ML20079N416

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Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Including,Ecological Studies,Water Chemical Analysis,Reproductive study,1987 Progress Rept & 316(a) & (B) Demonstration Study
ML20079N416
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 11/11/1991
From:
NORTHERN STATES POWER CO.
To:
References
RTR-NUREG-1437 AR, S, WM, NUDOCS 9111110222
Download: ML20079N416 (14)


Text

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,, i RESPONSE TO QUESTIONNAIRE TO SUPPORT PART 51 RULE CilANGE PRAIRIE ISLAND NUCLEAR GENERATING PLANT <

l Note: Prairic Island Nuclear Generating Plant is a two unit pressurized water rector located on the Mississippi river. Unless indicated otherwise, the two units were considered as one because the data has not been recorded separately.

WASTE MANAGD4ENT QUESTIONS A. Spent fuel questions:

1. Which of the following current techniques for at reactor storage are you using and how?

A. Re racking of spent fuel B. Control rod repositioning C. Above ground dry storage D. Longer fuel burnup E. Other (picase identify).

ANSWER: A. Prairie Island is teracked to the maximwn extent possibic, liigh density bora flex racks were installed in 1981. The plant expects current storage space to be adequate until 1994.

IL A demonstration fuel rod consolidation project was conducted about 2 years ago and 36 assemblies were put into 18.

D. Prairie Island is using longer fuel burnup to extend fuel cycle length from 12 months to 16 18 months.

2. Do you plan on continuing the use of these current techniques for at-reactor storage of spent fuel during the remaining time of your operating license or do you expect to change or modify them in some way?

ANSWER: The current methods will suffice only until 1994 so above ground dry storage is being pursued.

3. Which of the following techniques for at-reactor storage do you anticipate using until off site spent fuel storage becomes available and how?

A. Re racking of spent fuel B. Control rod repositioning C. Above ground dry storage D. Longer fuel burnup E. Other (please identify)

ANSWER: A. and D. The spent fuel pool is already reracked to the maximum extent possible and the fuel cycle will continue to be managed.

C. Prairio Island plans to have dry cask storage available in 1993.

k Questionnaire Response Prairie Island Nuclear Cencrating Plant Page 2

4. Will the techniques described above be adequate for continued at-reactor storage of spent fuel for the operating lifetime of the plant, including a 20 year period of license renewal, or are you developing other plans?

ANSWER: The above ground dry storage will be expandable to be adequate for the current licensing duration as well as for extended plant life.

$. Do you anticipate the need to acquire additional land for the storage of spent fuel for the operating lifetime of the plant, including a 20 year period of license renewal? If so, how much land? When would this acquisition occur? Where?

ANSVER: There is no need to acquire additional land.

6. Do you anticipate any additional construction activity on site, or immediately adjacent to the power plant, site, associated with the continued at reactor storage of spent fuel for the operating lifetime of the plant, including a 20 year period of license renewal?

ANSWER: Yes, it is anticipeted that there will be construction of the dry storage casks.

7. If you answered yes to question 6, briefly describe this construction activity.

ANSWER: Corstruction activity will be done 1991 1992 for Independent Spent Fual Storage Installation (ISFSI) for Dry Cash Storage. There will be two 32 ft. x 200 ft, concrete slabs constructed and they will be surrounded by a security barrier.

B, Low level radioactive vaste management questions:

1. Under the current scheme for LLRW disposal (i.e. LLRW Policy Amendments Act of 1985 and regional compacts) is tt te currently or will sufficient capacity for wastes generated during the license renewal period be available to your plant (s)? If so, what is the basis for this conclusion?

ANSWER: Prairie Island presently expects the three operating LLRW disposal facilities to remain available for disposal through 1992.

Beginning in 1993, it expects to store its LLRU on site for approximately three years. Michigan, the first host state for the Midwest Compact, plans to begin operation of its disposal facility in 1996. Michigan will operate its facility for 20 years, after which another midwest state will be chosen to host another facility.

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4 Questionnaire Response Prairie Island Nuclear Generating Plant '

Page 3

2. If for any reason your plant (s) is/are denied access to a licensed disposal site for a short period of time, what plans do you have for continued LLRW disposal?

ANSWER: The plant is able to store up to five (5) years of waste on site.

There are plans being considered to make modifications to this storage area to allow for storage of additional forms of LLRW.

