ML20196L057

Provides Suppl Info to USEC Previous Response to NRC 990407 RAI Re USEC Application for Amend to Coc GDP-1 to Extend Completion Date for Bldg C-331 & C-335 Seismic Upgrades to June 27, 2000

ML20196L057
Person / Time
Site:	Paducah Gaseous Diffusion Plant
Issue date:	05/14/1999
From:	Toelle S UNITED STATES ENRICHMENT CORP. (USEC)
To:	Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
GDP-99-0082, GDP-99-82, TAC-L32107, NUDOCS 9905210111
Download: ML20196L057 (16)

Text

{{#Wiki_filter:- gp d USEC .f. A Global Energy Company i May 14,1999 GDP 99-0082 i i ~ Dr. Carl J. Paperiello Director, Office of Nuclear Material Safety and Safeguards l Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 i l Paducah Gaseous Diffusion P! ant (PGDP) ' Docket No. 70-7001 Supplemeritary Response to Request for AdditionalInformation on Building C-331 and C-335 Seismic Upgrades (TAC No. L32107)

Dear Dr. Paperiello:

The purpose of this letter is to provide supplementary information in addition to USEC's previous response ( Reference 1) to the NRC's April 7,1999 letter requesting additional information concerning USEC's application to amend Certificate of Compliance GDP-1. This amendment would extend the completion date for the Building C-331 and C-335 seismic upgrades to June 30,2000. i . The supplementary information is provided in the enclosure. } If you have any questions or comments on this additional information, please contact me at (301) 564-3250. There are no new commitments contained in this submittal. Sincerely, 9

5. A. D Steven A.Toelle Nuclear Regulatory Assurance and Policy Manager

Enclosure:

United States Enrichment Corporation, Paducah Gaseous Diffusion Plant, Docket No. 70-7001, Supplementary Response to April 7,1999 NRC Request for Additional Information Concerning C-331 and C-335 Seismic Upgrades (TAC No. L32107) /

References:

1. Letter from Steven A. Toelle (USEC) to Dr. Carl J. Paperiello (NRC) "Paducah l Gaseous Diffusion Plant, Docket No. 70-7001, Response to Request for Additional Information on Building C-331 and C-335 Seismic Upgrades (TAC No. L32107)" I c y n,,, n, Df 9905210111 990514 PDR ADOCK 07007001 C PDR 6903 Rockle~dge Drive. Bethesda. MD 20817 1818 l l Telephone 301564-3200 Fax 301564 3201 http://www.usec.com g i8 W Offices in Livermore. CA Paducah, KY Portsmouth, OH Washington, DC j c

q i . ;( h. Dr. Carl J. Paperiello

May 14,1999 GDP 99-0082, Page 2 s<

hp cc: Mr. Robert C. Pierson(NRC f NRC RegionIII Office j' NRC Residentinspector-PGDP i NRC Residentinspector-PORTS Mr. Randall M.DeVault (DOE) i i ) l l: i. f h. i-ii \\ n J

Enclosure r :. GDP 99-0082 Page1of14 l United States Enrichment Corporation Paducah Gaseous Diffusion Plant Docket No. 70-7001 Supplementary Response to April 7,1999 NRC Request for AdditionalInformation Concerning Building C-331 and C-335 Seismic Upgrades (TAC No. L32107) l l

o ) 1 Enclosure GDP 99-0082 4 L Page 2 of14 Q1 (NRC 4/7/99 Letter) Pmvide the worst case uranium /HF consequences for the four evaluation cases outlined in Table 1 of the Compliance Plan Issue 36: (1) building collapse-no retention in cascade, (2) building collapse-l conservative estimate of retention in cascade, (3) partial building failure with no aerosol deposition, and (4) partial building failure with aerosol deposition. The worst case would involve the directional sector with the highest onsite population, the wind associated with that direction, and the worst case meteorological conditions. The above information should be provided as a minimum. Additional consequence or risk information, as deemed appropriate, may be provided to further address uranium effects on onsite 4 personnel, i Supplementary Response to Question 1 Structural Behavior of C-331 and C-335 l Worst case consequences, as defined in Question 1, for the four evaluation cases outlined in Table 1 of Compliance Plan Issue 36 were provided in USEC's April 27 response (original response). However, the first two cases specified in Question I and Compliance Plan Issue 36 are not l considered to be credible by USEC after June 30,1999, based on the following discussion. In this - discussion, work that is considered " complete" means that planned modifications have been installed in accordance with design requirements. Planned modifications in each building require replacement . of existing bracing with stifTer bracing, and installation of new bracing. New bracing accounts for approximately 30% of the work required to complete a section on the Cell Floor, and approximately 85% of the work required to complete a section on the Ground Floor of each building (Sections 1 through 8 9 3 l '" na"~ '-) 1 2 W3 j 4 ll o GROUND FLOOR: Review of the subject project f 2 schedule indicates that on the Ground Floor Sections 2 ) 9 I and 2 in each building will be essentially complete

