PREPARED BY:

W

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!f7 FOR: CUALIFICfTION PLAN DEVELOPM T PROJ T ENGINEER:

/ J. W. Anders'en '

e i

REVISIONS (DN420) poRM 11001ta.31 R2V. No.

DATE l PAGE CR PARAGRAPH AFFECTED l

BY A PP'L]

OESCAIPil0N OF CH ANGES A

10/9/87 Para. 1.2 (rf/A ei 1

e docux:ent revision fp 8' 6ilM +t*' g.94 Wtwr.u' e+o A

10/9/f7 Para. 1.3 V RA hs#

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Attachment to WM 87-0309 Page 62 of 89 Novehber 20, 1987 MWSMS REv.ou i

QUALIFICATION PLAft_17954-1 N

seusmme seawasee a avevasse ensuo DATE:_ October 9. 1987 i

REV.NO.

DATE PAGE OR F ARAGRAPH AFFECTED BY APP'L DESCRIPTION OF CHANGES A

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pfl graphs,as,needed..

3 10/16/81 1.2.AT3

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Attachment to WM 87-0309 Page 63 of 89 November' 20,- 1987 Quellfloation Plan No. 17954-1 Page N o. 111 Table of Contents 1.0 SCOPE 1-1.1 Purpos e........

I 1.2 Applicable Docum ents.............

1

- 1.3 Equipment Description.............

1-1.4 Qualification Sequence 3

2.0 QUAUP! CATION REQUIREMENTS..........

4 2.1 Definition of Service Conditions 4

2.1.1 M argin.................

4 2.1.2 Normal Conditions............

4 2.1.3 Accident Conditions...........

4 2.1.4 Seismic Conditions............

4 2.1.5 Other Servloe Conditions.........

5 2.2 Qualified Life Goal..............

5 2.3 Safety-Ralated Funettons 5

2.4 Acceptance Criteria..............

5 2.4.1 Punctional Testing............

5 2.4.2 Accident Simulation...........

5 3.0. DETERMINATION OF POTENTIAL A GNG ME CH ANIS MS.............

8 3.1 Relative Humidity 6

3.2 Press ure...................

7 3.3 Cycli ng...................

7 3.4 Thermal and Radiation Aging Documentation...

7 3.5 Tem perature.................

8 3.8 Radiation..................

9 4.0 QUAUFICAVON PROGRAM............

10 4.1 ReceivingInspection 10 4.2 Speelmen Preparation and Mounting.......

10 4.3 Basellne Functional Test.

10 4.4 Radiation Test....

10 4.5 Functional Test...

10 4.6 Therm al A ging..........

10 4.7 Punctional Test.

11 4.8 Accident Simulation Setup.

11 4.8.1 Thomas & Betts Nylon Wire Joints.....

11 4.8.2 AMP PVDF Butt Spl!ces..........

12 WYLE LABORATORIES e

e

_________._______m_

s Attachment to WM 87-0309 Page 64 of 89

(

November 20, 1987 I

l 1

wuauncation Plan No. 17954-1 l

Page No. iv I

o 2

~_.

. - - Tde d Ntets (Continued) 4.0 QUAIJFICATION PROGRAM (Continued) 4.9 Pre-A ccidnet Simulation Functional Test.

14 4.9.1 Thomas de Betts Nylon Wire Joints.

14

~ 4.9.2 AMP PVDF Butt Splices......

14 4.10 Accident Simulation...........

14 4.10.1 Thom as & Betts.........

I 14

-4.10.2 AMP PVDF Butt Spilces......

15

{

4.11 ' Functional Test.

4.1?.. Post-Test !nspection......

16 L

4.32. In-Process Inspection......

16 l

18 j

5.0 QUA IJT Y ASS URAN CE.. -.............

17 6.0 REPORT.........

17 Table I.

....................... 1-1 Table II Table III

......... <..... II-1 Table IV

................ III-1 IV-1 FIGURES

........................F-1 Appendix A Appendix B

................A-1

.......................B-1

................ AT1-1

................AT2-1

................ AT3 - 1

............... AT4 -1 6

4 WYLE LABORATORIES P4untevtale Facetity e

Attachment to WM 87-0309 0

Page 65 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page No.1 REYSION B l

1.0 BCOPE 1

This document Company for equ!pment used at CMnton-1 Nuclear Power Plan 1.1 Purpose

' The purpose of this document is to present the approach, methods, philosop and procedures for qualifying the equipment identified in Section 1.3.

Nuclear environmental qualification of any safety-related device to meet the l

requirements of IEEE 323-1974 is usually a three-step process, i.e., (1) normal radiation expceure, (2) aging, and (3) design basis event qualification (seismic, i

)-

and where applicable, MSLB, HELB or LOCA). The purpose of the first two st is to put the test specimem into a condition that represents the worst state of deterioration that the plant operator will permit prior to taking corroetive action, i.e., its and-of-quallfled-life condition. The next step demonstrates that the specimen still has adequate integrity to withstand the added environmental stresses of the specified design basis events and still perform its safety-related function.

1.2 Apolleable Documents o

10 CPR 50.49, " Environmental Quaufloation of Electrie. Equipment l

Important to Safety for Nuclear Power Plants." U.S. Nuclear Regulatory Commission, Janaury 21,1983.

IEEE 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for o

N ualear Power Stations".

o NURE G-0588, Category I,

Revision 1,

" Interim Staff Position of Environmental qualification of Safety Related Electrical Equipment,"

dated July,1981.

