ML19309B547
| ML19309B547 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/08/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19309B542 | List: |
| References | |
| ACRS-1681, NUDOCS 8004040267 | |
| Download: ML19309B547 (22) | |
Text
-
.s FOIA EXEMPTION (b)5 O
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EN MEETING DATE:
10/26/79 WORKING COPY ISSUED: 1/08/80 CERTIFIED:
2/06/80 MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE LACROSSE BOILING WATER REACTOR WASHINGTON, DC - OCTOBER 26, 1979 The ACRS Subcommittee cognizant of the Lacrosse Boiling Water Reactor met in 26, 1979 Room 1046 at 1717 H St. N.W., Washington, DC at 8:30 a.m. on October to review the proposal to enlarge the storage capacity of the spent fuel Notice of this meeting was published in the Federal Register on storage pool.
October 12, 1979 (Attachment A).
A copy of the detailed schedule of presentation No written statements from the public were received is attached (Attachment B).
No written reports were nor were there any requests to make oral statements.
At list of documents issued or approved by the Subcommittee.at this meeting.
provided to the Subcommittee during this meeting is attached (Attachment C).
ATTENDEES NRC STAFF ACRS J. Shea W. Kerr, Chairman C. Woodhead S. Lawroski D. Ziemann J. Lee, ACRS Consultant J. McKinley, Designated Federal Employee P. Tam, ACRS Staff 1
f 8004040 2 6 9 l
8
. ATTENDEES CONT'O DAIRYLAND POWER COOPERATIVE DAMES & MOORE R. Shimshak M. Nataraja G. Boyd R. Prince E. Tremmel S. Raffety C. Angle NUCLEAR ENERGY SERVICES PUBLIC R. Miles E. Gasser, Gasser Associates P. Buck R. Bradee, Milwaukee Sentinel I. Husain A. Yoli L. Zezza Executive Session (0 pen'to the Public) dr. Kerr, Subcommittee Chairman, opened the meeting at 8:30 a.m. with a statement regarding the conduct of the meeting in accordance with the provisions of the Federal Ad ' ory Committee Act and the Government in the Sunshine Act.
Mr. J. C.
.ninley was the designated federal employee.
Dr. Kerr reviewed the proposed schedule (Attachment B) and asked the Subcmnmittee members and consultant if they had topics they would like to add to the discussion.
Dr. Lawroski asked for a status report on the liquefaction potential at the i
site.
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e
. getina with Dairyland Power Cooperative and the N F
ibed the current status of the plant; cted to achieve 15,000 MW days /t Mr. R. Shinshak, plant superintendent, descr it tas operating at 85% of rated power and expei h time it would be 26, 1980 at wh c locations of which 133 are currently El average burnup by January t red at GE facilities The spent fuel storage pool has 134 storage Eight additional irradiated fuel elements are s to be returned cccupied.
at Morris, Illinois.
to the plant.
being fabricated to the design ill be Currently, replacement fuel storage racks areIt is expected that the tions.
described in the amendment.
These new racks will provide 440 storage loca delivered in December 1979.
tarting in 1970, to find ways and Mr. Shimshak described Dairyland's efforts, st least 10 approaches locations to dispose of spent LACBWR fuel; al tion and so Dairylan A public hearing has but none developed into an acceptable so u age pool.
the capacity of its current spent fuel storing Board and a decision is i
been held by an Atomic Safety and L cens in late November or early December.
describes the current spent fuel Mr. Angle, an engineer with Dairyland Power,The pool is 11 feet squ tains space and storage racks and the pool arrangement.In additipn to ask.
feet deep.
support pads for the spent fuel transfer c tly occupied.
for 134 fuel elements of which 133 are curren ilable to LACBWR; one holds two Two models of spent fuel shipping casks are avaConsideration is for those fuel assemblies that have fuel elements and the other holds eight.
development of special shipping canistersSuch a canister is experienced gross fuel rod failure.fuel storage racks which incorporate a Mr. Zezza described the proposed spent All of the racks are seismic unique two tier design (see Figure 1).
e N
i All components j
braced to each other and to the pool walls at three elevations.
of the racks are fabricated from type 304 stainless steel except the leveling l
screws which are 17-4 pH stainless steel and the fixed neutron poison which is a boron carbide composite material.
