ML20040F335

Forwards Qualification Documentation for Auxiliary Feedwater safety-grade Automatic Actuation & Flow Indication Sys, Reactor Coolant Venting Sys, & Listed Monitors & Level Indication Sys,Per NUREG-0737

ML20040F335
Person / Time
Site:	Fort Calhoun
Issue date:	02/01/1982
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Clark R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 LIC-82-043, LIC-82-43, NUDOCS 8202090091
Download: ML20040F335 (8)

Text

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9-Omaha Public Power District 1823 HARNEY a OMAHA. NEBRASKA 68102 m TELEPHONE 530 4000 AREA CODE 402 February 1, 1982 LIC-82-043 e\\*

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Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission

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Office of Nuclear Reactor Regulation

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Reference:

Docket No. 50-285 V7 -

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Dear Mr. Clark:

5 to the Omaha Public Power District's letter dated August 26, 1981 provided the District's schedule for submitting environ-mental qualification documentation for electrical equipment installed under TMI Action Plan (NUREG-0737) requirements. Attached please find qualification documentation for the auxiliary feedwater safety grade automatic actuation and flow indication systems, the reactor coolant venting system, the containment high range radiation and hydrogen monitors, the pressurizer level indication, the containment sump level indication, containment wide range pressure monitor, and the safety injection pump leakage detection system. Qualification infonnation for the majority of the equipment components is not complete because the vendors are still in the process of conducting qualification tests.

Although the qualification testing is not complete, the vendors have assured the District that the installed components will meet the criteria of IEEE 323-1974, based on pre-test analysis and testing results to l

date. The schedule for submitting the additional qualification inform-ation is provided in the attachment.

l Also attached is an updated Enclosure 13, " Outstanding Items", to the District's August 26, 1981 letter, which indicates that aging and chemical concentration qualification documentation is necessary to complete the qualification of the Conax seals for the reactor coolant venting system.

Sinc r ly, OY 8282090091 820201

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C.Qones DR ADOCK 05000285 Divisf6nManager

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p PDR Production Operations WCJ/KJM/TLP/RWS:jmm

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Attachment cc:

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C.

20036

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Auxiliary Feedwater (AFW) Modification The safety grade actuation system for AFW incorporates the use of eight (8) Foxboro pressure transmitters (Model #N-E11GM-IIEl-AFL) and eight (8) Foxboro level transmitters (Model #N-E13DM-IIH-1-AFJL). The 4

AFW safety grade flow indication system utilizes two (2) Foxboro flow indication transmitters.

These Foxboro transmitters presently meet IEEE 323-1971 criteria and are being tested to meet IEEE 323-1974 standards.

It should be noted the vendor who supplied the transmitters has provided assurance that the transmitters will meet IEEE 323-1974 criteria, based on pre-test analysis. Once the test results are obtained, the System Component Evaluation Work Sheets (SCEWS') will be submitted.

The AFW system also uses four (4) Asco solenoid valves (Cat.

1. NP8314C29E 125 VDC), one (1) Asco solenoid valve (Cat. #NP8314C29E 120 VDC), two (2) Asco solenoid valves (Cat. #NP8320A185V 125 VDC), and two (2) Asco solenoid valves (Cat. #NP8320A175E 125 VDC). The Asco solenoid valves are presently being tested for compliance with IEEE 323-1974 4

qualification criteria. SCEWS' will be submitted when the testing is

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completed.

The AFW system also incorporates the use of fourteen (14) Namco limit switches (Part #EA180-11302).

The qualification testing is complete and meets the requirements of IEEE 323-1974, 344-1975, and 382-1972. The SCEWS' will be provided in sixty (60) days.

All splice or seal interfaces installed meet applicable standards.

Raychem splices have been qualified to IEEE 323-1974.

SCEWS' will be submitted within sixty (60) days documenting the qualification.

Reactor Coolant System Vent Modification The reactor coolant vent system uses a Target Rock solenoid valve (Model #80B-001-7). The qualification test report, Report #2375.C, (for 4

aging, seismic and accident simulations) for this solenoid valve is complete and demonstrates that it meets the requirements of IEEE 323-1974, 344-1975, and 382-1972. A SCEWS for this solenoid valve is attached.

All cable splices and interconnecting cables utilized for this system meet the qualification requirements of IEEE 323-1974. Raychem splices have been qualified to IEEE 323-1974. All of the interconnect-ing cables used for the reactor coolant system vents are CQE qualified, as specified by Class 1E equipment qualification (IEEE 323-1974 and IEEE 383). The SCEWS' which document the new cable and splice qualification will be submitted within sixty (60) days.

The Conax seal utilized is qualified for in-containment appli-cations during normal and abronnal conditions, including seismic, MSLB and LOCA design basis events, and is qualified to the requirements of IEEE 323-1974 and IEEE 344-1975.

However, the District needs to obtain information from the Conax Corporation verifying the boron concentration

. of the chemical spray used in the qualification tests. Conax is also verifying the aging qualification of the seals. A SCEWS containing the available qualification information is attached. When the District receives the remaining qualifica+1on data, the SCEWS will be updated to indicate the verified information.

