ML20041D830
| ML20041D830 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/29/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-03.C, TASK-3-3.C, TASK-RR LAC-8059, NUDOCS 8203090300 | |
| Download: ML20041D830 (12) | |
Text
o DlDA/RYLAND h
[k COOPERAT/VE
- PO COX 817
- 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN 9601 (608) 788 4 000 Janua ry 29, 1982 In reply, please refer to LAC-8059 DOCKET NO. 50-409 U. S. Nuclear Regulatory Commission g
ATIN: Mr. Darrell G. Eisenhut, Director Division of Licensing
(
Of fice of Nuclear Reactor Regulation 5) 2 Agoa %0 fD Division of Operating Reactors 9
Washington, D. C.
20555 L
SUBJECT:
DAIRYLAND POWER COOPERATIVE (DPC) h ab.
LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45
/
SEP TOPIC III-3C -
INSERVICE g
INSPECTION OF WATER CONTROL STRUCTURES
REFERENCE:
(1) DPC Letter, LAC-7387, Linder to Eisenhut, Dated February 27, 1981 Gentlemen:
Our letter, Reference 1, identified topics for DPC to submit for NRC evaluation.
The subject topics were listed in the schedule submitted with Reference 1.
4 Enclosed find the Safety Evaluation Report (SER) for Topic III-3C, " Inservice Inspection of Water Control Structures."
If there are any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL : HAT:eme cc:
J. P. Keppler, Regional Director, NRC-DR0 III NRC Resident Inspector WP1 6
l 8203090300 820129 6I g
i L
DR ADOCK 05000
LA CROSSE BOILING WATER REACTOR SYSTEMATIC EVALUATION PROGRAM SAFETY EVALUATION REPORT TOPIC III-3C INSERVICE INSPECTION OF WATER CONTROL STRUCTURES 1.
INTRODUCTION The safety objective of this review is to assure that adeqJate and timely inspections of water-control structures, systems and components are accomplished to minimize the risk to public health and safety resulting from operation of nuclear power plants.
The review specifically pertains to water-control structures (e.g., dams, reservoirs, conveyance facilities) built for use in conjunction with a nuclear power plant and whose failure could cause radiological consequences adversely affecting the public health and safety.
In general, to be included under this topic, the structure must have been built, wholly or in part, for the purpose of controlling or conveying water for either emergency cooling operations or flood protection of a nuclear power plant.
Such structures 3
may be located on or off the site.
The scope of the review embraces the following subjects which are evaluated using data developed by the licensee and information available fran all sources:
(a) Engineering data compilation; (b) Onsite inspection program and reports of these inspections; (c) Technical evaluation of inspection results; and (d) Frequency of inspections.
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II. CURRENT REVIEW CRITERIA The' criteria which are applicable are (1) 10 CFR Part 50, Section 50.36, (2) 10 CFR Part 50, Appendix A including General Design Criteria 1, 2 and 44, (3) 10 CFR Part 100 and-(4) 10 CFR Part 100, Appendix A.
Pertinent regulatory positions contained in Regulatory Guides 1.27, 1.28, 1.127,1.132 and 1.138 (Ref.1) also apply. Review procedures as contained in NUREG 75/087 Standard Review Plan Sections 2.5.4 and 2.5.5 die also used where appropriate.
III. RELATED SAFETY TOPICS AND INTERFACES The slope stability aspect of water-control structures will be reviewed under Topic II-4.D.
Settlement of water-control structures will be reviewed under Topic II-4.F.
Other interface topics include:
II-4.E,
" Dam Integri ty" ; II-3. A, " Hydrologic Description" ; II-3.C, " Ultimate Heat.
Sink" ; III-3. A " Effects of High Water on Structures" ; IX-3, " Station Service and Cooling Water Systems"; III-6, " Seismic Design Considerations".
IV. REVIEW GUIDELINES In general, the method for complying with specific portions of the Commission's rules and regulatory positions as described in Regulatory Guide 1.127 is used in evaluating inservice inspection programs for water-control structures. Pertinent elements of the licensee's program are evaluated and compared to current criteria and the safety significance of i
i any dif ferences is evaluated. The practices of other public agencies for similar facilities posing similar public risk may also be used for applicable guidance.
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]
V.
TOPIC EVALUATION 1.
Site Description and Water Supply i
The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa 2, is located on the east bank of the Mississippi River at Genoa, Vernon County, Wisconsin. The plant was completed in 1967 and has a capacity of 50 MWe.