Each fuel cell has poison strips on two opposite sides (see Figure 2) and alternate fuel cells are rotated 90* so that stored fuel will see poison on all four sides (two sides from its cell and two sides from adjacent cells).
The poison material is boron carbide particles imbedded in a fiberglass cloth Two of these bonded fiberglass sheets are encased in a bonded with a polymer.
stain 1ess steel sandwich which is then attached to one side of the storage A similar sandwich is attached to the opposite side.
Inspection ports cell.
are incorporated near the top of the stainless steel sandwiches to permit visual confirmation of the presence of the poison material and to allow venting of any gas generated within the sandwich.
The boron carbide composite material has been tested to 10" rads without At Lacrosse, if freshly discharged fuel is put into significant degradation.
10 a cell every five years, the poison material would see something like 3+ x 10 rads over a 25 year lifetime.
Fuel assembly support plates are welded into the grid structure of the lower A remotely operable removable fuel assembly support plate is tier cells.
Access to the lower cells is provided for the upper tier (see Figure 3).
obtained through the upper cells by removal of the upper support plate.
The spent fuel storage cells are designed to accommodate both the separate fuel shrouds and fuel assemblies either separately or both in the same cell.
Mr. Yoli described the thermal / hydraulic and mechanical / structural design of The mechanical design had to work the proposed spent fuel storage racks.
within the existing pool and accommodate Exxon as well as Allis Chalmers fuel Each fuel element is independently supported.
and the separate fuel shrouds.
The racks are designed to acconnodate the fuel drop and cask drop accidents as well as seismically induced loads, r
e The thermal design had to allow flow openings to permit convection cooling of I
the spent fuel.
Sufficient space (* 9") has been allowed between the bottom of the racks and the bottom of the pool to assure an adequate flow area in I
spite of debris accumulation.
less than 0.95 for the The major nuclear design criterion was to keep k,ff worst case configurat'on.
The major thermal consideration was to avoid boiling at the highest allovable pool temperature. Other design considerations are shown on Figures 4, 5, 6, and 7.
The pool cooling system is adequate to accommodate the maximum anticipated heat load.
If all pool cooling is lost it would take approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> to raise the pool temperature sufficiently for boiling to take place (normal heat load, with a fresh full core discharge the time would be shortened to about 81shrs).
A makeup rate of 2 to 5 gpm would accommodate the heat load in the boiling mode.
There was considerable discussion of the thermal and nuclear analyses, and the Subcommittee and its consultant appeared to be satisfiec with the assumptions and conclusions.
Mr. R. Prince of Dairyland Power reviewed the radiation exposure experience at LACBWR for the past 3 years in the vicinity of the spent fuel storage well (see Figure 8). The total annual exposure at LACBWR averages about 210-220 man rem per year, thus the exposures related to spent fuel operations represent a small fraction of the total.
Exposures during fuel handling are controlled by the height of the sill of the canal gate which controls the height of shielding water above an irradiated fuel element being moved. The new, double tiered, storage racks will not extend above the canal mte sill and, therefore, there should be little change in personnel exposure.
If there is a leak in transfer canal that allows the water to drain down to the cand gate sill there will still be about three feet of water over the top of the upper tier of spent fuel. Mr. Prince estimated that this reduction in
+
. tes of 10-20 r/hr at the top of shielding would result in radiation exposure raMr. Prin than a drain f
h Since the pool.
line failure, by which all water could be lostry I and has redundant valves, the drain line is designed to seismic Catego did not believe its failure was credible.
E' l of the used racks that are Mr. Prince also discussed the problem of disposaThe g decontaminated f
200 mr/hr on contact).
to be removed.
and disposed of as low level waste (below The total fuel storage pool.