Accident Monitoring Instrumentation The Fort Calhoun Station accident monitoring instrumentation i

incorporates the use of Consip, Inc. hydrogen analyzers (the Delphi IV hydrogen analyzer). The qualification testing is complete and the monitor meets the requirements of IEEE 323-1974. The District is com-pleting its final evaluation of the radiation dose test value.

The SCEWS' will be submitted within sixty (60) days.

The accident monitoring system also incorporates the use of a Valcor isolation valve (soler.Jid operated, Model fV526-5891-15) and several other Valcor isolation valves (solenoid operated, Model #V526-5295-68). The qualification testing is complete and the valves meet the requirements of IEEE 323-1974. The SCEWS' will be submitted within sixty (60) days.

The instrumentation also incorporates the use of Asco solenoid valves (Model #X206-381-6RF). The qualification testing (Asco Test Report #A0521678KR REVA) is complete and the valve meets the require-ments of IEEE 323-1974. The SCEWS' will be provided within sixty (60) days.

The qualification testing of the Class 1E Victoreen high range containment radiation area monitor system is complete.

The monitor meets the requirements of IEEE 323-1974.

The District is completing. its final evaluation of the radiation dose qualification.

The SCEWS' will be submitted within sixty (60) days.

All Raychem interfaces in splices or seals have been qualified to i

IEEE 323-1974.

SCEWS' will be submitted within sixty (60) days.

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Pressurizer Level Indication

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4 The pressurizer level indication incorporates the use of Foxboro level transmitters. These Foxboro transmitters meet IEEE 323-1971 criteria and are presently being tested to meet IEEE 323-1974 standards.

It should be noted that Foxboro has provided assurance that the trans-mitters will meet IEEE 323-1974 criteria, based on pre-test analysis.

The District will submit the SCEWS' when the test data are available.

All. interfaces in splices or seals have been qualified to IEEE 323-1974.

SCEWS' will be submitted within sixty (60) days.

Containment Sump Water Level Modification The containment sump water level transmitters incorporate the use of GEMS' level transmitters. These GEMS transmitters, at the present time, do not have completed qualification documentation as required by IE Bulletin 79-01B for TMI-2 action items. Wyle Laboratories is in the s'

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process of completing the final IEEE 323-1974 qualification testing of these level transmitters (reference Wyle Laboratories Qualification Plan 45102-01). The District will submit the SCEWS' af ter the qualification testing is completed in June 1982.

All of the interconnecting cables used are CQE qualified cablet, as specified by Class IE equipment qualification (IEEE 323-1974 and IEEE 383). The transmitters and interconnecting cables are the only electrical equipment used in this modification that could be exposed to a harsh environment. The District will provide the qualification test reports upon receipt from Wyle Laboratories.

All' interfaces in splices or seals have been qualified to IEEE 323-1974. SCEWS' wil,1 be submitted within sixty (60) days.

Containment Wide Range Pressure Monitor he containment presdure monitor use's Foxboro pressure transmitters.

ThqselpressGretransmittersmeetIEEE 323-1971 qualification criteria and'are prp ently being tested for compliance with IEEE 323-1974.

Foxboro has ass'ured the District that the subject pressure transmitters

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will meet the criteria of IEEE 323-1974, based on pre-test analysis.

The District will suMit the SCEWS' when the qualificaticn testing is completed.

All splice or seal interfaces have bee qualified to IEEE 323-1974.

-The SCEWS' will be submitted within sixty (60) days.

,r Safety Injection Pump leakage Detection System

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The SI pump leakage detection hs't'em is hr,esently being installed as part of the plant shielding modf fhation.,' The District's letter

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dated December 28, 1981 provided the schedule for completion of this modification, which is expected to be April 30, 1982. This system utilizes GEMS' level transmitters which, at the present time, are undergoingMEEE 323-1974 qualification testing at Wyle Laboratories.

s The Distriedwill sNbmit the SCEWS' 'af ter the qualification testing is completed.

All interconnecting cables are CQE quElified and meet the quali-fication criteria of IEEE 323-1974 and IEEas383.

SCEWS' will be pro-s vided within sixty (60) days.

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Facility:

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Docket No.: 50-285'

' #0 y/A SYSTEM COMPONENT EVALUATON WORK-SFRET m

50CUMENTATON; JEFE

,, CATION ING 4 3

ENVIRONMENT N

QUALIFI-OUTSTAND' EQUIPMENT DESCRIPTION Specifi-Qualif-Speci fi-Qualifi-

<METil0D e,

ITEMS Parameter cation cation cation cation System: Electrical Equipment Operating

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2 Analysis NONE Time Continuotj s Continuot,s' Item N,o.: CONAX Electrical Conductor Seal Assemblies Tempera-ture *F 305*F 340*F 1

2 Type Test N_0NE '

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s Component: All Pressure C

D Manufacturer: CONAX d

Relative Model No.: N/A Ilumidity %

100%

100%

1 2

Type Test NONE Boron & NA0il Function: Sealing of wires for Chemical 1700 ppm Pli of 10.5 mtrs, L-Switches, pps, inst, vv Spray Boron 1

Note 4 Type Test.