Its site is at mile 678.6, approximately 3300 feet below U. S. Lock & Dam No. 8, and about 17 miles south of the city of La Crosse, Wisconsin LACBWR shares a 163.5-acre site with two conventional steam plants, the 14-MWe Genoa 1 and the 350-MWe Genoa 3.
LACBWR's safety related cooling water supply and for the once-through cooling system for the turbine condenser is drawn from the Mississippi River.
LACBWR shares a connon discharge structure with Genoa 3.
The location of the cooling system outfall, 200 feet downstream from the 1
l intake, is such that the heated discharge is directed into Thief Slough, a side channel separated from the main channel of the Mississippi by Island 126.
The reactor site is in the Mississippi River valley.- In the vicinity of the site, this valley is deeply cut into highly dissected-uplands. Frcxi La Crosse, Wisconsin, to Prairie du Chien, Wisconsin, the valley varies in width from about 2-1/2 to 4-1/2 miles. The valley walls rise sharply from the level of the river a distance of 500 to 600 feet.
There is little or no agricultural use of the floor of the river valley.
It consists primarily of marshy land, islands between river channels, and extensions of a low-lying flood plain cut by ponds, WP1,
- s sloughs, and meandering stream channels.
Numerous short, steep-sided valleys have been cut into the uplands by tributary streams and intercept the main river valley.
The valley walls of both the main and tributary channels are wooded.
The flat upland areas and some of the tributary valleys are cultivated and grazed.
The main channel of the river ranges greatly in width above and below the site. A series of dams have been built and.are operated by the U. S. Army Corps of Engineers for navigational purposes.(1)
Above Dam No. 8, about 3/4 miles north of the site, the river is nearly 4 miles wide. Between Dam No. 8 and the site, the river is 1500 to 2000 ft wide.
Below the site the river is relatively narrow for a distance of 20 miles, then gradually widens as the river approaches Dam No. 9, 33 miles south of the site.
The LACBWR site is favorably located with respect to drainage.
from the hills to the east because of two short valleys east of the bluff along Highway 35, one draining north toward Genoa, and one south below the reactor site. The two valleys limit the hill area that contributes runoff across the site and only the precipitation that falls on the bluff and a small upland area can cross the site.
This drainage is channeled along the highway and railroad to prevent i
interference with traf fic. A small amount of other drainage from the railroad right-of-way and nearby hills is channeled to the river via two underground culverts. No flash floods from storm runoff have occurred or are foreseen at the site.(2) i WP1.
r
LACBWR was constructed on a fill site, developed from sediment dredged from the river channel, extending approximately 300 feet to the west of the original river bank. The elevation at the site (639' above MSL) is approximately 19 feet above normal river level. The bank is sloped at a 3 to I ratio, and overlayed with rip-rap rock from the sheet pile loading dock at Genoa 1, past LACBWR and beyond Genoa 3.
2.
Foundations and Engineering Characteristics of the Site A description of the subsurface geology near the site has. been -
obtained from rock samples collected during drilling the wells for LACBWR and extensive core sample drilling. Valley fill of sand extends to a distance of approximately 170 ft.
Eau Claire sandstone of Cambrium age underlies the valley fill to a depth of approximately 300 ft.
It is underlain by Mt. Simon sandstone, extending to a measured depth of 635 ft.
Areas close to the site but not within the river valley are characterized by a sub-layer of Mt. Simon sandstone.-
Other formations overlie the Mt. Simon in the following order: The Eau Claire, Galesville, and Franconia Sandstones, and the Trempeauleau formation.
The major structures of LACBWR are founded on piles driven into the valley fill to a minimum density of 50 blows per foot. The water intake structure is of poured concrete construction set on a poured foundation in the site fill on the edge of the river.(3)
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1 3.
Description of Water-Control Stractures The following structures and components-associated with the LACBWR site have been identified as requiring surveillance in accordance with the regulatory guidance in Regulatory Guides 1.127:
A.
Cooling Water System Structure:
Crib House, Intake Screens, Sheet Piling Side Walls, and outfall seal well.
B.
Water Control Structure:
Rip-rap and bank slope and sheet piling for weed diversion.
4.
Engineering Data Compilation on Water Control Structures Engineering data for all existing water control structures are available on-site and accessible.
This data includes: general site data, hydrologic and hydraulic data, foundation and embankment materials data, construction and construction inspection and testing data, data related to concrete materials and sources, data related to geologic features, geotechnical engineering data, seismic and seismic design data and as-constructed drawings. Some photographs of as-constructed structures are available. A considerable amount of additional engineering and geologic data developed through site borings in conjunction with an investigation of liquefaction potential of sites of hydraulic fill is also available onsite.