3 by June 30, 1999. Section 3 in C-335 will be s 6 s 5 approximately 25% complete. Section 3 in C-331 will

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y i be approximately 50% complete. k y L: 9 4 4 CELL FLOOR: By June 30,1999, Sections 1 through I o o 6 in C-331 will be essentially complete, in C-335 l Sections 1 and 2 will be complete while Sections 3 Figure 1 through 6 will be approximately 50% complete.

r Enclosure GDP 99-0082 Page 3 of14 After June 30,1999, Sections 1 and 2 in both buildings will have attained structural stiffness equivalent to that required by design with respect to the evaluation basis earthquake (EBE). However, because adjacent sections will not be complete, Sections 1 and 2 will likely experience " slamming" by adjacent units should such an event occur. " Slamming" is likely because the "as-found" analysis for the sections predicts the unmodified sections will experience large deflections during the seismic event. The predicted deflections for a single unmodified section are of such magnitude that during out of phase motion the modified and the unmodified sections will contact. Building impact will likely result in minor local damage at impact sites. Based on the relative state of differential stiffness that will exist among the building sections after June 30,1999, slamming is expected to be most severe along the expansionjoint between Sections 7/8. Slamming which is less severe is expected along the expansion joints between Sections 1/8,2/7, and 7/6. No slamming is expected along the expansion joint between Sections 1/2. Along interfaces not mentioned above, some slamming is possible but at a level much less severe than that expected for Sections 7/6. With respect to the behavior of the buildings, were they subjected to the Evaluation Basis Earthquake after June 30,1999, general collapse (total collapse of the gross structural frame) would not be expected in any section. Support for this prediction is founded in analyses of the "as-found" condition of the subject structures which predicts only partial collapse of building sections. Partial collapse as used here means collapse, roof to ground, of building bays approximately 20' wide indicated by hatched areas in Figure 1. Section I will experience minor damage due to slamming along the 1/8 expansionjoint. Section 2 will experience similar damage along the expansionjoints between 2/3 and 2/7. Section 3 in C-331 will be much stiffer than the "as-found" condition, especially with respect to loading along the minor axis of the building section. With respect to loading along the major axis of Section 3, the structure will be only slightly stiffer, exhibiting essentially the same stiffness as that in its "as-found" state. Because the stiffness of Section 3 is nearly that required along its minor axis, slamming between Sections 2 and 3 is not expected, slanuning between Sections 3 and 4 should be similar to that between 1/8 and 2/7. Sections 4,5 and 6 will behave essentially as predicted by the SARUP as-found evaluation of the structures, i.e. local failures along the rocker supported expansionjoints (hatched vertical areas in Figure 1). Because Sections 5 and 6 are relatively stiffer at the cell floor location than at the ground floor a soft story situation will exist for a time after June 30,1999. These sections will likely experience a greater degree oflocal collapse (areas of collapse which may or may not extend from roof to ground vertically and, from I bay [20' x 20'] to 4 contiguous bays [40' x 40'] in plan ). Figures 2 through 5 show the locations of all planned bracing installations and the anticipated construction progress as of June 30,1999 for the Cell Floor and the Ground Floor for each building. Planned bracing installations are indicated by a heavy bar (new installation) or a heavy ellipse (replacement installation). Those locations which are scheduled for completion by June 30,1999 are circled. ( Consequence and Risk Analyses