Figure 9 shows the water chemistry of the spent
-3 microcuries per t 4 x 10 gross beta gamma activity of the water is abou oilliliter including the tritium constituent.
ecurity aspects of the A closed session (20 minutes) was held to discuss sMr. Shimshaf spent fuel storage facilities.
ld be perpertrated from within the l and their loyalty and taken to assure that r.o adverse action couHe emphasi facility.
dedication to the plant and its protecton.
that resulted in a Safety i
Mr. J. Shea (NRC) described the NRC staff rev ew an Atomic Safety and f
Evaluation Report (SER) and a public hearing be ore early Licensing Board.
i ation factor of 100 allowed December.
In response to a question relating to the decontam nthrough the for iodine removal as fission product gases passTechnical Specificat over the spent fuel, Mr. Shea noted that thet condition to allow for the minimum of 16 feet but this is a trans end into the pool..Normally the po i
The decontamination ment of water when a fuel cask is lowere the spent fuel.
ations conducted with the will have more than 20 feet of water over factor becomes important only when considering ope has aged ntainment isolated.
containment unisolated.
less than about 43 days will be done with the co
.. Mr. Shea confirmed that the NRC would not make a critically analysis of the racks assuming that one or more of the boron poison strips are missing unless the inspection program finds that one or more are missing.
The NRC staff mentioned that the hearing board, taking note of the systemati':
evaluation program (SEP) review of LACBWR and the need to convert the current Provisional Operating License to a Full Term Operating License, asked for an economic analysis of the costs of modifying the spent fuel storage capability if the SEP found that a Full Term Operating License could not be issued.
Th.3e costs were to be compared with the costs of shutting LACBWR down immediately.
Dairyland Power confirmed that it plans to continue to use stainless steel clad fuel for a variety of reasons. One is that replacement fuel is needed promptly and it would probably take 2 to 3 years to get a zircalloy clad fuel licensed.
Mr. Nataraja, consultant to Dairyland Power, reported on the status of the evaluation by Dames & Moore of the liquefaction potential of the LACBWR site.
Field and laboratory testing has been completed and Dames & Moore concluded that the LACBWR site had adequate factors of safety against liquefaction up to an SSE of 0.12g at the ground surface.
He implied that the NRC agreed with the Dames & Moore findings with a few coments. Upon questioning, it was discovered that there continues to be a significant difference of opionion between the licensee and the NRC staff (and its consultants) regarding the liquefaction potential for the SSE. This matter may become the subject of a future Subcommittee meeting.
Caucus (0 pen to the Public)
Dr. Kerr suggested that the Subcondde wise the full Comittee of this review and, aside from one or two suggestioni, he did not recommend a presentation to the full Committee. The other member and the ccasultant agreed with this proposal.
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.g-to the ACRS for Lee to forward any comments or suggestions Dr. Kerr asked Dr consideration.
oral report to the full ACRS It was agreed that the Subcommittee would make an hk at a convenient time.
The meeting adjourned at 2:0S p.m.
f this meeting is on file A complete transcript of the open sessions o N.W., Washington, DC, in the NRC Public Document Room at 1717 H St.ters, Inc., 444 Note:
or can be obtained from ACE Federal Repor20001 - (202) 0 Street, Washington, DC i
I
BBSD Federal R"-. / Val M. No. fee / Petday. Odober u. we / Nonees l
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1046. L*17 H St. NW, Washsngton. D.C mishea==mittee en hed=r gentayy, s
Asesenes Carieral discussion of the current status and future plans of the Group B.of the Advisory Committee 20555. De purpose of this meetmg re to Condwised heettar Scienma Section.
for Phyedotogy. Cae6 der, and testacador coer. der proposed changes to the existing spent fuel storage pool to Sloeogy;leseemg pp r.tapemme Acmw Coermwnee ti.m. e..
.rca :d in accordance with the Pederal
[
Advisory Cootenttee Act. Pob. L e -4n reschsshded from October in 1s79.