Regulatory Guide 1.89, " Qualification of Class 13 Equipment for Nucler -

o Power Plants", Novembar 1974.

Wyle Laboratories Quality Assurance Program Manual, April,1987.

o o

Sargent and Lundy Engineers Cale. No. CQD-037380, Rev. 03, dated October 16,1987 (Attachment 3).

B 1.3 Equipment Description The equipment to be qualified are electrical splices described as follows:

f WYLE 1.AGORATORIES Mum.m. smury i

l l

1

I Attachmont to WM 87-0309 Page 66 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page No. 2 REVISION A 1.0 SCOPE (Continued) 1.3

- Equipment Description (Continued)

A Specimen Connector /

Cable /

Plant Plant Number Insulation Insulation

_Loestion

_Apatication 1A,B,C-T&B RB-4 1/C 16 AWG O.C.

240/440 VAC Motor

' 10A, B, C Nylon

Rockbestos 800Y Leads XLPE 11A, B, C-T&B RC-6 1/C 12 AWG O.C.

240/480 VAC Motor 20A, B, C Nylon Rockbestos 600V Leads i

XLPE 21A,B-AMP 53549 TSP 16 AWG I.C.

24 VDCInstru-28A, B '

PVDP Okonite 300V mentation Circuits Shielded 29A, B-AMP 53550-1 2/C #19/25

!.C.

120 VAC Control 36A, B PVDP Okonite/Okolon/

Circuits Okolon 600V EPR/CSPE/CSPE 37A,B-AMP 53550-1 2/C #19/25 I.C.

125 VDC Control 44A, B PVDP Okonite/Okolon/

Circuits Okolon 600V EPR/CSPE/CSPE l

45A, B, C-AMP 53550-1 3/C 9 AWG I.C.

30 480 VAC 52A,B,C PVDP Okonite/Okolon Power Circuits EPR/CSPE 1000V Note la The T&B wire joints are used in dual voltage Limitorque valve actuators.

Note 2:

T&B wire joints RB-4 are the same as RB-44 except for the number in the box. The same is true for RC-6 and RC-55 (See Attachment 1).

Note 3:

See Attachment 2 for material information for the AMP spilee.

i Note 4:

The nuclear grade AMP connectors and the nuclear grade cables are to be supplied by Illinola Power Company.

The cable insulation system is not being qualified by this tast program.

The T&B connectors are to be procured by Wyle Laboratories.

WYLE LABOR ATDnlES MWMttethe W cility S

e

{

4

Attachment to WM 87-0309 Page 67 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page No. 3 RrvIsIoM A 1.0 SCOPE (Continued)

I u

1.4 Qualiftontion Sequence..

i The qualification program shall be performed in the following sequences Receiving Impaction o

o Specimen Preparation o

Baseline Functional Test Radiation Exposure (Normal plus acaldent) o o

Punctional Tat o

Thermal Aging Pet-Thermal Aging Functional Test o

PWAceident Simulation Functional Tat o

o Accident Simulation o

Punctional Test A

o Past-Tet Impection WYLE LABORATORIES 9

Attachmant to WM 87-0309 Page 68 of 89 November 20, 1987 Qualitteation Plan No.179s4-1 Page.N o. 4.

REVISION.IL_ _ _.

2.0 QUAI 2FICATION REQUIREMENTS 2.1 Definition of Servloe Conditform 2.1.1 Marrin Adequate margirs have been included in the specifications to account for normal variations in commercial production of equipment and variations in service conditions except for nominal operating voltage which shall have the following B

margin added.

o Voltage

+10% of Nominal Voltage

(+10%,-15% for Specimens 1 through 20) 1 l'

PVDP PVDF I

Nermal Nylon PVDP PVDF Instr.

Instr.

2.1.2 Conditions Limitorque Control Power Annulus O.C.

Radiation (Rads) 1E4 2E7 1E4 SE7 IE7 I

(40 yeara)

Temperature (Max) 1500F 1500F 1040F 1420F 1500F l

Pressure (water)

-1 to

.1"

+/- 5 5.4"

-1 to

.1"

-1 to.1"

-1 tol" A

Relative Humidity 90 %

90 %

l PVDP PVDF Accident Nylon PVDF PVDP Instr.

Instr.

2.1.3 Conditions Limitorque Control Power Annulus 0.C.

Radiation (Rads) 1.1E7 2.2E8 2.2E8 2.2 E8 2.2E8 (40 yrs + Accident)

Temperature 2650P 3450F 2650P 2750P 2850F B"

(Peak) 4' Pressure (Peak) 9 psig 33 psig 16.5 psig 18.5 psig 9 psig (Water)

Relative Staam and Steam and Steam and Steam and Steam and Humidity 100 %

10 0 %

100 %

Spray No Nota 2 Note 2 Note 2 No A

Duration 110 days 110 days 110 days 110 days 110 days Note 1: See Attachment 3 for detailed plant locations and accident profile.