Enclosure GDP 99-0082 Page 4 of14 The results provided in the original response were based on an assumed factor of 2 credit for sheltering (reduction of unsheltered consequence data). Additional analyses have been performed for the partial building failure cases to determine the consequence and risk results without the factor of 2 reduction for sheltering. These results are shown in Tables 1 through 3. Table I shows the number ofonsite personnel that receive a dose whhin a particular " bin" or " range." Bins that contain no workers are nct listed in the summary table. For onsite personnel, F3 conditions with a wind direction from 082* produce the highest consequences for the partial failure scenario. Table 2 shows comparable results for the some source term combinations, but assuming the most likely meteorological conditions (D4) and wind direction (from SSW) for PGDP. The calculated consequences are based on several highly conservative assumptions: PGDP was assumed to be operating at a 2200 MW power load. If any part of a target building fell within a 22.5' downwind sector of the release from either C-331 or C-335, then the entire target building population was assumed to be located at the centerline of the plume in the portion of the building closest to the release. Standard compass wind sectors were not assumed for the worst case condition; instead, a w' d direction from 082' was assumed that would maximize the number of onsite workers m afTected by the plume. Toxicological doses were calculated based on an active " light exercise" breathing rate. This produced 20% higher doses than workers engaged in " normal activities" would obtain. The release was assumed to occur on a weekday during daytime business hours when the onsite population is maximized. Results of the additional risk calculations are summarized in Table 3. Table 3 presents injury frequency data for four renal injury categories based on the same combinations of conditions as the consequence calculations presented in Tables 1 and 2. The calculated annual risk in each of four renal injury categories considers the probability of the event (conservatively assumed to be a 70 year return period) and the pmbability of the wind direction from C-331 or C-335 to the target bdiding, l given the source term, and meteorological conditions. Ilowever, no credit was taken for the fact that i at least 70% of the time the plant population is well below (less than half of) the assumed peak population. Even with these conservatisms, Table 3 shows that the risk ofinjury due to uranium toxicity is low and that the maximum severity ofinjuly associated with the risks is moderate renal injury. The risk calculations incorporated probability data of wind blowing from a source building (C<331 or C-335) to a target building. The calculations did not, however, consider the probability of the specified meteorological conditions; therefore, no credit was taken for probabilities of the selected meteorological conditions. L

V. Enclosure GDP 99-0082 1 Page 5 of14 Table 1. Uranium and HF Consequences for Worst Case Wind Direction and Meteorological Conditions No Credit For Sheltering Partial Building Failure Uranium Intake No Aerosol Deposition Aerosol Deposition (mg U) F3 Meteorological Conditions F3 Meteorological Conditions No. Workers No. Workers No. Workers No. Workers HF Ex sure with Uranium with HF with Uranium with HF (ppm HF) Uptake Exposure Uptake Exposure [70,80) [60,70) 31 i {50,60) 5 [40,50) 5 1 [30,40) 74 5 l [20,30) 593 249 [10,20) 444 693 693 [0,10) Note: Each range [x,y) is denoted within a left bracket and a right parenthesis. The left bracket denotes an included value while the right parenthesis denotes an excluded value. For example, [15,20) defines a range that includes all values between 15 and 20--including the value 15 but excluding i the value 20. I l a 1 L )

w w. Enclosure GDP 99-0082 Page 6 of14 Table 2. Uraniumi and HF Qonsequences for Most Likely Wind Direction and Meteorological Conditions No Credit For Sheltering Partial Building Failure Uranium Intake No Aerosol Deposition Aerosol Deposition (mg U) D4 Meteorological Conditions D4 Meteorological Conditions No. Workers No. Workers No. Workers No. Workers HF Ex sure. with Uranium with HF with Uranium. with HF (ppm HF) Uptake Exposure Uptake Exposure [60,70) [50,60) [40,50) [30,40) l [20,30) l_ [10,20) - 50 j l [0,10) 50 50 50 l Note: Each range [x,y) is denoted within a left brncket and a right parenthesis. The left bracket denotes an included value while the right parenthesis denotes an excluded value. For example, [15,20) ' defines a range that includes all values between 15 and 20-including the value 15 but excluding the value 20. )

ii Enclosure - GDP 99-0082 ' Page 7 of14 Table 3. Results of Risk Analysis No Credit For Sheltering Partial Building Failure No Aerosol Deposition Aerosol Deposition Renal Uranium injury-Intake Meteorological Conditions Category (mg U) Worst Most Worst ' Most Case ,Likely Case Likely F3 D4 F3 D4 Low 50 to 0.0548 0.0703 0.0192 0.019-Renal <100 Injury Moderate 100 to 0 0.0192 0 0 Renal <l50 Injury l High 150 to 0 0 0 0 Renal <200 Injury Potential 200 or 0 0 0 0 Lethal greater Renal Injury Note: In performing the consequence analysis, the " worst case" meteorological conditions that affected the largest number of onsite personnel were F3. However, the most likely meteorological - conditions, D4, pose a slightly higher risk. 1 9 L