3. In a couple of pages, please describe the specific methods of LLRW management currently utilized by your plant. What percentage of your current LLRW (by volume) is managed i f:

A. Vaste compaction?

B. Vaste segregation?

C. Decontamination of wastes?

D. Sorting of waste prior to shipment?

i E. Other p ANSWER: A. 80% is managed by waste compaction C. 5% is managed by decontamination of wastes i.e. stainless steel pipe i E. 15% is handled by dewatering spent resin l-i 4. In a couple of pages, please describe the anticipated plans for LLRW

! management to be utilized by your plant (s) during the remainder of the

( operating license and through the license renewal term. What percentage

!- of your anticipated waste (by volume) will be managed by:

A. Vaste compaction?

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L B. Waste segregation?

l C. Decontamination of wastes?

! D. Sorting of waste prior to shipment?

! E. Other ANSWER: Essentially there will be no change except that off site incineration may be used which will reduce the total volume of LLRW and tho' compaction volume. This reduction will cause the percentage of resin of the total volume to increase even though l the resin volume will be constant. With Below Regulatory concerns l (BRC) approval some additional reduction could be made in dry ,'

active vaste levels.

5. Do you anticipate the need to acquire additiot.a1 land for the storage of LLRW for the operating lifetime of the plant, including a 20 year period of license renewal? If so, how much land? When would this acquisition occur? Where?

ANSWER: No acquisition of additional land is anticipated for LLRW storage.

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4-Questionnaire Responso Prairie Island Nuclear Generating Plant Page 4

6. To provide information on the timing of future low level waste streams,

.if you answered yes to question #9, over what periods of time are these activities contemplated?

ANSWER: Not appilcable

7. Do you anticipate any additional construction activity, on site, or immediately adjacent to the power plant site, associated with temporary LLRW storage for the operating lifetime of the plant, including a 20 year period of license renewal?

ANSWER: No, modifications will be made within interiors of existing buildings.

8.- If you answered yes to question 7, briefly describe this construction activity.

ANSWER: Not applicable

9. To provide information on future low level waste streams which may <

effect workforce levels, exposure, and waste compact planning, do you anticipate any major plant modifications or refurbishment that are

- likely_to generate unusual volumes of low-level radioactive vaste prior to, or during, the relicensing period for the plant? If so, please describe these activities. Also, what types of modifications do you anticipate to be necessary to achieve license renewal operation through a 20 year license renewal term?

ANSWER: Steam generator replacement will be the major modification considered for extended life of the plants, n

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4 Questionnaire Response Prairie Island Nuclear Genera +1ng Plant Page 5 AQUATIC RESOURCE QUESTIONS

1. Post licensing modifications and/or changes in operations of intake and/or discharge systems may have altered the effects of the power plant on aquatic resources, or may have been made specifically to mitigate inpacts that were not anticipated in the design of the plant. Describe iny svch modifications and/or operational changes to the condenser cooling water intake and discharge systems since the issuance of the operating license, ANSWER: The original
  • temporary" discharge permit for Prairie Island was '

issued by the Minnesota Pollution Control Agency (1972 1973). '

rindings from the EPA 316 ' Power intake and Discharge Study" (duration 36 months, 1974 1976) were:

1. No controlled aquatic barrier to the river
2. No means of returning fish / aquatic life back to the river
3. Present discharge allowed plant heated discharge to return to the intake crea which altered readings from river inlet
  • temperature detectora in response to these findings, modifications to the condenser cooling water intake and discharge systems were done at the Prairie Island Nuclear Generacing Plant. These modifications were completed in 1983. This modification included a new intake screenhouse with fine and coarse mesh screens, bypass gates, and a

- fiah return to the river to' satisfy items 1 and 2. Entrainment of fish and cold shock potential were reduced by these changes.

A redesigned discharge canal and sluice gates satisfied iter #3.

The discharge changes provide rapid mixing of discharged water with the river to eliminate concentrations of fish'and reduce potential for cold ...ock. Fish loss has:been reduced substantially since these modifications. ,

2. Summarize and describe (or provide documentation of) any known impacts on aquatic resources (e.g., fish kills, violations of discharge permit conditions) or National Pollutant Discharge-Elimination System (NPDES) enforcement actions that have occurred since issuance of the Operating 1.icense. How have these been resolved or changed over tinc?