Note 2: Demineralized water spray of 1GPM/sq. ft, starting at 10 minutes and continuing for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

A 2.1.4 Seismie Conditions A

IEEE 383-1974 does not require seismic testing to qualify cables and field WYLE LABORATORIES Hyntoni6e l'acility

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e Attachment to WM 87-0309' L,7, j

Page 69'of 89 j

November 20)11987n Qualitteation Plan No. 17954-1 Page No. 5 REVIslon Ae

- A 2.0 QUAUFICATION REQUIREMENTS (Continued 2.1.4 -

'Selsmie condiths t.contlaued)

~ '

splices, therefore, it is judged that seismio conditions are not applicable to this tent program.

ir J

,(

2.1.5 Other Servlee Cond!tions

, Nominal c!roult voltages are as tabulated in Section 1.3.

g'k )

i 2.2 Qualified Life Goal The qualifiedlih goals are 18 months,3,8 and 40 years.

2.3 Safety 4el;ated Functions The safety classiftention of this equipment is class 1E. The subject equipment

.provides essential services in support of emergency reactor shutdown, containment' isolation, reactor core cooling and containment and reactae heat removal, or is otherwise esitential in providing tauppert to prevent signii%ent ralease of radioactive material to the environment.

2.4 Acceptejee Criteria The following acceptance criteria has been established for the purpose of tir.s i,

qualification effort.

2 4.1 Fwtotional Testirg s

During baseline, post radiation, and post aging functional testing the spilous 3han have a resistance of less than 1.0 ohm and an insulation restitance of gteater than 1.0 M ohm.

2.4.2 Accident Simulation -

i Before, during and after acc! dent simulation the following acceptance cF,tMa

) l applys The T&B connectm shall allow the connected Limitorque valve actuator o

to operate.

The Amp s;iiices in the control circuits shall allow the connected ASCO e

valves to operate.

The Amp splices in the power circuits shall maintain circuit continuity and o

voltage to within125% of that appued without tripping the " amp fuse, i

i The Amp splices in the tratrumentation circuit shall allow the attached o

transmitter to operate with a loop corrent diffr.;tance of lom than +/-15% >

(!

WYl.E LABORATDRIEa Muniome F.cin,y n

"^

'l a

Attachment to WM 87-0309

[

Page 70 of 89 November 20, 1987 I

h Quallfloation Plan No. 17954-1 i

Page No. 6 4

~ DETERMINATION OP POTENTIAL AGNG MECHANBMS 3.0

^

Each component in the subject equipment has been reviewed in order to eseertain all the safety related maturtals of construction. Then a determination of the aging. mechanisms which may affect the subject materials is accompushed by reviewing its application and the service conditions to which the equipment will be quallfled. The service cond!tions to be addressed area Relative Humikty.

o.

t o

Pressure c

o Cycling" o

Temperature o

' Radiation ~ ~ ~ -

3.1 Relative Numidity k3 Por insulation systems, the effect of a humid environment is not considered an aging mechanism.' As notedin Wyle Aging Library (WAL) No. 0255-80:

"In most' cases, moisture plays only a secondary role in the l

failure.

t-It does not produce damage to the irsulation, the insulation wears away or cracks for other reasons. Moisture merely provides a direct electrical pathway between these mature devloes and ground."

IEEE 117-197-1974, Paragraph 3.3.3 states:

" Moisture is used to make d=1.utriu testa inurir6tredingNP- -- -

[s physical and thermal damage to electricalinsulation systems."

As further noted in WAL No.

thermally aged test specimens:0010-78, in a discussion of moisture conditioning of

" Moisture conditioning is included in the (test) procedure (of IEEE 117-1974) as a probe for determining insulation failures at the time they occur, and la not in itself intended to be an aging factor (emphasis added).

Most electrical Insulation, as~1t thermally ages, increases in ability to absorb moisture, which in turn la reflected in a lower insulation resistance and corresponding electrical strength."

The Nuclear Regulatory Commission, in a discussion of comments on 10 CPR part 50 states:

"I t has not been demonstrated that the time-dependent variation in humidity will produce any differences in degradation of ele:tric equipment."

It is therefore concluded that relative humidity is not an aging mechanism.

WYLE LABORATORIES Huntsville FaC6Hly e

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Attacnraent' to WM 87-0309 j

i

'g Page 71 of 89 vn 1

November 20, 1987 e

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iY Qualification Plan No. 17954-1

~W Page No. 7 i' REVBION A

~-

q 3.0 DETERMINATION OF P(yfENTIAL AGNG AECHANEndS (Continued) 3.2 Pteceure I

,, ; y

.p The atmospheric' pressure is equal to 406.Wiinehas' O.

Typicauy, from WAL No. 0269-80, the mean changes by S _4 inches cP across the United States. Within the same location, the mean changes fleth 2 to 4 inches of Hgo

?

f each year. Qus11floation requirements for atmospheric pressure changes within the limits of 8.4 inches of H O are judged to be of no consequence since neither 2

I WAL Nos. 0021-78A nor 0456-80 noted ut effect due to domtal cmospherto changes.

[

t, 3.3 /

gg}ig i

Cyoung is not an applicable aging mechanism for the butt spuces and wire joints

[

ouvered in this program.

3.4 Thermal and Radiation Aging Daoumentation,

~

In order to document the thermal and radation aging mechanismalaeoeisted with the materials of construction included in this progrnm an Aging Matrix (Table D has been prepared. The materials identifloation is based on data obtained from.the manuf acturer unless otherwise noted.

o-Column 111sts the item number.

I Column 2 Usts the item's name, manufacturer and ria.terial, o

o Column 3 lists the thermal age sensitivity criteria for each materfri and whether that material is age sensitive. For equipment located in a _ mild environment the criteria is 120 years for a 40 year quall s

the expected 11fe found in column 4 is greater than AN ye fled Ufe goal. If ors that item can be exempted from thermal aging.

