ML20209B782

Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee

ML20209B782
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/01/1999
From:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-MA3636, TAC-MA3637, TACMA3636, VPN-056-99, VPN-56-99, NUDOCS 9907080123
Download: ML20209B782 (8)

Text

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L PGE - a- m-* c-Trojan Nuclear Plant 71760 Columbia Rur Huy I

Rainier oR 97048 (503)556-3713 i

July 1,1999 VPN-056-99 U. S. Nuclear Regulatory Commission ATfN: Document Control Desk <

Washington,DC 20555

Dear Sir:

Response to Request for Additional Information j Regarding License Change Application (LCA) 244 and i Accompanying Request for Exemption (TAC NOS. MA3636 and MA3637)

This letter responds to Nuclear Regulatory Commission (NRC) letter dated June 9,1999, l

" Request for Additional Information [RAI] Regarding License Change ApplSation 244 and l

Accompanying Request for Exemption (TAC NOS. MA3636 and MA3637)." As requested in the NRC's RAI, this letter provides a detailed breakdown to support estimation of radioactive i material that will remain on the Trojan Nuclear Plant site after the removal of the spent' nuclear i fuel and the reactor vessel and internals (reactor vessel package) from the 10 CFR 50 licensed area. The detailed information herein supports an estimation of remaining radioactive material previously provided by Portland General Electric Company (PGE) letter VPN-014-98,

" Exemption Request and License Change Application (LCA) 244; Deletion of Emergency Plan Requirements from Part 50 License After Fuel Movement to the ISFSI and Reactor Vessel and Intemals Removal," dated August 27,1998. {l PGE's exemption request states that after the removal of spent nuclear fuel and the reactor vessel package from the 10 CFR 50 licensed area, the remaining radioactive material would be comprised of approximately 423 Ci of activated material within the concrete bioshield wall, 415 Ci of sealed source material, and 36.7 Ci of contaminated materials within plant systems. .o\

The NRC's June 9,1999, RAI encompassed three questions related to this information on -

l remaining radioactive material. These questions and PGE's response to each question are provided below.

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' L Page 2 0f 4 L RAI Item 1 The documentation should be given in radio-isotopi rm to allow comparison with the l' inventory ofradioactive materials specified in 10 CFR 'J0. 72, " Schedule C - Quantities of Radioactive Materials Requiring Consideration ofthe Needfor an Emergency Planfor Responding to a Release. "

PGE Response to RAI Item 1 A breakdown by radionuclide of the radioactive material amounts that are estimdted to remain after the removal of the spent nuclear fuel and the reactor vessel package from the l 10 CFR 50 licensed area is provided in Attachment 1. This breakdown includes radioactive material in activated concrete; plant systems and structures; radioactive sources; and fluids, filters, and other operational sources.

l As indicated in Attachment 1, the estimated amount of contaminated materials within plant systems and structures has been reduced from 36.7 Ci, as previously submitted, to approximately 11.2 Ci. This reduction reflects the continning removal of contaminated systems, as well as an updated estimate of spent fuel pool surface contamination. The l revised spent fuel pool surface contamination estimate is based on radiological survey L data obtained from a spent fuel storage rack removed from the spent fuel pool.

l Attachment I also provides a comparison by radionuclide of the radioactive material, as projectd to remain after the removal of spent nuclear fuel and the reactor vessel package from the 10 CFR 50 licensed area, with the 10 CFR 30.72 Schedule C quantities. For i each radionuclide, the total activity projected to remain in the 10 CFR 50 licensed area is i divided by the quantity for that radionuclide as listed in 10 CFR 30.72 Schedule C. The resulting ratio for each radionuclide, as well as the sum of the ratios of all the listed <

radionuclides, indicates that the total remaining quantities of radioactive materials will be

- well below the quantities specified in 10 CFR 30.72 Schedule C.

RAIItem 2 Radioactive materials in sealedform are excluded in the compilation ofradioactive materialsfor comparison with the inventory in Schedule C by 10 CFR 30.32(i)(1). Therefore, provide a separate listing ofsealedsource materials, i.e., appropriate portion ofthe 415 Cl indicated in l the exemption request. l l

.PGE Response to RAI Item 2- j Attachment 2 to this letter provides a listing of radioactive material sources maintained at

- the Trojan Nuclear Plant as of the date of this letter. This listing of sources reflects the

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l acquisition and removal of various radioactive sources since PGE's August 27,1998, exemption request.

The radioactive source inventory provided in Attachment 2, Table 1, includes six sources specifically identified as scaled sources. These six sealed sources contain 415.06 Ci, or approximately 99.9% of the radioactive material currently maintained on the Trojan Nuclear Plant site in the form of radioactive sources. As sealed sources, these sources are excluded by 10 CFR 30.32(i)(1) from the compilation of radioactive source material for comparison with 10 CFR 30.72 Schedule C quantities.

In addition to the six sealed sources discussed above,122 other radioactive sources are currently maintained on the Trojan Nuclear Plant site. Listed in Attachment 2, Table 2,  !

by radionuclide, some of these sources may be scaled sources and therefore could be excluded from comparison with 10 CFR 30.72 quantities. However, the effort necessary to review all 122 sources to identify the specific type of each source was determined to be l not warranted considering the minimal amount of radioactive material represented by I these sources.

i Containing only approximately 0.44 Ci, or about 0.1% of the radioactive material i currently maintained on the Trojan site in the form of radioactive sources, these 122 sources are included in the comparison with 10 CFR 30.72 Schedule C quantities. The results of this comparison, incorporated into Attachment 1, indicates that the total l quantities of radioactive materials, including those from radioactive sources not excluded by 10 CFR 30.32(i)(1), will be well below the quantities specified in 10 CFR 30.72 i Schedule C follow' m g the removal of spent fuel and the reactor vessel package from the 10 CFR 50 licensed area.