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4 Questionnaire Response j 1- Prairie Island Nuclear Generating Plant Page 6 '

/35WER: The following is a list of the number of fish lost in fish kills.

the year it occurred and the cause.

Chlorination Related Kills l Date Number of Fish 1980 162,448 1981 28,095 1982 Unavailable 1983 37,124 1984 35,464 1985 7.578 i

Cold Shock Related Killa 4/18/88 1,345

$/06/88 570 Violations of NPDES permft limits occur periodica~11y and are often related to pH r' chloritatier requirements. The number of violations per year har. decreased markedly between the early 1980's and the past fav < ara. No NPDES enforcement actions have occurrod at the Pratrie island plant.

3. Changes to .he ::PLES nermit during operation of the_ plant could indicate

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whether water yunlity pa:Maeters were determined to have no significant impacts (snd were dropped from monitoring requirements) or were subsequently raised as a water quality issue. Provide a brief summary of changes lar.d when they occurred) to the NPDES permit for the plant sir.:e issuar.ce of the Operating License.

ANSPER: The following major changes were made to the-Prairie Island NPDEC pirait:

1) 1982 Added requirements for the liquid discharge of the radwaste system to.take weekly samplings for boron, to record the amount of daily discharge from the system,-and to -

release.the flow over as long a period as possible.

2) 1983 Changes in the condenser _ cooling water intake study to determine if the new intake screenhouse was reducing fish entrainment/ impingement mortality.
3) 1985 Added requirement tol conduct a creel census from.

December through May. ,

4) 1985 Eliminated setning due to poor seining areas and results.

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Questionnaire Response Prairie Island Nuc1 car Generating Plant Page 7

5) 1985 Shortened the fish holding time to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> f rom 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> in the latent fish impingement survival study.
6) Oj i.' niscontinued the water chemical analysis study. Alter t) 'smea of study, the only parameter showing an impact was t ir J<iated river water temperature downstream of the

%m't 4 iling water discharge. River water temperature 1.c 6 /rwt. was continued as required by the NPDES permit.

7) afi7-fi*wont'i ued the Walleye /Sauger reproduction study which evaluated the spawning success related to chill periods through gonad maturation analysis. It was felt that the reproduction of the walleye and sauger had t.ot becu -

impaired.

8) 1988 Discontinued the trapnetting portion of the Adult Fish Population Study. It was agreed that the data accumulated over the years supported the ominston of trapnetting and that electrofishing collection would continue to provide a represent.tive population.
9) 1989-Discontinued the latent survivorship portion of the fine mesh traveling screen impingement survival study. The prior years' studies hed adequate evaluation of latent survivorship. Also discontinued were the abundance sampling portion of the same monitoring study. Data acquired for the period 1984-1988 had adequately provided estimates of fish abunoance/ density over a variety of envirotunental and plant operating conditions.

4 An examination of trends in the effects on aquatic resources monitcring can indicate whether impacts have increased, decreased, or remained relatively stable during operation. Describe and summarize (or provide documentation of) results of rnonitoring of water quality and aquatic biota (e.g. related to NPDES permits, Environmental Technical Specifications, site specific monitoring required by federal or state agencies). What trends are apparent over time?

ANSWER: Environmental monitoring programs have deter:.  !

that no long term detrimental trends to aquatic resources have occurred.

Thermal input is the only demonstrated effect on the river system, and it has remained within permit limits. Water quality monitoring undet the environmental program has been eliminated hosever, the plant continues to do routine NPDES water quality monitoring.

Attachment 1 is a copy of the l989 Environmental Monitoring and Ecological Studies Program for the Prairie Island Nuclear Generating Plant.

j Questionnaire Response _ i Praitle Island Nuclear Generating Plant Page 8 Also enclosed are documents from previous years of the Prairie Island Annual Environmental Monitoring Reports which summarize the  ;

vatious monitoring programs conducted at the plant over the years. '

Attachment 2 contains copies of the last Water Chemical Analyses (1986) and the Lake Pepin Ice Thickness and Water Temperature <

Survey (1985) done. The final Walleye /Sauger Reproduction Study *

(1985) is Attachtnent 4 and the final Creel Survey (1987) is Attachment 5 to this survey. -