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g L 4 L Enclosure GDP 99-0082 Page 12 of14 Q2 (NRC 4m99 Letter) For, the' estimated consequences' to onsite personnel, either provide justification for your ' determinations where no additional interim compensatory measures are necessary or propose ' additional interim compensatory measures.- Supplementary Response 'to Question 2: Based on the supplementary response to Question 1, the complete building collapse scenarios postulated in the Compliance Plan Issue 36 JCO are not considered to be credible for the Evaluation Basis Earthquake after June 30,1999. For the partial building collapse scenarios evaluated in the supplementary response to Question 1, a number ofconservatisms were included in the consequence, and risk calculations. These conservative assumptions are listed below: The source term assumes the failure of every B bypass and process line adjacent to the rocker-supported building section lines, all of which are assumed to collapse, for every section in both buildings. 'Ihe entire inventory in these B lines and the adjacent stages on either side, along with the unit bypass lines, building tie lines and surge drums, is assumed to be released within 5 minutes. The best estimate picture of the releases is that initial releases are going to be small (in the range of hundreds of pounds vs thousands of pounds) with small releases occurring over hours as the air and UF, mix and the moisture is reacted. If any part of a target building fell within a 22.5* downwind sector of the release from either C-331 or C-335, then the entire target building population was assumed to be located at the centerline of the plume in the portion of the building closest to the release. Standard compass wind sectors were not assumed for the worst case condition; instead, a wind direction f om 082 was assumed that would maximize the number of onsite workers affected by the plume. Toxicological doses were calculated based on an active " light exercise" breathing rate. This produced 20% higher doses than workers engaged in " normal activities" would obtain. . No credit was taken for workers taking evasive action ("See-and-Flee") to escape the oncoming release plume. No credit was taken for any reduction of exposure for workers remaining in intact or damaged buildings. The release was assumed to occur on a weekday during daytime business hours (only 30% of the total time in a week) when the onsite population is maximized. Interim compensatory actions currently being implemented include restricting operations in C-331 .and C-335 to subatmospheric pressure and limiting access to these buildings to only essential personnel. No further actions have been identified to protect the general public or the personnel in these facilities. Existing emergency response plans and procedures provide adequate protection for the other workers on the plant site. 3 i { k i

Enclosure GDP 99-0082 Page 13 of14 The PGDP emergency response program provides Local Emergency Directors (LEDs) for each ~ nonnally occupied building on site. Two individuals (a primary and an altemate) from each building are designated. These individuals are trained in the incident cvownsnd process, which includes taking _ charge of a situation, assessing required protective actions, and communicating' these actions to the - q people in their building and to the site Incident Commander. The LED in each building has a radio - for communication with the Central Control Facility (CCF), if needed. The local building emergency plans for each facility address, among other situations, earthquakes and chemical threats from outside the facility. If the LED determines that the facility must be evacuated following an earthquake,. personnel would be directed to evacuate'away from the plume. The specific evacuation direction. would be dependent upon the location of the source of the release relative to the facility and the existing wind direction. This information would be communicated to the LED from the Incident - Commander by telephone, public address system, radio and/or messenger. Ifno specific instructions . are available, the LED would direct evacuation at a 90 degree angle to the plume path (existing wind direction). . In the event of a major earthquake, the CCF would direct the immediate shutdown of the cascade. The Incident Commander would attempt to establish communication with the various site facilities to-assess;the extent of. damage _ and to recommend protective actions. In ' addition.to the communication methods listed above, the emergency response squad have access to vehicles with mobile PA systems which can also be used to notify personnel. In the event of a chemical release initiated by an earthquake, the hazardous material release procedure would also be followed.- All onsite personnel are trained to evacuate areas upon detection of a release by sight or by odor ("See-and-Flee"). The See-and-Flee response to an umontrolled hazardous material release is a well-established plant policy and is thoroughly understood by all plant personnel. In addition, the irritating effects of HF are noticeable at concentrations well below that'which are immediately dangerous to life or health. As a result, personnel would be induced to leave the plume area regardless of speci_ fic instructions to do so. Predicted exposures without taking any actions are already low. Moving away from the plume will further reduce exposures, even if personnel are temporarily in the plume. - Based on the discussion above, no additional interim compensatory actions are practical or necessary - to protect on-site workers not located in C-331 and C-335.

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Enclosure GDP 99-0082 Page 14 of14 Q3 (NRC 4/7/99 Letter) Discuss the use of the term " injuries" associated with onsite workers in the buildings in your to the j January 27,1999 RAI Question 1. To the extent possible, discuss the effects of uranium intakes for onsite workers in the buildings. Supplementary Response to Question 3: USEC has no supplementary response to provide for this question. i i 1-}}