The eritenir? 'far items in a harsh environment outside of containment is 1,000 yurs. and for inside q.,

containment it is 10,000 years, au for a 40 year qua11%ed life goal.

o Column 4 lists the rated maximum, continuous use tempneture in DC for the material and the heat rise le r #C asecciated with the partfeular

. Ocmponent where appilcable. The listed heat rise is used in calculating the expected life in column 8.

Column 5 IIsts the activation energy of he material and the WAL o

reference number for the document from which this value was obtained.

o' #

o Column 6 Usts the radiation throshild value for the material and the.WAL maference nt'mber for the source of this information. WAL No. 05c5-8tA 1

Wefines the radiation threshold ass

'The Iowat radiation dese Nolon inheca permanent change in a measured yoperty of a material."

nn".daoans "the first detectable change in a property of a material, consistent with its application,is used for this procedure."

~

WYLE LABORATORIES Hwmsvme eacuity

<{:

4 e

A?

o.

Attachment to WM 87-0309.

Page'72 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page No. 8 REYBION A 3.0

.~ -

=

DETERMINATION OF POTENTIAL AGNG MECHANBMS (Continued) 3.4 Thermal and Radiation' Aging Documentation (Continued)

If the normal 40-year total integrated dose is less than 80% of the radiation threshold the item can be exempted from normal radiation exposure. If the 40-year normal plus accident totalintegrated dose is less than 80% of the threshold the item can be exempted from au radiation testing.

o'

- Column 7 Ests the application of the item.

~

Column 8 lists the expected 11fein years of the item and a reference to any o

g notes providing additionalinformation pertaining to the particular item.

The Reference List (Table U) tabulates the Wyle Aging Library (WAL) references which f arm the basis of the analysis and/or conclusions of this report, as wen as -

those utilized in the preparation of the Aging Matrix.

The' normal service conditions which are used as the basis for the calculations in the Aging Matrix are documented in Table IH.

i 3.5 Temgeraturq -

Normal temperature' conditions coupled with time create an aging mechanism known as time / temperature effects. As notedin WAL No. 02$6-80.

'The expceure of polymen to the influence of environmental factors over a period of time generally leads to deterioration in physical properties."

)

Appendix A provides a deta!Ied explanation of the methodology used to determine thermal age sensitivity and aging parameters.

A literature search of the Wyle Aging Library has been utilized to obtain auditable aging data. Por components with time / temperature-related aging mechanisms, the aging analysis was based upon available auditable aging data, as f

noted in Table 1. The Arrhenius constants whleh are most appropriate to the i

materials and their applications have been utilized when more than one set of

-l constants are known.

Due to the small currents drawn in instrumentation and control circuits there is 3

no significant heat rise. In the power circuits addressed in this program, the end devices are only operated intermittently and the heat rise associated has no effect on qualified life.

{

The calculation sheets for the aging program and post DBE aging program are included in Attachment 4.

O

Attachment to WM 87-0309

'Page 73 of 89 November 20, 1987 Qualification Plan No. 17954-1

_,,......, Page No. 9 3.0 DETERMDIATION OF POTENTIAL AGNG MECHANISMS (Continued) 3.6 Radiation f 2.,__

Evaluation has been. made of: the function of the component materials. This information has been compared to auditable data to determine the susceptibility of the material, in its application, to the radiation exposure level specified.

A literature search of the Wyle Aging Library has been utilized to obtain the radiation threshold values tabulated in Table I.

Appendix B discusses how synergism is addressed in this program.

Per Table I, all of the subject equipment have radiation thresholds less than the requirements.

Therefore, radiation exposure is required to confirm the capabDity of these specimens to perform their safety-related function in the specified environment.

WYLE LABORATORIES Hunisvm, ascinty a

Attachment to WM 07-0309

)

Page 74 of 89 November 20, 1987

)

Qualification Plan No. 17954-1 Page N o.10 REVISION A 1

4.0' '

QUALIFICATION PROGRAM l

(

1 4.1 Receiving Inspection An irspection shall be performed upon receipt of the components at Wyle l

i Laboratories. This inspection shall assure that the equipment received is as described in Paragraph 1~.3.

Applicable numbers shall be verified. The results of j

the inspection (component identification, quantities, etc.) shall be recorded. For j

informational purposes record the manufacturer, insulation system, gague, number of conductors etc. for the cables. The subject test specimens shall be labeled, as' deemed necessary by the Test Engineer, for positive identification of l

' the specimens during all phases of the test program.

l 4.2 Specimen Preparation and Mounting The specimens shall be prepared as indicated in Table IV. Photographs shall be taken of aH test assemblies.

I l

4.3 Baseline Functional Test

)

Continuity of the assembled specimens shall be verified with a dgital o

ohmm eter.

Insulation resistance shall be measured by applying 500 VDC between the o

conductor of the spliced cable and ground for one minute. If a readng cannot be obtained at 500 VDC, the voltage shall be reduced until the Insulation resistance is measurable.

\\

All results shall be recorded and compared to the acceptance criteria in l

o Saction 2.4.1.

4.4 Radiation Test Assemblies 1 through 10 shall be irradiated to 1.1E7 rads and Assemblies 11 through 18 shall be irradated to 2.2E8 rads with a Cobalt 60 source. Radiation exposure shall be performed at the maximum possible dose rate (approximately 3E6 rada/ hour). The dose shan be based on the centerline of the test specimens and they shall be rotated 1800 half way through the exposure.

