ML20116G779

Responds to NRC Request for Addl Info Re Average Annual Vols & Radioactivity of Wastes Shipped During Period of 1974-91 & Significance of Exeeding Estimated Values for Shipments Over Proposed Extension Time

ML20116G779
Person / Time
Site:	Oyster Creek
Issue date:	11/05/1992
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-92-2223, NUDOCS 9211120124
Download: ML20116G779 (4)

Text

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g G,d Nuclear GPU Nuclear Corporation

er::r388 Forked River, New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Number:

November 5, 1992 C321-92-2223 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Was:.ngton, D.C.

20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Operating License No. OPR-16 Docket No. 50-219 Response to Request for Additional Information (RAl)

=

License Amendment Request No. 199 in response to the NRC staff's request for additional information, dated April 29, 1992, Enclosure 1 of this letter addresses Item 3 of the referenced RAl.

i

erely,

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B r on V' l e]' resident and Director 0 sVr Creek Nuclear Generating tation DJD/JJB/amk Enclosure cc:

Administrator, Region I NRC Resident Inspector Mr. Alex Dromerick, Jr., Project Manager 120031 9211120124 921105 PDR ADOCK 050002 i g] )

P PD GPU Nuclear Corporat:on is a subsidiary of General Pubhc Ut,1, ties Corporation

C321-92-2223 Page 1 of 3 M CLOJt)RE I Qt)LSTION ll3 in response to item 6 of 10 CFR 51.52, GPU Nuclear Corporation (GPUN',

indicated that DCNGS shipped approximately 12,200 cubic feet of solid waste compared to the value of 11,250 cubic feet estimated in Section 5.7.4 of the Final Environmental Statement (FES) dated 1974. Section 5.7.4 also estimated that about 2700 Ci of radioactivity would be shipped offsite each year.

A review of the 1990 and 1991 Semi-Annual Radiological Environmental Reports indicate that 5785.4 Ci of radioactivity was shipped offsite in 1990 and that 17,413 cubic feet of waste was shipped offsite in 1991.

Provide the average annual volumes and radioactivity of wastes shipped during the period of 1974 through 1991 and discuss the significance of exceeding the estimated values 4

discussed in Section 5.7.4 of the FES.

Additionally, GPUN needs to discuss fho ef feCt of the increase of these shipments over the proposed operating ion time.

E age annual volumes and radioactivity of waste shipped during the 974 through 1991 is tabulated below. The 1992 through 2009 values are

.ad estimates.

YEAR CURIES VOLUME (f t')

1974 1570 4E,756 1975 2810 34,982 1976 1280 42,403 1977 137,273*

61,840 y

1978 1149 54.558 1979 1339 39,965 1980 1322 71,767 1981 421 62,827 1982 4666 35,519 1983 561 35,371 4

1984 43,950*

49,345 1985 630 16,315 1986 795 20,906 1987 36,658*

8334 1988 6298*

7096 l

C321-92-2223 Page 2 of 3 YEAR CURIES VOLUME (f t')

l 1989 232,793*

14,837 1990 1130*

11,386 1991 1390 17,406 1992 62,000*

13,000 1993 1510 13,000 1994 938 12,000 4

1995 1510 13,000 1996 938 12,000 1997 1510 13,000 1998 938 12,000 1999 1510 13,000 2000 938 12.000 2001 1510 13,000 2002 938 12,000 2003 1510 13,000 2004 938 12,000 2005 1510 13,000 2006 938 12,000 2007 1510 13,000 2008 938 12,000 2009 1510 13,000

• Denotes irradiated hardware shipments NOTE:

1993 - 2009 assumes the following:

1510 ci and 13,000 (Ft.') for outage year.

938 ci and 12,000 (FT.') for operating year.

No Irradiated Hardware shipments after 1992.

Current on site and off site waste processing capabilities l

remain the same.

Current radwaste volume reduction capabilities, e.g.,:

incineration, decontamiriation/ recycling and super i

compaction remain the same.

A review of the 1990-1 and 1990-2 Semi-Annual Effluent Reports indicate that an error was made in reporting the total curies shipped during the second half of 1990.

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(*321-92-2223 Page 3 of 3 1

I It appears that in the second half of 1990 the total cubic foot column value for l

all four (4) categories, 4931.2 (Ft.'), and the total curies shipped off site to -

i SEG for Dry Active Waste, 278.25 Ci _was used as the total and reported in the i

executive summary for the second half of 1990 as 5785.4 Ci.

The-total curies

?

shipped off site in 1990 was actually 1130.23 Ci, as correctly documented in Tables 5 and 6 of these reports.

It can he seen that with the exception of years which include irradiated hardware shipments, the projected average curie level of radwaste shipped from 1974 i

through 2009 (1345 C1) would be well below that assumed in the 1974 FES, even with higher volumes of solid radwastes shipped.

As stated in the Semi-Ar.nual Ef fluent Release Report, these shipments are similar to those of nuclear plants of comparable type, age and size. It is expected that the curie content of solid i

radwaste generated over the proposed operating time extension will remain below that previously evaluated.

Filter Sludge and Concentrated Liquid Wastes are processed into Steel or High Integrity Containers (HIC's) and mixed with cement.

Bead Resins are processed into High Integrity Containers (HIC's) and dewatered, WASH-1238, " Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power i

Plants", December,1972, which provided the data supporting Table 5.3 in the 1974 FES for OCNGS, assumed solidification and transport of waste in steel drums only.

3 Filter Sludge, Concentrated Liquid Waste and Bead Resins at OCNGS are shipped directly to a licensed disposal facility in a licensed NRC Type A or B cask. Dry Active Waste (DAW) is processed into strong tight containers (STC) and shipped i

off site to licensed waste reprocessors or directly to a licensed disposal j

facility. The average expected volume of Radioactive Waste and curies generated from 1991 to 2009 is 12,810 f t.'

and ?.,289 curies, WASH-1238,Section VI, l

Table 8 assumed a value of 13.22 Ci/f t' for solid radwaste.

As shown above, OCNGS solid waste radioactivity levels are projected to be well below this value.

The projected radwaste volume does not represent a significant increase in the l

value assumed in the 1974 FES, and the projected curies generated over the remaining period of plant operations iracluding the proposed period of extension is well within the value assumed in'the 1974 FES. Shipping ;ontainers currently used at DCNGS are a significantly higher integrity design than that assumed in l

the FES evaluation. The NRC Enviror. mental Assessment in support of tFe Full Term Operating License, dated April 10, 1986, reexamined the environmental impacts l

initially presented in the 1974 FES. This evaluation determined that there were i

no new impacts that differ significantly from those evaluated in the FES. Based on the_above_, the Conclusion remains Valid for the extended period of operation.

I As requested in follow-up-discussions,-the collective annual exposures to OCNGS plant workers in terms of whole body dose were 310R for 1990 and 1184R for 1991'.

The 1991 whole body dose potentially received by an assumed maximum exposed individual _ from 0CNGS liquid and airborne effluent? was conservatively calculated -

to be about 7.08 E-3 mil 11 rem total-or only 2.83 E-2 percent of the OCNGS Technical Specification Limit-(OCNGS REMP Report for 1991).

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