October s. tv s as asiended, the Netxmal Sosna Notim me p=heumed in the Fadural i
pm om. =-mar rems so.n se se - t Foundation ammoimcas the loGowing 19siseer c septsaber 20.iars (44 FR anAmu cosa amee meseng-
, yj, esaast: Subcommfttee on Mai w amordance with the procedans on Dwatopmental Biology Croup B of the AdmorT outlined in the Federal Resistae on N'
Committee for Phystology. CeDular and October 1.1779 (44 F1t 56406), oral or In accordance with the Fed rSt Molecdar Hology.
written statements may be presented by Advisory Committee Act. Pub. L v2-es3. oats Ano Tass: October 29 and 30.197.
members of the public, recordings wtIl as amended. the National Sesence -
e.00 a.m. to 1.00 p.m. each day.
be permitted only dunng those portions of the meetmg when a transcriptis being Foendation announces the foUowmg ps.Aca: Room m Natinrtal e,c=ne, kept. and questions may be asked 'only Foundation.1800 G Street. N.W.,
by members of the Sebcommittee. Its meetmg-maass: Subcommittee on Developmental Washington. D.C 32550.
consultants, and M Persons dessng Type or anzTme: Comed.
Biology of the Advisory Committee for to make oral statements ahmM notify 00887Aof Pensoec Dr. Donald Gaean, the Designated Federal Employee as far Physiology. Cellular and Molecular Propam Direcair, bchemistry ta advance as practicable ao that mology.
Prtgram. Room 13a Natioma! Eria.c, appropriate ansagementa can be made DATE Aase Tuss:m.... %-.1.2. and 3*
Foundation. Waaluasson. D.C. 2Guc.
to allow the necessary time danag the 1979-4 am. to 5 pm. sach day.
Tal=pha=a N meeting for such statements.
etAca: Room 643. National Science
,y,,,,g,, aimea===TTse To pevvide De agenda for subject aneeting obs!!
Foundat>on. taoo C Street. N.W.
advice and recosimendatmas be as fouowe Washington. D.C 20550.
concerums support for rumaarch in TTre or marTwee Closed.
Molecular blogy.
hider. Octobera u?P aanma To rrwew and eveheate 430 a.m. Usnt de Carmhsase af arsamms courtACT Pensoec Dr. Mary F. Cutter, s
Program Director.Devebpn etal research proposala as part of the h Subcommitane may meet la ' eve Biology Program. Room 326. Nationa]
selection procena for awards-Semon. with any of fis consuttants wtio may Science Foundation. Washmglon. D.C.
NEA8 oft POR CLo0Wect De proposals be present, to explore and ensange then 20550, telephone (322) 852-4314.
being rvviewed inc!ude inforuration of a Pnhminary openons mentems menen which abound be ammiend dar b meettig and propnetary or cotzfidential nature.
',, g,,,,3,,,,p,,,,,us Pustroat op ennen
,Trar:To provvie tacluding Marcs! inicartion.
to the full r%
advice and recommendetions i
a a
s fu reaaad m At the concleston of the LG-co7* P**^ '
Sesafort the Subcominee wtB beer
,3 c rmstro g
8U individua!e asectiated wfth the AcaseDA:To ruww and evainate proposals.Dese matters are withm presentations by and hold drscusstons with reprmetetives of the NRC Staff, rmarch proposals as part of the exemptions (4) and (6) of 5 USC.
the Dairyland Power Co,m.L. et al senection process for msed*
552b(c). Government in the Sanshin, and their Canaultants, peftment tp this MEA $oelPom CtoS#eG:De proposals Act.
"'i"' ubcommittee may then enacte to bemg reviewed include information of a AUTwosuTY TO CLost utETDue: Dis eS propnetary or confrdential nature.
determination was made by the determine whether the matters including tedmacalinformation; Committee Management Officer Identified in the irdtial session have financial data, such as salanea, and pursuant to provisions of Section 10(d) been Adequately covered and wtether personalinformation concerning of P.L 92-463.De Ccr:runfttee
,anyects n@o k h h &
%4..siduals associated with the Management Oficer was delegated the full CominfMe.