The test i

specimens shall be unpowered during the radation exposure.

Electrical i

monitoring of the test specimens is not required during the radiation exposure.

Note: As soon as Assemblies 1 through 10 have completed Mdlation they shall be returned to Wyle Laboratories for functional testing and th<e.r.a1 aging.

4.5 Punctional Test The functional test of Paragraph 4.3 shall be repeated af ter radation exposure.

4.6 Thermal Aging Thermal aging of the specimens shall be performed as specifled below. The thermal aging program is based on the irnulation of the spilces and a 1250F nominal ambient temperature. The Arrhenius calculations which document the accelerated aging time are included as Attachment 4. The test specimens shall be unpowered during thermal aging. Electrical monitoring of the test specimens is not required during this phase of testing.

WYLE LABORATORIES Myaltsvilig P 3cility 8

Attachment to WM 87-0309 Page 75 of 89

-November 20, 1987 Qualification Plan No. 17954-1 Page No.11 REVISION B _

4.0 QUALIFICATION PROGRAM 4.8 Thermal Aairs(Continued)

Assembly Quallfled' Irmulation Aging.

Aging Number '

Life Goal Material Temperature Time 1+6

[8 months Nylo' -

2020F 108 hrs n

2+7l 3 years Nylon ~

~ 2120F 117 hrs 3+8 3 years Nylon 1760F -

916 hrs 4+9 8 years Nylon 2120F 311 hrs 5+10 40 years Nylon 2120F 1553 hrs 11+15 18 months PVDF 2020F 102 hrs 12+16 3 years PVDF 2140F 101 hrs 13+17 8 years.

PVDF 2320F 104 hrs 14+18 40 yeare PVDF 2650F 105 hrs Notes All temperatures shall be controlled to +100F,-00F during aging and the A

time shall be controlled to +3, -0 hours.

4.7 Funetional Test The functional test of Paragraph 4.3 shall be repeated at the equivalent of 10 years and af ter thermal aging.

4.8 Accident Simulation Setuo A_

4.8.1 Thomas at Batta Nylon Wire Joints 4.8.1.1 Specimen Preceration 1.

Put the cover back on the Limitorque SMB-0 valve actuator used in Test Procedure 17943-1. Note: The assembly used in the accident simulation may be changed based on the results of section 4.7 and visual examination l

of the specimens.

2.

Remove the existing T&B wire joints from the motor leads.

i-3.

Provide a three pole double throw control device such that the motor of the actuator can be powered through either specimens 4A, B, and C or 14A, 3

B and C. A wiring diagram shall be providedin the test report.

4.

Run the control device wires through the access holes in the housing adjacent to the top of the cover. Do not seal the hole.

3 t

WYLE t. LABORATORIES m,etssme nea,ty

Attachment to WM 87-0309 Page 76 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page No.12 REVISION B

~

4.0 QUALIFICATION PROGRAM (Continued) 4.8.1.1 Specimen Preparation (Continued) 5.

All splices between the test specimen leads, the control device wiring and the motor leads shall be !nsulated with Raychem heat shrink tubing. Do not put Raychem on the T&B wire joints,,

6.

Verify that the drain plug in the bottom of the cover is in place.

7.

Take Polaroid and regular photographs of the test specimem and the test set up.

8.

Manually stroke the actuator to approximately the mid-position.

4.8.1.2 Powerfra Supply 528 VAC (+3%,-0% VAC) power.

3 l 4.8.1.3 Instrumentation 1.

Three thermocouple shall be located in the environmental chamber within two inches of the surf ace of the cover and shall be utilized to monitor the chamber temperature.

The individual readings shall be recorded and averaged, and the averaga recorded. The average of the values from the three thermocouple shall be used for control thereafter.

~

2.

A pen chart recorder shall also be provided to continuously record the B

chamber temperature.

3.

Monitor and record motor voltage, current and limit switch operation to verify actuator operation.

4.8.2 AMP PVDP Butt Sollees 4.8.2.1 Specimen Preostation 1.

The NEMA 1 enclosure containing assembly 14 shall be mounted and affixed to a Wyle supplied test fixture in the test chamber in an upright orientation. Note: The assembly used in the accident simulation may be changed based on the results of Section 4.7 and visual examination of the specimens.

2.

Irstall a pressure transmitter outside the chamber and connect its pressure port to a dead weight tester set at 375 inches of water for a reference pressure. The output of the transmitter is the " loaf for Test Specimens 24A and B.

3.

Imtall a 120 VAC ASCO solenoid valve outside the chamber as a load for Test Specimem 32A and B.

WYLE LABORATORIES Muettvitie Pacility e

Attachment to WM 87-0309

?

Page.77 of 89 November 20, 1987 Qualification Plan No.17954-1 Page No.13 REV15 TON B 4.0 QUALIFICA'ITON PROGRAM (Continued) 4.8.2.1 Specimen Preparation (Continued) l 4.

Install a 125-VDC ASCO solenoid valve outside the test chamber as aload.

for Test Specimens 40A and B 5.

Provide a 3-phase 5 ampere (+10%). losa < < 520 VAC- (+10%,-0) for Specimens 48A, B, and C. This ciEcult shan ha fused at 7 amperes..

6.

The splices between the test specimen loam and their connectedloads shall be insulated with Raychem heat shrink tubing. Do not put R&ychem over the AMP test specimens.

7.