Based upon the information available, the general type and quantity of engineering data available on-site and/or readily accessible is adequate to meet the inservice water control structures inspection program required for LACBWR structures.
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On-Site Water Control Structure Inspection Program and Reports A formal inspection program for the water control structures employing the methodology set forth in Regulatory Guide 1.127 has not been established to date.
A program which includes all the appropriate elements for all our inspections to be accomplished in a systematic manner will have to be formulated.
Items to be inspected will include the crib house foundation, intake screens, sheet piling side walls, outfall seal well, the rip-rap condition in the vicinity of the plant and the sheet piling for weed diversion. An appropriately detailed check list will be developed and the inspection program will be conducted under the direction of the LACBWR staff experienced in inspection practices.
Inspection reports will be prepared and available for reference. An inspection interval of approximately two years is evisioned. However, in the unlikely event of an earthquake provisions wil' be made for accomplishment of special inspections immediataly af ter the occurrence of earthquake events. This inspcction effort will encompass most essential elements of the Inservice Inspection Program described in Regulatory Guide 1.127.
This inspection effort would be in accordance with the rules of the Commission and the guidelint ; of Regulatory Guide 1.127. and is, therefore, acceptable.
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Because the water-control structures were completed several years ago, the first-inspection will be similar to the inspections described in Regulatory Guide 1.127, Section C.2 and may be considered as initial inspections meeting the requirement of the Commission rules and the regulatory guidance of Regulatory Guide 1.127.
Inspections, with an appropriate check list, as detailed in Section C-2 of Regulatory Guide 1.127 and Reference.3, will be prepared and an inspection report..as described in Section C-5 of Regulatory Guide 1.127, will be prepared documenting the results.
The report will be placed on file at the site for ready reference and future access.
Special inspections, to be perfonned af ter the occurrence of significant unusual events, such as earthquakes or intense local rainfall capable of degrading the.
capability of site water control structures, will also be planned and carried out under the supervision of engineering personnel using pre-established checklists. A report of these special inspections will also be placed on file at the site.
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. ~. _ _
r-e 6.
Technical Evaluation of Inspection Results In meeting the requirement of the rules and regulatory positions of the Commission, the methodology of Regulatory Guide 1.127 includes the accomplishment of a technical evaluation of inspection results when significant changes have occurred which potentially impact upon
~
the capability of water control structures to function as designed.
The technical evaluation would include a complete presentation of the existing condition of the structure and a thorough assessment of the impact of changes on such factors as hydraulic and hydrologic design capacities, slopes, subsurface materials, foundation stability, structural integrity, and structural stability.
At LACBWR, routine visual observations on the water control-structures indicate that no significant changes in the condition of the structures have occurred which warrant accomplishment of a technical evaluation of the change. Additionally, no change to any site water control structure as-built conditions has been identified as a " reportable occurrence" (as defined by Regulatory Guide 1.16) that required plant shutdown or remedial action or corrective measures to permit continued plant operation in a manner less conservative than that considered in the design and construction of the plant, or to prevent the existance or development of an unsafe condition. Therefore, no technical evaluation has been required or perf anned for any of the site water control structures to date.
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Frequency of Inspections The licensee has 'not, to date, established a formal schedule of inspections for LACBWR water control structures. LACBWR intends to schedule the inspections on a 2-year schedule,' preferably at low river water levels in late summer.
Special inspections to be performed after the occurrence of significant unusual environmental events will be planned on an "as requi red" basis.
General estimate of required frequeacy of inspections is in accord with the Regulatory guidance of Regulatory Guide 1.127 and is, therefore, acceptable.
VI. CONCLUSIONS
-1.
Appropriate water control structures associated with the LACBWR site which come under the rules and the regulatory positions of the 1
Commission have been identified. All available engineering data related to the site and the structures are on-site and readily accessible.
2.
A formal inspection program, as outlined in Regulatory Guide 1.127, will not establishcd for the site water control structures.
After formulation of the program inspections of water control structures will be scheduled on a routine basis, tentatively every 2 years.
Special inspections to be performed after the occurrence of significant unusual e.ents, such as earthquake are planned on an "as required" basis.
This general schedule approach and the planned frequency of inspections is in accord with the Commission rules and the regulatory guidance of Regulatory Guide 1.127.
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REFERENCES U. S. Army Corps of Engineers - General Details and Plan of (1)
Operation 9-Foot Channel Navigation Projects, Mississippi
-River, St. Paul District.
-SEP Topic II.3.B, Flooding Potential and Protection (2)
Requirements SEP Topic II.4.F Settlement of Foundations and Buried (3)
Equipment 11 _
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