5,  : Summarize types and numbers (or provide documentation) of organisms entrained and iinpinged by the condenser cooling water systen. since issuance of the Operating License. Describe any secsonal patterns associated with entrainment and itspingement. How has entrainment and 1 frapingement changed over tiene7 ANSWER: Impingement on the original traveling screens was inonitored from 1973 to 19P4 The 316(b) studies also included entrainment assessment in 1975. Impingement studies related to the new screen system have been conduc';.d stuce modificatior, of the intake at Prairie Island in 1983 (see response to question 1). Both impingement-and entraitunent losses have been greatly reduced by the new intake system. Attachment 3 gives the pertinent data-to support this finding. It is made up of the following documents:

1) The 1974 1975 316(b) impingement and entrainment data +
2) -The 1984 Annual Report Ecological Studies " Impinge: tent of Fishes and other Organisms on the Prairie Island Plant Cooling Water Intake Traveling Screens"
3) The_1988 Annual Report " Fine Mesh Vertical Traveling Screens Impingement Survival Study"
6. Aquatic habitat enhancement _or restoration efforts (e.g. ,- anadromous fish runs) during operation may have enhanced the biological communities in the vicinity of the' plant. -Altetnatively, degradation of habitat or water quality may have resulted in loss of biological resources near t.he site.. Describe any-changes to aquatic habitats (both enhancement and degradaticn) in the vicinity of the power plant since the issuance of the Operatin6 License including those that may have resulted in different' plant impacts than those initially predicted.

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/,NSWER: No specific aquatic habitat enhancement or restoration efforts have been instigated.- Improvement following the 1983-intake / discharge modifications discussed in question 1 of the l Aquatic Resoutce section, iroproved conditions for fish survival over premodification conditions. No measurable degradation of habitat has occurred. ]

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s Questionnaire Response  !

Prairic Island Nuclear Generating plant Page 9 *

7. Plant operations may have had positive, negative, or no impact on the '

use of aquatic resources by others. Describe (or provide documentation for) other nearby uses of waters affected by cooling water systems '

(e.g., swimming, boating, annual harvest by commercial and recreational fisheries) and how these impacts have changed since issuance of the  ;

Operating License.

ANSWER: A concern was raised that extended open water periods during the winter due to Prairie Island's thermal discharge-could affect gonad maturation in prespawning walleye and sauger populations and also allow over harvesting by recreational fishermen during the winter months. A walleye /sauger reproduction study was completed in 1985 (see Attachment 4) and showed no significant decline in gonad development. A summary of the data and conclusions of the creel survey are provided in the 1987 Creel Census Report (Attachment 5) which showed no increase in open water fishing during the winter months.

8. Describe other sources of impacts on aquatic resources (e.g., industrial discharges, other power plants, agricultural runoff) that could contribute to cumulative impacts. What are the relative contributions ,

by percent of these sources, including the contributions due to the power plant, to overall water quality degradation and losses of aquatic biota?

1 ANSWER; The Prairie Island Nuclear Generating Plant is approximately 40 miles downstream of the Minneapolis /St. Paul metropolitan area and approximately-20 miles downstream of llastings, KN on the Mississippi River. Two major tributaries enter the Mississippi River within that distance, the Minnesota and the St. Croix Rivers. The Cannon River and the Vermillion River enter the Mississippi within approximately 3 miles downstream of the. plant discharSe. Agricultural runoff via the tributaries as well as. the Mississippi itself is substantial. In addition, the metropolitan waste treatment overflow and storm sewer discharge enter the river as well as potential drainage from innumerable riverbank located industries in the metropolitan area. Northern States Power does not have the means to quantify the cumulative impacts for this reach of the Mississippi River.

9. provide a copy of your Section 316(a) and (b) Demonstration Report required by the Clean Waste Act. What Section 316(a) and (b) determinations have been made by the regulatory authorities?

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e Questionnaire Response Prairie Island Nuclear Generating Plant Page 10 ANSVER: The results of the 316(a) and 316(b) studies were partially responsible for the intake and discharge modifications discussed in quest. n 1 of the Aouatic Resource section, and subsequent additional seguired monitoring programs and studies. Copics of-the Table of Contents and the Summaries of the 316(a) and 316(b) demonstrations are included as Attachment 6. The reports are too extensive to facilitate providing complete copies. If selected sections of the reports are needed, they can be supplied.