All test leads shall exit the top of the NEMA-1 box through a Myers Hub, a 900 elbow and 12" horizonti section of conduit. Do not seal the conduit.

Assure that there is a 1/4" drain hole in the bottom of the box.

8.

All test leads routed through the chamber penetrations shall be potted per Wyle Laboratories standard practies.

9.

Each cable shall be labeled for identification.

10.

Polaroid.and regular photographs shall be taken of the test specimens and the test setup.

11.

A wiring diagram shall be provided in the test report.

B 4.5.2.2 Powerhw 1.

Supply 132 VAC (+10%, -0%) across specimens 32A and B,137.5 VDC

(+10%, -0%) across specimens 40A and B, and 528 VAC (+3%, -0%) across 3

Specimens 48A, B, and C.

2.

Supply 28.4 VDC (+10%,-0%) and 375 in. H 0 (+10%) to the pressure 1

transmitter.

4.8.2.3 Instrumentation 1.

Three thermocouple shall be located in the environmental chamber within two inches of the surface of the NEMA 1 box and shall be util! zed to monitor the chamber temperature.

The individual readings shall be recorded and averaged, and the average traorded.

The thermocouple registering the highest temperature shall be used to control the chamber temperature during the initial ramp. The average of the values from the three thermocouple shall be tsed for control thereafter.

2.

Chamber pressure shall be monitored with an appropriate pressure sensing device. Results shall be recorded.

3.

Flow rate of the demineralized water spray shall be monitored by a flow meter. Results shall be recorded.

4.

Monitor and record the current into and out of the current loop containing Specimens 24A and B.

WYLE LA80RATORIEa Hunts e e Faemty l

Attachment to DE 87-0309 0

Page 78 of 69 November 20, 1987 Quallfleation Plan No. 17954-1 Page No.14 REVISION B' 4.0 QUALIFICA'110N PROGRAM (Continue 4 4.8.2.3, Instrumentation (Continued).

S.

Monitor and record the voltage and current for all other specimens.

6.

Monitor and record leakage' to ground for all test specimens. Continuously 3

monitor the peak leakage current (within equipment limitations) and rscord it at the intervals speelfled below:

7.

Measurements in steps 4 and 6 shall be made to three significant figures.

8.

The data acquisition system shall operate at its peak rate during theinitial ramp, then at 1 minute intervals for the first 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and then every 15 minutes thereafter. The data acquisition system shall operate at its peak' rate during each operational check of each specimen.

9.

A pen chart recorder shall also be provided to continuously monitor the chamber temperature.

4.9

' Pre-Aoeident Simulation PunctionalTest J

4.9.1 Thomas & Betts Nylon Wire Joints Apply power to the valve actuator first through Specimens 4A, B and C and then through 14A, B, and C.

Verify that the motor operates by monitoring the voltage, current and 11mit switch operation. Verify operability at both 528 YAC

(+10% -C% VAC) and at 408 VAC (+0%, -10% VAC). Record the results and compare to the acceptance criteria in Section 2.4.2.

4.9.2 AMP PVDF Butt Solfoss 1.

Apply 26.4 VDC power and 375 inches of water pressure to the transmitted.

Measure and record the output current. This value is the reference value for future functional testing.

2.

Apply power, as in Section 4.8.2.2 Step 1, to' the ASCO solenoid valves, verify that they change state, and ' monitor the voltage and current.

Record the results and compare to the acceptance criteria in Section 2.4.2.

3.

Apply power, as in Section 4.8.2.2 Step 1, to the 3-phase resistive load, monitor voltage and current, and verify that the 7 amp fuse did'not blow.

Record the results and compara to the acceptance criteria in Section 2.4.2.

4.10 Aceldent Simulation 4.10.1.

Thomas & Betts Hylon Wire Joints 3

WYLE LABORATORIES MWtsville Pacillfy

Attachment to WM 87-0309 Page 79 of 89 November 20, 1987 Quallfloation Plan No. 17954-1 Page No.15 REVISION B 4.0 QUALIFICATION PROGRAM (Continue 4

- 4.10.1.1 Temperature And Pressure, 3-l'.~5 tab 1112e the test chamber at 1500F (+10,-00P) and 100% relative humidit (on a best effort basis)for 30 minutes.

9 trdeot saturated steam and attain the initial ramp of Pgure 1 on a best effort basis.

B 3.

Envelope the profne of Pfgure 1 until 2070F is reached, then hold at 2070F until the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months point. Simulate the remaining 109 days by aging at 2070F -

for 121 hours0.0014 days 0.0336 hours 2.000661e-4 weeks 4.60405e-5 months .

B 4.10.1.2 Opersbuity Repeat the functional'tast of Section 4.9.1 when the temperature reaches 2A50F, B

and every hour from the first through 6th hour of the test, then once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at the 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months point, than once every day untu the end of the test, and again just prior to the completion of post-DBE aging.

4.10.1.3 Additional Testiar At the conclusion of 'the accident simulations Power will decide if additional samples need to be tested to the same or a reduced accident profue.

4.10.2 AMP PVDP Butt Solices 4.10.2.1 Tempeenture. Pressure And Spray 1.

Stabilize the test chamber e.t 900F (+10,-00P) for 30 minutes.

Irdeet superheated steam and attain the initial ramp of Figures 2 and 3 on a 2.

best effort basis.

3.

Envelope the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Figure 9 and fouow the " test profile" of Figure 3.