N r sals. Dese matters are wrthm authority to m6ke such determinatioha In addhm. ft may k neemary b a Wti ns (4) and(6) of 5 U.S.C.
by the Director. NSF. un }a!y 6.1879.
the S-,--oh to hold one w mm 552b(c). Government in the Sanoinae Myce F., api==ta.
closed sessions for the purpose of Act.
ActavCamase Meiasmo.nr Causessair explorktg matters is4ius proprietary information. I have determined. frr aumoarTT To ctosa metrusa: Dis october s. tars.
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accordance wfth Sebeection to(d) of determination was made by the yeo mre.n ra Pebbc I.Aw 92-463. that, should such Committee Management Offreer serais cons nee e pursuant to provisions of Section told) smions be required. It la necessary te Management Officar w as delegated the NUCLEAR REGut.ATORY '
dose these sessions to protect of Pub. L 92Aa3.De Committee proprietary information (5 UAC, authority to make such determmations COM&taSSION 552b(cK4)).
Furtbar informacon regardmg topics by the Director. NSF. on july L 1W9.
Adwtaory Coinmittee on Reactor to k AW wh th unetmg Jeyes F. t =M Safeguards; Subcommittee on the La has hen Mlad a esdoduled. &e Actmg Cosumatrae Manspeess Ceardamer.
Croase BoWrg Water Reactoq Maetag Chairmanta ruMms en r== pia =#= lar the Ocsober a tyra De ACRS Subcommittee on the la opportunity tg present oral stateswnts tre o m aue rnw s m a ee w Canae Boating Watee >=ctre will hand and the time allothed teorefoe can be a meeting on October at lars km Rooms obtened by~a prepaid teamphone sail to
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I 59024 Federal Register / Vol. 44. No.199 / Friday October 12,1979 / N; ices the Designated Federal Employee for from 9 a.m.lo 4 p.m., Monday through development of the Uniform Guidelines this meetmg. Mr. John C. McKinley.
Fnday.
on Employee Selection Procedures. the (telephone 202/04-3285) between 8.15 poa Fuernssa sosroussAnoes CostrACT:
Office of Personnel Management is a.m. and 5 00 p.m EDT.
William H. Lynch. Work Force committed to actions which will-Background information concernina Information Division (202) 254-9778.
eliminate prohibited discnmination in items to be considered at this meeting gy,PLEsoENTAny iseronesanosc The amployment practices on grounds of can be found in documents on file and ongmal CSC-4 system of records was disability. race, color. religion, sex, or avanble for public inspection at the designed to cover only those personnel national origin in so far as OPM N'
?ublic Document Room.1717 H research and test validation records that. Government. wide authorities permit.
Sr : NW., Washington. D.C. 20555 and were physically maintained by the Additionally. OPM is committed to at the La Crosse Public Library. 800 former Commission *s (now OPM's) actions that accomplish these aims l
Mam Street. La Crosse. WI 54001.
Personnel Research and Development while assuring that the individual's self.
Dated: October 5.1979.
Center (PRDC). Since these records identification is not provided to the
?
lohn C. Hoyle.
pertained to current and former Federal selecting official. Thus, not only is it Advisory Committee Management Officer, employees and applicants for Federal appropnate for OPM to publish a I
pn r= mins ma io. nam aes ;
employment. when revising the former
~ Government. wide systemtf* records for am cooe vs e,
CSC ;ystems of records it was our use in meeting these mandates, but a intention to identify them as an OPM/
single OPM Government-wide system of CENM record system.This records, along with acccmpanying OFFICE OF PERSONNEL approach, however, would not cover regulations and guidance, will help MANAGEMENT similar records that agencies have assure that such records will be properly maintained or will maintain in the futm maintained. It will also alleviate the Privacy Act of 1974; Proposed Revised on their own applicants or current and need for every Executive Branch agency System of Records and Proposed New former employees, either as a direct to publish its own systems notice for System of Reccrda result of an OPM request or when doing such records.
