ML20052D906

Forwards Pages 6-59A,6-78 & 6-78B to Sys Component Evaluation Worksheets for Conax Electrical Seal Aging & Chemical Spray Qualification & Containment Hydrogen Analyzer Valcor Isolation Valves Per 820325 & 0402 Ltrs

ML20052D906
Person / Time
Site:	Fort Calhoun
Issue date:	05/03/1982
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Clark R Office of Nuclear Reactor Regulation
References
IEB-79-01B, IEB-79-1B, LIC-82-187, NUDOCS 8205070301
Download: ML20052D906 (6)

Text

s Omaha Public Power District 1623 HARNEY '

OMAMA. NEBRASMA 68102 8

TEL EPHON E 536 4000 AREA CODE 402 May 3, 1982 LIC-82-187 x

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Mr. Robert A. Clark, Chief

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A U. S. Nuclear Regulatory Commission I

S193 F I Office of Nuclear Reactor Regulation C

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Division of Licensing O

Operating Reactors Branch No. 3

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6 Washington, D.C.

20555

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Reference:

Docket No. 50-285

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Subject:

Environmental Qualification of Safety-Related Electrical Equipment at the Fort Calhoun Station The Omaha Public Power District's letters dated March 25, 1982 and April 2,1982 stated that System Component Evaluation Worksheets (SCEWS) for the Conax electrical seal aging and chemical spray qualification and for the containment hydrogen analyzer Valcor isolation valves would be provided by May 1, 1982. Accordingly, attached pages 6-59A, 6-78, and 6-788 provide the subject information. A revised Enclosure 13 to the District's qualification package, which reflects the most current information regarding outstanding items, is also attached.

The attached SCEWS and revised Enclosure 13 should be incorporated into the Dis-trict's qualification package transmitted to the Commission by letter dated August 26, 1981.

The District is aware of proposed regulations to extend the completion date for environmental qualification of safety-related electrical equipment beyond June 30, 1982. Several outstanding items to Enclosure 13 have completion dates of June 30, 1982, based on this requirement.

If the date for environmental qualification is extended, the District may request extension of the completion date for several of these items.

Sincergly, fdp__J g$

W. C. Jones 3

DivisidnManager Production Operations

j Attachments cc

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

Washington, D.C.

20036-8205070301 820503 PDR ADOCK 05000285 p

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Facility: Fort Calhoun 1 Docket No.:

50-285 C-300 SYSTEM COMPONENT EVALUATION WORK SHEET thv1Rohtith I DOCUMENTATON QUALIFI-OUTSTAND CATION ING EQUIPMENT DESCRIPTION Specifi-Qualif-Speci fi-Qualifi-METHOD ITEMS Pa ramete r cation cation cation cation System: Electrical Equipment Operating Time Continuoo s Continuoo s 2

Analysis NONE Item No.: CONAX Electrical Conductor Seal Assemblies Tempera-ture 'F 305*F 340 F 1

2 Type Test NONE Component: All Pressure

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PSIg 60 PSIg 75 PSIg 1

2 Type Te'st NONE Manufacturer: CONAX Relative Model No.: N/A Humidity %

100%

100%

1 2

Type Test NONE Re rce E "?.0!i Function: Sealing of wires for Chemical 1700 ppm Ph of 10.5 ctrs,'L-Switches, pps, inst, vv Spray Boric Acid 3000 ppm 1

3 Type Test NONE 7' -

oper, inst transmtrs, etc.,

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' Accuracy - Spec: N/A Note 1 8

3" Demon: N/A Radiatior.

Note 1 2x10 R 1

2 Type Test NONE q

Service: See function

!j Location: Containment Aging N/A 40 yrs N/A 3

Type Test NONE i

ll Flood Level Elev:

1000.9' Submer-

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Above Flood Level: Note 2 gence N/A N/A N/A N/A N/A NONE if

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Documentation

References:

Notes:

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1) Enclosure #1.

1) Worst Case containment radiation equals 3x10 R q

2) CONAX Qualification Report,

2) See Item 4, Enclosure 13, for those limit switches No. IPS-409 & IPS-325 that will be moved above the submergence level.