Initiate demineralized water spray at the rate of 1 gpm/sq.ft. at 10 4.

minutes and continue until 70 minutes. Anow the pressure to rise to saturated conditions.

5.

Simulate the remaining 109 days of the profue by aging the specimens at 3

2650F for 170 hours0.00197 days 0.0472 hours 2.810847e-4 weeks 6.4685e-5 months .

Notes Pigure 2 !s a composite curve of the conditform in Attachment 3. The pressure profile of Pigure 3 envalopes au the conditions in Attachment 3.

WYLE LABORAYOnlES Muntsyme Facd.ty O

i Attachment to WM 87-0309 Page 80 of 89 November 20, 1987 qualification Plan No. 17964-1 Page No.16 REVISION B 4.0 QUAIJFICATION PROGRAM (Continued)

I 4.10.2.2 ~. Operability-

- 4 Repeat the functional tests of Section 4.9.2 when the temperature reaches 34507, and every hour from the first through the 8th hour, then once every 8 5

{

hours for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then once every day until the end of the test, and again just

)

prior to the completion of post-DBE aging.

4.10.2.3 Additional Tutiar

(

A At the conclusion of the accident simulation IL Power will decide if a6didonal samples need to be tested to the same or a reduced accident profile.

4.11 Functional Tests A

Repeat the functional tests of Section 4.3 for informational purposes only.

4.12 Pcst-Test Inspectice The equipment shan be visuauy inspected. The equipment shan be dissambled to the extent necessary to perform the inspection. The condition of the equipment ahan be recorded..

4.13 In-Process Inspection All test specimens shan be examined for possible damage foHowing Sections 4.4, 4.6 and 4.10. An important results shall be logged.

Polarold and regular photographs shall be taken of any noticeable physical damage which may occur.

i WYLE LABORATORIES 5 HWnt9fil84 7& Cal 6ty e

LL *-

Attachment to WM 87-0309 I

.Page 81 of 89 November 20, 1987 Qualiftoation Plan No. 17954-1 Page No.17 S.0 QUALITY ASSURA.MCE All'. work performed on this program will be conducted in accordance with Wyle Laboratories' Quality Assurance Poliales and Procedures Manual, which conforms to the applicable ' portions of ANSI N45.2,10 CFR 50 Appendix B, and Military Specification MIL-STD-45662.

Standards utilized in the performance of all calibrations are traceable to the National Bureau of Standards.

8.0 REPORT Treport ihall be issued which shall describe the test requirements, procedures, and results. The report shan also include rationale and justification required for I

the test and shall describe those test items which passed the. tests. The customer shan receive three bound copies plus one reproducible copy of 'the report.-. Raw test data will be available for one year af ter program completion.

l wys.s Lamonatomas

%,i.e. p. cme, e

Attachment to WM 87-0309 Page 82.of 89 November 20, 1987 Qualification Plan No. 17954-1 Page I-1 REVE!ON A k

I Table I Aging Matrix ~

s 4

k...

Attachment to WM 87-0309 Page 83 of 89 November 20, 1987 I

QUALZF2CATTON PLAN 1*1954

- 1 R EtF T S T O N A PAGE NO I=

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MTUIA AE SENE MAT R!$E Ea REI 42 RL ggg g;g

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88tCtrD31A Tri31"H ICC 1.1 CCNhtC7CA 783 - INSLLATC4 1000 125 1.17 8.6E5 ELETRICAL 1.M ! 5 NYLCh - ZYT L 101 2

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1. I CABLE 1/C 16A'4 -

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Attachment to WM 87-0309 Pago 84 of.89 November 20, 1987

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QUAL 17ICATION PLAN 17954 1

REVISION A PAGE NO I-3 TABLE ! ASIW $7R!!

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!*I* NO I~D / % F C.RR CR!Ttq1A AATC 7pc sc N acD tedi.: ;#ei.:02*;;4 E181. 4 mittfaL AGE IDE 4At AISE la 487 as At!

SEI Wir s.o satics my 88t0: 2 4 454 Th434W st:

5.1 SAME As 4.1

5. I CARLI - 3/C Wh4 O(!*tTE/0N!Lth 1000W - SAME AB 4.2 l

l

Attachmant to WM 87-0309 Pago 85 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page IV-1 1

Table IV Specimen AssemWy and Mounting i

i I

l WYLE LABORATORIES 1

MWettydle Facil6ty e

\\

~~ Attachment to WM 87-0309 Pago 86'ofR89 November?20, 1987 Qualification Plan No. 17954-1

.... T a b l e I V.

Page No. IV-2.

ASSY. SPECIMEN.CONNECTCR C A B'_E CRIMPING LIFE NO, NUMBERS NUMBERS DESCRIPTION TCOL GOAL COMMENTS 1

1A,B.C a Ab-4 1/C 16AWG NOTE.1 18MC3 11A,B,C RC-6 1/C 12AWG NOTE 1 2

2A,B,C &

RB-4 1/C 16AWG NOTE 1.