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. t Questionnaire Response- f Prairie Island Nuclear Generating Plant [

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SOCIDECONOMIC Q1*r'STIONS 1, To understand the importance of the plant and the degree of its socioeconomic impacts on the local region, estimate the number of '

permanent workers on site for the most recent year for which data are ,

avai) *,bl e .  ;

E ANSWER: Permanent staff on site 1989 426 workers 1 Staff at- nearby (but off site) training center 41 workers

2. To - derstand the importar'ce of the plant to the local region, and how that has changed over time, estimate the average number of permanent -!

workers on_ site, in five year increments starting with the issuance of .

-the plant's Operating-License. If possibic, provide this information for each unis at a plant site, l l

ANSWER: The numbers given include security staff which are contracted employees but are always required to be onsite by the plant, i 1.isted as a separate category are the employees of the training ,

center. The center is not directly onsite but within the area of-the plant and affects the local region. ,

1973 200 employees onsite 1978 280 employees onsite 1983 425 employees onsite 20-employees training center 1988 490 employees onsite 30 employees training center

3. To understand the potential impact of continued operation for an additional 20 years beyond the original licensing term, please provide for the following three cases:

A)~ a typical planned outage; B)' an ISI outage; and

'C) the largest single' outage (in terms of the number of workers  ;

involved) that has occurred to date _

an estiniate of additional workers involved (for the entire outago and'-

for each principal-task). length of outage, months and year in which  ;

work occurred,-and cost. Also,. estimate occupational doses received by '

permanent and-temporary workers during each principal task- ,

v Questionnaire Response Prairie Island Nuclear Generating Plant Page 12 ANSWER: Prairie Island does not have separate Inservice Inspection outages. A portion of the inspections are done each refueling outage.

A) A typical planned outage Adriittonal workers angroxientely 500 to 600 workeys (not able to break down per task)

Length of outage 12.Anya_,

Cost The estimated cost given does not include: (a) replacement energy s cost, (b) normal base load operating cost (such as permanent employees salaries, (c) corrective maintenance, (d) non reoccurring items, (e) capital costs and (e) costs associated with fuel cycle design and analysis. It does include (a) plant labor and support group costa. (b) service contracts and consultant costs (c) materials, and (d) radioactive _ waste disposal costs. In 1985, an estimate was made thur_a typical outage cost approximately $6,000,000. In 1989, the price of a Prairie Island outage had increased to approximately $10,000,000.

Principal task costs are not available.

Doses The occupational dosage received by permanent and temporary employees during an average outage at the Prairie Island Nuclent Generating Plant is 75 to 100 man rom per unit. The specific dosos received for major projects done at the plant are not available.

c) The largest single outage The outages for each unit were longer because of the 10 year inspections that were done in addition to the refueling. -

Additional workers anoroximatelv 500 to 600 workers ver unit (not able to break down per task)

Length of outage 55 days each unit tionths and years of outage Unit 1 Janunrv/ February 1985 Unit 2 Sentember/ October 1985 Cost The estimated cost given doca not include: (a) replacement energy cost, (b) normal base load opera'.lfe fast (such as permanent employees salaries, _ (c) corrective maintenan:w, Jd) non reoccurring items, (e)

-capital costs and (e) costs associacad 'ith fuel cycle design and analysis. It does include (a) plant 40 or and support group costs, (b) service contracts and consultant costs, (c) materials, and (d) radioactive waste disposal costs. The cost of-the 1985 refuel outage for each unit was approximately $10,000,000. Principal task costs are not available.

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Questionnaire Response

  • Prairie Island Nuclear Generating Plant Page 13 Doses Occupational doses received by permanent and temporary employees is not available for each major task during the 1985 outage. The total dose received by workers during the outage was approximately 160 165 man reas per unit. .The dosage received for refueling was approximately 1$ man rem and for the Inservice Inspections was 68 man rem per unit.
4. To understand the plant's fiscal importance to specific jurisdictions, for 1980, 1985, and the latest year for which data are available, estimate the entire plant's taxable assessed value and the amount of s taxes paid to the state and to each local taxing jurisdiction.

Distribution of Tax 1980 1985 1990

-Market Value $ 319,889,988- $346,514,400 .$378,196,100 City 2,077,096 3,701,055 5,892,006 County 1,480,756 2,089,695 4,109,230 School District 256 3,899,739 4,486,202 6,991,410 Total 7,457,591 10,276,952 16.992,646 I

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