23

3) CONAX letter from W. C. Fredrick to R. F. Mehaffey (OPPD) 1" a,

dated Feb. 5, 1982

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Present Qualification:

@3 IEEE 323-1974 4571/f-82/g 6

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Ftcility: Fort Calhoun 1 Dockzt No.: 50-285 R7-1

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SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON QUALIFI-OUTSTAND ~

CATION ING EQUIPMENT DESCRIPTION Specifi-Qualif-Specifi-Qualifi-METl!0D ITEMS Parameter cation cation cation cation 2 Analyzer Operating 45,000 System: H Time 1000 hrs cycles Note 1 2

Type Test NONE Item No.: HCV 820A HCV 821A Tempera-HCV 883B ture *F N/A N/A N/A N/A N/A NONE HCV-884B Component: Solenoid Valve Pressure PSIg N/A N/A N/A N/A N/A NONE Manufacturer: Valcor Relative Model No.: V 52660-5295-68 Humidity %

N/A N/A N/A N/A N/A NONE Function: H2 Analyzer Iso Chemical NA N/A N/A N/A N/A NONE is valves Spray f

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Accuracy - Spec:

N/A 5

8 Demon: N/A Radiation 8x10 R 2x10 R 1

2 Type Test NONE

>I Service: See function Location: Room 59 Aging N/A 40 yrs N/A 2

Type Test NONE Flood Level Elev: N/A Submer-Above Flood Level:

gence N/A N/A N/A N/A N/A NONE

,t Documentation

References:

Notes:

1) " Implementation Methods and Schedules for

1) See Enclosure #14 NUREG-0578" Section 2.1.6B Page 18, Fig. 4.2-3 (December.1979) 3g

2) Valcor Qual. Report QR52600-5940-2 g'J5 Present Qualification:

Q3 IEEE 323-1974 3

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4571/f-86/g

Fc'cility: Fort Calhoun 1 Dockat No.: 50-285 Cl-29 SYSTEM COMPONENT EVALUATION WORK SHEET EaVIR0natat DOCUMENTATON QUALIFI-OUTSTAND CATION ING EQUIPMENT DESCRIPTION Specifi-Qualif-Specifi-Qualifi-METHOD ITEMS Parameter cation cation cation cation System: H2 Analyzer Operating 45,000 Time Continuot s cycles 1.

2 Type Test NONE Item No.: HCV 820B HCV 821B Tempera-ture 'F 305*F 346 F 1

2 Type Test NONE Component: Solenoid Valve Pressure PSIg 60 PSIg 113 PSIg I

2 Type Test NONE Manufacturer: Valcor Relative Model No.: V 526-5891-15 Humidity %

100%

100%

1 2

Type Test NONE Perer ac:d

-Function: Hg Analyzer Iso Chemical 1700 ppm 9.5-10.5 ph valves Spray Boron Note 1 1

2 Type Test NONE og da

@8 4ccuracy - Spec: N/A 5

8 Demon: N/A Radiation 5.82x10 R 2x10 R 1

2 Type Test NONE Service: See function Location: Containment Aging N/A 40 yrs N/A 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

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Documentation

References:

Notes:

1) Enclosure #1.

1) The only materials exposed to the spray solution are

2) Valcor Qual. Test Report QR52600-5940-2 type 316 stainless steel (body), nickel plating

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(solenoid shell and cover), and the ethylene pro-pylene 0-rings which seal the interior solenoid I.

assembly from the environment.

Present Qualification:

IEEE 323-1974 4571/f-85/g

> 3 Outstanding Items 1.

The aging and qualified life maintenance program will be imple-mented by June 30, 1982.

2.*

FT-236 was relocated from a harsh environment to a " normal room environment" (the corridor outside of Room 13) during the 1981 refueling outage.

3.

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

4.

The District has completed a submergence evaluation and expects to move the following electrical equipment above the flood level in containment during the 1982/1983 refueling outage:

Limit Switches and Solenoids Limit Switches Only Flow Transmitters HCV-467A HCV-238 FT-313 HCV-467C HCV-239 FT-316 HCV-438A FT-318 HCV-438C FT-322 HCV-1387A HCV-138EC 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 Refueling 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 has completed the radiation calculations for Auxiliary Feedwater Valves HCV-1107A and HCV 1108A due to their proximi-ty to be4.96x10gasdeterminedthattheintegrateddosereceivedwould the RCS and RADS.

This valve is much lower than the radiation qualification dose for these valves of 2.04 x 108 RADS.

The District has completed the radiation calculations for VA-3A and minedthattheintegrateddosereceivedwouldbe8.64x10gsdeter-VA-38 due to their proximity to the charcoal filters and h RADS.

This valve is much lower thag the radiation qualification dose for these fan motors of 1.0 x 10 RADS.

9.

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

13-1 R8 5/3/82

s 3 Outstanding Items (Contir.ued) 1

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

11.* The limit. switches and Valcor solenoid valves in containment were replaced with environmentally qualified components during the 1981 refueling outage.

12.* The solenoid valves and limit switch in the auxiliary building were replaced with environmentally qualified components during the 1981 i

refueling outage.

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. The District is in the process of verifying the 100 day dose qualification for the Accident Monitoring Instrumentation Modi-fications items.

• These items are complete.

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