3 YRS 12A,B,C RC-6 1/C 12AWG NOTE 1 3

3A.B C &

RB-4 1/C 16AWG MOTE 1 3YR$

13A,B C RC-6 1/C 12AWG NOTE-1 4

4 A,B, C &~

RB-4 1/C 16AW'G NOTE 1 SYRS 14A,B,C RC-6 1/C 12AWG NOTE 1 I

5 5A,B C &

RB-4 1/C 16AWG NOTE 1 40 YRS

)

15 A, B. C -

RC-6 1/C 12AWG NOTE 1 6

EA,B.C &

RB-4 1/C 16AWG NOTE 1 18MOS SPARES' 16A,B.C RC-6 1/C 12AWG NOTE 1 7

7A,3,c &

RS-4 1/C 16AWG NOTE 1 3 YRS SPARES 17A,B,C RC-6 1/C 12AWG NOTE 1 4

SA,B,C &

RB-4 1/C 16AWG NOTE 1 3 YRS SPARES j

18A B.C RC-6 1/C 12AWG NOTE 1 9

9A,B.C &

RS-4 1/C 16AWG NOTE 1 SYRS SPARES 19A,B,C RC-6 1/C 12AWG NOTE 1 10 10A,B.C &

RB-4 1/C 16AWG WOTE 1 40 YRS SPARES 20A,B,C RC-6 1/C 12AWG NOTE 1

)

11 21A&B 53549-1 TSP 16AWG NOTE 2 16MOS 29A&B 53550-1 2/C 19/25 NOTE 3 37A&B 53550-1 2/C 19/25 NOTE 3 45A,3&C 53550-1 3/C 9AWG NOTE 3 12 22ALB 53549-1 TSP 16AWG NOTE 2 3 YRS 30A&B 53550-1 2/C 19/25 NOTE 3 38A&B 53550-1 2/C 19/25 NOTE 3 46A,B&C 53550-1 3/C 9AWG NOTE 3 13 23A&B 53549-1 TSP 16AWG NOTE 2 SYRS 31A&B 53550-1 2/C 19/25 NOTE 3 39A&B 53550-1 2/C 19/25 NOTE 3

)

47A.B&C 53550-1 3/C 9AWG NOTE 3 14 24A&B 53549-1 TSP 16AWG NOTE 2 40 YRS 32A&3 53550-1 2/C 19/25 NOTE 3 40A&B 53550-1 2/C 19/25 NOTE 3 48A,B&C 53550-1 3/C 9AWG NOTE 3 i

d

' Attachment to WM 87-0309'

'Page 87 of'89 November-20, 1987 Qualification Plan No. 17954-1 Table IV Paca No. IV-3 REVISION A 1

ASSY. SPECIMEN CONNECTOR CABLE CRIMPING LIFE NO.

NUMEER3 NUMBER 2 DESCRIPTION TCOL COAL COMMENTS 15 25A&B 53549-1 TSP 16AWG NOTE 2 18MOS SPARES 33A&B 53550-1 2/C 19/25 NOTE 3 41A&B 53550-1 2/C 19/25 NOTE 3 49A.B&C 53550 '

3/C 9AWG NOTE 3 16 26A&B 53549-1 TSP 16AWG NOTE 2 3 YRS SPARES 34A&B 53550-1 2/C 19/25 NOTE 3

'42A&B 53550-1 2/C 19/25 NOTE 3 SOA,B&C 53550-1 3/C 9AWG WOTE 3 17 27A&B 53549-1 TSP 16AWG NOTE 2 SYRS SPARES 35A&B 53550-1 2/C 19/25 NOTE 3 43A&B 53550-1 2/C 19/25 NOTE 3 51A,8&C 53550-1 3/C 9AWG NOTE 3 18 28A&R 53549-1 TSP 16AWG WOTE 2 40VRS SPARES 36A&B 53550-1 2/C 19/25 NOTE 3 44A&B 53550-1 2/C 19/25 NOTE 3 I

52A,3&C 53550-1 3/C 9AWG NOTE 3 NOTE 1:

USE AN APPROPRIATE WYLE CRIMPING TOOL.

NOTE 2:

USE AMP TOOL NUMBER 47387.

NOTE 3:

USE AMP TOOL NUMBER 59239-4.

MOUNTING:

1-ASSEMBLY 4 WILL BE MOUNTED IN THE COVER OF THE VALVE ACTUATOR AFTER THE COVER HAS BEEN REMOVED.

CONNECTORS 4A AND 14A SMALL I

BE MOUNTED ON THE OPPOSITE ENDS OF THE COVER WITH THE OPEN ENDS l

l UP.

CONNECTORS 4B&C AND 148&C SHALL BE MOUNTED AT OPPOSITE ENDS OF THE BOTTOM OF THE COVER.

REMOVE THE PAINT FROM THE AREAS WHERE THE SPECIMENS ARE TO BE ATTACHED TO THE COVER.

2-THE FOLLOWING PAIRS OF ASSEMBLIES SHALL BE MOUNTED ON FIXTURES

.TO PROTECT THEM DURING IRRADIATION AND THERMAL AGING:

3&& 11&l5 1&6 2&7 S&10 12&16 AFD 13&17.

ASSEMBLIES 9 AND 18 SHOULD BE ON SEPARATE' FIXTURES.

3-ASSEMBLY 14 SHALL BE MOUNTED INSIDE A NEMA 1 BOX WITH A DRAIN HOLE.

THE SPECIMENS WITH THE SAME NUMBER PORTION SHOULD TOUCH EACHOTHER AND THE GROUND PLANE.

Attachment to WM 87-0309

^

i Page 88 of 89 November 20, 1987 Qualification Plan No. 17954-1 Page F-1 1

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ML20236Y234

Text

Subject:

Dear Mr. Martin:

References:

Background

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O et eV at et at et nW et et e

Reference:

Reference:

==

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