RAI Item 3 Onlyfixed radioactive materialis addressedin the exemption request. Indicate whether or not the quantity ofradioactive materialin the waste storagefacility andfrom other operational sources (e.g., radioactivefluids, filter media, resins) has been accountedfor in the inventory of remaining radioactive material.

PGE Response to RAI Item 3 As indicated in Attachment 1, an estimated 118 Ci of radioactive material from operational sources has been added to the total estimated quantity of radioactive material.

The sources of this material are the spent fuel pool water and associated filters and resin, i which are anticipated to be removed from the site shortly after the fuel is removed from the 10 CFR 50 licensed area. Radioactive material in water and other media from sumps, floor drains, and other decommissioning activities is accounted for under the category I

VPN-056 99

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" contaminated materials within plant systems"in PGE's August 27,1998, exemption request, as updated in PGE's response to RAI Item 1 above.

Attachment I provides a breakdown by radionuclide of the estimated 118 Ci of radioactive material from operational sources under the heading " Fluids, Filters, etc."

This radioactive material is included in the comparison by radionuclide with the 10 CFR 30.72 Schedule C quantities as provided in Attaciunent 1. This comparison indicates that the total quantities of radioactive materials, including those from operational sources, will be well below the quantities specified in 10 CFR 30.72 Schedule C following the removal of spent fuel and the reactor vessel package from the 10 CFR 50 licensed area.

This letter is submitted under oath and affirmation as required by 10 CFR 50.30(b). Also attached is one signed copy of a Certificate of Service to the Chief Executive of the County in which the facility is located and to the Director of the Oregon Office of Energy. If you have any questions regarding this correspondence, please contact Mr. Lanny Dusek of my staff at (503)556-7409.

Sincerely,

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Stephen M. Quennoz Vice President Nuclear and Thermal Operations Attachments c: L. H. Thonus, NRC, NRR S. Roudier, NRC, NRR Director, NMS, NRC Region IV D. Stewart-Smith, OOE A. Bless, OOE

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Attachment 2

' WPN-0.56-99 )

- July 1,1999 Page1of1 TROJAN RADIOACTIVE SOURCE LISTING Table 1 Sources Specified as Sealed Sources Nuclide Number of Sources Curies Largest Source (Ci)

Cs-137 3 406.13 400.13 Pu-238 1 8 8 Am-241 1 0.77 0.77 1 Cm-244 1 0.16 0.16 TOTAL 6 415.06 N/A  !

Table 2 l I

Sources Other Than Those Specified as Sealed Sources

. Nuclide Number of Sources Curies Largest Source (Ci) 11-3 2' 4.480E-7 2.250E-7 C-14 l' 2.250E-7 2.250E-7 Cl-36 6 1.200E-5 2.000E-6 Co-60 10 8.482E-6 4.980E-6 Ni-63 4 1.500E-2 1.000E-2 Sr-90 18 3.299E-5 1.000E-5 Tc-99 15 3.727E-7 1.500E-7 Ba-133 8 4.147E-6 1.560E-6 Cs-137 3 26 4.233E-1 1.13E-1 TI-204 1 5.000E-4 5.000E-4 Th-230 . 1 5.000E-9 5.000E-9 Pu-239 5 3.762E-7 3.40E-7 Am-241 2 26' 3.368E-5 3.136E-6 l TOTAL 122 4.389E-1 N/A

' includes I mixed nuclide source.

6 includes 2 mixed nuclide sources.

• Includes several sources with mixed ga:nma contributors.

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STATE OF OREGON, )

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COUNTY OF COLUMBIA )

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I, D. L. Nordstro.m, being duly sworn, subscribe to and say that I am the General Manager, Plant Support and Technical Functions, for Portland General Electric Company, the licensee herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.

Date fu / ,1999 l

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ITL. Nordstrom, General Manager, Plant Support and Technical Functions Portland General Electric Company On this day personally appeared before me, D. L. Nordstrom; to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act.

GIVEN under my hand and seal this / day of c(>_A< ( ,1999.

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omcatsEAL gf 9 FATscNArraAN nepusuc OREGON canassout3N8 urcmaaSSON EMESMN.m Notary %bh. .cm State of Ore r the Residing at fN//d//L.2 My commisNTon expires 7-a y,=;te$

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of _  ;

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PORTLAND GENERAL ELECTRIC COMPANY ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) License NPF-1 PACIFIC POWER & LIGHT COMPANY )

(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE I hereby certify that copies of the Trojan Nuclear Plant response to the Nuclear Regulatory Commission's Request for Additional Information Regarding License Change Application 244 to the Operating License for the Trojan Nuclear Plant, dated July 1,1999, have been served on the following by hand delivery or by deposit in the United States Mail, first class, this 1st day of July 1999:

State of Oregon Attn: David Stewart-Smith Oregon Office of Energy 625 Marion Street NE Salem, Oregon 97301-3742 Chairman of County Commissioners Columbia County Courthouse St. Helens, Oregon 97051 L }, . Dusek Manager, Nuclear Regulatory Affairs On this day personally appeared before me Lansing G. Dusek, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act.

GIVEN under my hand and seal this ist day of July 1999.

OFFCALSFA PAT SCHAFFRAN Notary u ic i yd for the St e of Ore on 9""COMM6Sl0NNO.323839 NOTARYPUBUC-OREGON 7

Residing at .//I

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My commis'sfon expires 7-dp-fcamJ j