Asancy: Office of Personnel research or validation surveys on their nere are several cities in the system Management.
own initiative under the Uniform notices to 5 CFR Part 297.Rese Acnoec Notice: Proposed revision of an Guidelines on Employee Selection existing system of records and a Procedures. OPM has now determined regulations were published as proposed proposed new system of records.
that it is appropriate for OPM s system in the Federal Register of May 29.1979 notice to cover these agency records.
FR m. M @te MH be sunsasAny:ne Office of Personnel thereby changing the system to a published after consideration of Management (OP51) published on May Government-wide system. By doing this, comments.
29.1979 (44 FR 30836), a notice of those agency records maintained as a Concurrent with publication of this proposed revisions to the former Civil system of records and used for proposal for a revised and a new systs Service Commission's systems of personnel research projects or in test of records. a " Report on New Systems" records remaining in effect under validation surveys would be covered.
has been filed with Congress and the Section 902 of the Civil Service Reform Agencies m3y be maintaining such Office of Management and Budget. No I
Act of 1978. Public Law 95-454. Among records eitner at the request of and waiver of the 60<!ay advance period has the system notices to be revised was under the direction of OPM or, been requested and, therefore. these CSC-4. Personnel Research and Test alternatively, under OPM's oversight systems will become effective. as Validation Records, which was to responsibility for personnel proposed, on December 11.1979. unless become OPM/CENIllAle3. Personnel management policies and practices comments received necessitate changes.
Research and Test Validation Records.
(including authority to determine ne complete text of both system.'
The purpose of this proposalis to advise adverse impact in the total selection notices appears below.
that OPM intends to now revise'the process of Executive Branch agencies).
8""'
CSC-8 system to become OPM/GOW-Because in either case OPM would need
- 6. Personnel Research and Test to review agency personnel research N7 N'"**'
Validation Records.The OPM/
and test validation records, including ' ' #las-ceS *8*mManaser.
f CENTRAlc3 system is therefore not those where the agency initiated the
'N adopted. Additionally this proposal also research. OPM may appropriately idectifies a new system of records to be p,.lish such a Government. wide system
,,,rais massa.
knoun as OpM/ GOVT-7. Applicant of records Personnel Research and Test Race. Sex. Ethnicity, and Disability Regarding the proposed new system.
Validation Records Status Records.
of records. OPM/GOW-7. Appitcant couusrty o ATE:Any interested party Race. Sex. Ethnicity, and Disabilny may submit written comments regarding Status Records, it is OPM s intenhon to l
these prcposals.To be considered.
use the records in this system to Director. Personnel Research and l
comments must be received on or before implement the requirement of Section Development Center. Office of i
November 12.1979.
310 of the Civil Service Reform Act of Personnel Management.1900 E Street, l
Aoonass: Address comments to the 1978 codified as 5 U.S.C. 7201, and the N.W. Washington. D.C. 20415. OPM Deputy Assistant Director for Work Uniform Guidelines on Employee regional offices (see list of regional Force Information. Agency Compliance Selection Procedures (1978). The law (5 office addresses in the Appendix to and Evaluation. Office of Personnel U.S.C. 72Di(c)) specifically requires the GPM) Federal Register notice of Mansgement. (Room 6410) 1900 E Street Office of Personnel Management to proposed systems. 44 HL 30836. May 29.
NW, Wash ngton. D.C. 20415.
Implement a minority recruitment 1979), and agency personnel offices (or 1
Comments received will be available for program for Executive Branch agencies.
other designated offices) conducting l
public inspection at the above address Additionally, as a party to the such programa.
k E u)i t ah lh i
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TENTATIVE DETAILED SCHEDULE LACROSSE BOILIE WATER REACTOR SUBCCMMITTEE MEETING ROCN 1046,1717 H ST., NW WASHIE TON, DC OCTOBER 26, 1979 TIMES ARE APPROXIMATE 8: 30 a.m.
EXECUTIVE SESSION (OPEN)
Revies schedule of presentations and add or delete topics MEETING WITH DAIRYLAND POWER COOPERATIVE (DPC) AND THE NRC 8:45 a.m.
STAFF (DOR) (OPEN) 1.