NONE oper, inst transmtrs, etc.

Accuracy - Spec: N/A Note 1 8

Demon: N/A Radiation Note 1 2x10 R 1

2 Type Test NONE Service: See function Location: Containment Aging Note 4 Note 4 Note 4 Note 4 Note 4 NONE Flood Level Elev:

1000.9' Submer-Type Test Above Flood Level: Note 2 gence Note 3 Note 3 Note 3 Note 3 Note 3 NONE Documentation

References:

Notes:

7

1) Enclosure #1.

1) Worst Case containment 3x10 R

2) CONAX Qualification Report,

2) See limit switch SCEW sheets for flood information No. IPS-409 & IPS-325

3) Units are sealed units, See enclosure 13, Item 4.

.4)

See enclosure 13, Item 15.

Present Qualification:

..l IEEE 323-1974 J

Facility: Fort Calhoun 1 Docket No.:

50-285 SYSTEM COMP 0NENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATION REF.

QUALIFI-OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi-Qualif-Specifi-Qualifi-METHOD ITEMS Parameter cation cation cation cation l

System: Reactor Coolant Operating Available Available l

Time during Post during Post 1

2 Type Test NONE Item No.: HCV-176, 177, 178, accioent accident 179, 180, 181 Tempera-ture F 305 F 385 F 1

2 Type Test NONE Component: Solenoid Valve Pressure PSIg 60 PSIg 66 PSIg 1

2 Type Test NONE Manufacturer: Target Rock Corporation Relative Model No.: 80B-001-7 Humidity %

100%

90%

1 2

Type Test NOTE 2 Function: Reactor Coolant Chemical 1700 ppm 6200 ppm System Vent Spray Boron Boron 1

2 Type Test NONE Accuracy - Spec: N/A Demon: N/A Radiation Note 1 3.53x10 Rds 1

2 Type Test NONE 7

Service: Reactor Coolant System Vents 18,000 Location: Containment Aging Cycles 40 years 3

2 Type Test NONE Flood Level Elev:

1000.9' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation

References:

Notes:

5 5

1) Enclosure #1.

1) HCV-177, HCV-176, 9.90x10 with possible sector OSN 1.92x10,

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2) Qualification Test Report No. 2375.C HCV-178, 179, 180, 181, 1.92x10 Rads, Sector, O.

3) IEEE 382

2) The District is presently evaluating the 90% humidity test.

Due to the valves LOCA qualification, no qualification Present Qualification:

problems are anticipated.

323-1974

b o 3 Outstanding Items

. 1.

The aging and qualified life maintenance program will be implemented by June 30, 1982.

2.

FT-236 will be relocated to a " normal room environment" by the end of the 1981 refueling outage.

3.

The Conax penetration testing will be completed by June 30, 1982.

4.

The District is investigating the moving of all safety related electrical equipment above the flood level in containment.

This investigation will be completed by the end of the 1981 refueling outage.

5.

The District plans to re-evaluate the radiation dose received by equipment just above the containment flood level.

This will be completed by June 30, 1982.

6.

In investigating the effects of chemical spray, the FSAR value of 1700 ppm boron was used.

In discussions with the plant staff, the concentration for the Safety Injection and Refuel-ing Water Storage Tank is maintained at up to 2500 ppm boron.

The District feels that this will not effect the equipment, however, the question is being re-evaluated.

This will be completed by June 30, 1982.

7.

To insure proper evaluation of the radiation effects in contain-ment, the District requests the NRC's concurrence on its use of the D0R guidelines to establish containment radiation doses.

8.

The District plans to do plant specific radiation calculations for Auxiliary Feedwater Valves HCV-1107A and HCV-1108A due to their proximity to the RCS.

The District plans to do plant specific calculations for VA-3A and VA-38 due to their proximity to the charcoal filters.

This will be completed by June 30, 1982.

9.

The District will complete evaluation of FT 416, 417, 418, and 419 by June 30, 1982.

10.

The District plans to complete testing of the Fisher 304 limit switch by June 30, 1982.

11.

The replacement of the limit switches in containmer.t and Valcor solenoid valves in containment will be completed by the end of the 1981 refueling outage.

12.

The solenoid valve and limit switch in the auxiliary building will be replaced by June 30, 1982.

13-1 R6 1/25/81

.. 3-Outstanding Items (Continued) 13.

TE 866 and TE 867 will be replaced during the first refueling outage after receipt of qualified parts.

14.

Qualified Safety Related Equipment will be identified and marked with orange in the control room and operator training will be completed by June 30, 1982.

15.

Conax Corporation is in the process of verifying by letter,

-the' Chemical Concentration Qualification and will provide the Parts Per Million Concentration of Boron that was used in testing.

Conax Corporation is in the process of verifying by letter, the Aging Qualification of their Conax seals.

The SCEW sheets will be revised no later than 3/13/82.

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