Description of current spent fuel storage pool and j
racks - DPC 2.
Description of proposed changes - DPC 3.
Mechanical / Structural considerations including bases l
for materials selection, unique design details, i
corrosion or chemical reactions, etc. - DPC 4.
'Ihermal/ Hydraulic considerations including cooling following a loss of shield water, pool toiling, lower plenum flow area and potential for blockage, etc. - DPC 5.
Neutronic/ Criticality considerations including conse-quences of a systematic assembly error in the location of the poison strips, corrosion or loss of poison, use of soluble poison, etc. - DPC 6.
Access / Handling considerations including radiation exposure for normal operations and with a loss of shield water, etc. - DPC 7.
Operational considerations including installation and removal of fuel and racks, decontamination and disposal of used racks, shield water quality control, ecoling system reliability, pool heatup rate, pool housekeeping and handliry of damaged fuel, etc. - DPC 8.
NRC review, evaluation and conclusions - DOR f
9.
Schedule of futher actions - DOR 2:00 p.m.
CAUCUS (OPEN) 2:30 p.m.
ACL70 URN k TTACHMENT B
~'
ATTACHMENT C DOCUMENTS AVAILABLE TO THE LACROSSE SUBCOMMITTEE - OCTOBER 26, 1979 1.
Schedule for Lacrosse Boiling Water Reactor Subcommittee Meeting October 26, 1979, undated (Attachment B).
2.
Federal Register Notice dated October 12, 1979 (Attachment A).
3.
Copies of transparencies used by Dairyland Power Cooperative (17 sheets).
4.
Project Status Report Lacrosse Boiling Water Xeactor dated October 26, 1979.
5.
Dairyland Power Cooperative letters dated April 20, June 7, July 11, August 7, September 28, October 4 and 26, November 20 and 29,1978, January 4 and 31, February 14, March 1, May 17, and June 26, 1979.
6.
NRC Safety Evaluation Report dated July 13, 1979.
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M_ECHANICAL DESIGN CONSIDERATIONS RACK DESIGN CRITERIA
. MAXIMUM CAPACITY
. COMPATIBILITY h TH ALL FUEL TYPES STORAGE / HOLD-DOWN OF F/A SHROUD INDEPENDENT SUPPORT OF EACH F/A
. WET INSTALLATION WITH STORED FUEL
. COMPATIBLE WITH STRUCTURAL, NUCLEAR AND T.H. REQUIREMENTS POOL INTERFACE CONSIDERATIONS
. CORE SPRAY BUNDLE STORAGE
. ADEQUATE CASK SET DOWN AREA
. CASK DROP PROTECTION REQUIREMENTS
. CONTROL ROD STORAGE REQUIREMENTS
. COMPATIBILITY WITH OTHER FUEL POOL EQUIPMENT RACK MATERIAL SELECTION STRUCTURAL MATERI ALS 304SS,)17-4PH (WITH APPROPRI ATE HEAT TREATMENT AND CLEANING
. BASES FOR SELECTION
- MATERIALS COMPATIBLE WITH POOL ENVIRONMENT, F/A AND POISON MATERIAL
- MATERIALS HAVE EXTENSIVE APPLICATION IN SIMILAR ENVIRONMENTS AND HAVE PERFORMED SATISFACTORILY 6
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i NUCLEAR DESIGN CONSIDERATIONS RACK DESIGN CRITERIA VALUE < 0.95 FOR WORST CASE CONFIGURATION
.KEFF
. COMPATIBLE WITH ALL FUEL TYPES AT HIGHEST ENRICHMENT ACCOMMOLATE STORAGE OF ZIRCALOY SHROUDS COMPATIBLE WITH STRUCTURAL, MECHANICAL AND T.H. REQUIREMENTS POISON MATERIAL CONSIDERATIONS CORROSION / LOSS OF POISON 10 CONCENTRATION USED IN ANALYSIS 0.022 GMS B10/CM2 B
10 CONCENTRAT!6N 0.024 MINIMUM SPECIFIED B 10 CONCENTRATION OF ACTUAL MATERIAL 0.038 AVERAGE B VERIFICATION OF POISON DURING FABRICATION AT PLANT SITE FIGURE 5 1
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THERMAL-HYDRAULIC DESIGN CONSIDERATIONS RACK DESIGN CRITERIA
' NO LOCAL BOILING AT HIGHEST POOL OPERATING TEMPERATURE
. LOW POTENTIAL FOR CELL FLOW BLOCKAGE
' COMPATIBLE WITH' MECHANICAL, STRUCTURAL AND NUCLEAR REQUIREMENTS POOL COOLING SYSTEM CONSIDERATIONS
, MAXIMUM REQUIRED COOLING CAPACITY
- NORMAL HEAT LOAD
- ABNORMAL HEAT LOAD (FULL CORE DISCHARGE)
LOSS OF COOLING ABILITY
- TIME TO REACH BOILING (NORMAL, ABNORMAL WATER LEVELS)
- COOLANT MAKEUP RATE a
i FMc6 e
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STRUCTURAL DESIGN CONSIDERATIONS RACK DESIGN CRITERIA
. ACCOMMODATE APPLICABLE LOAD COMBINATIONS
- SEISMIC (0.12G) 4 FUEL DROP ACCIDENTS CASK DROP ACCIDENTS
- SHIPPIGG/ INSTALLATION
. COMPATIBLE WITH MECHANICAL, NUCLEAR AND T.H. REQUIREMENTS
- RESULTED IN LATERALLY BRACED RACK DESIGN POOL INTERFACE C0!iSIDERAT10NS
.. POOL STRUCTURAL INTEGRITY
- STATIC / SEISMIC LOADS
- CASK DROP LOCAL POOL WALL / FLOOR STRESSES
. LINER INTEGRITY FOR DROP ACCIDENTS ANALYSIS CONSIDERATIONS FUEL RACK ANALYSIS
- FINITE ELEMENT LUMPED MASS MODELS
- FUEL ASSEMBLY / FUEL RACK IMPACTS PCOL STRUCTURAL ANALYSES
- FINITE ELEMENT LUMPED MASS MODEL (STATIS/SEI'CMIC)
- CASK DROP ANALYSIS
- P0OL DRAIN LINE ANALYSIS Fieune 7
~
o Th3 annual man-rem cxpo2uro in th3 FESW arca frcan all opsrstions for the past three years is stummarized below:
i I
Man-Rem Exposures All Other Operations
~
Year Refueling (Except Those Described Below) 3.136 1978 0.360 4.584 1977 0.893 1.655*
1976 0.314
- Includes rack modification of 1976.
The proposed modification is not anticipated to have any significant impact on these occupational exposures.
OPERATOR TOURS During all fuel handling operations, the FISW water level is main-tained at the 700' elevation.
While the plant is operating, the water level is usually maintained below the 700 ' elevation.
The dose rate in the immediate vicinity and/or directly over the foot pool is 5-30 mrem /hr when the water level is at the 680 elevation.
Approximately three feet from the edge of the pool, all dose rate levels are less than 5 mrem /hr.
During plant operation, occupancy times in the vicinity of the FESW are minimal.
The FESW is not located in a high traffic area.
Operator tours rapresent the most significant ~ occupancy factors for this area.
These occupancy times amount to approximately two level.
It is conservatively estimated hours per week on the 701' out of this time,10 minutes per week is spent in the immediate
- that, vicinity of the FESW.
The annual exposure due to this occupancy is 0.17 man-rem based on an average exposure of 20 mrem /hr.
ROUTINE MAINTENANCE EXPOSURES The maintenance jobs that represent any significant personnel exposure due to the increase in storage capacity are the routine changing of the fuel well purification system filters and deminer-aliger resins.
These filters and resins have been changed about every six months for the past four years.
The storage well capacity was increased in December 1976, without any affect on this maintenance schedule.
This could be due to the fact that this modification (84 to 134 fuel assembly storage locaticms) does not represent a significant increase with regard to the demineralizer and FESW system capabilities.
Also, there are currently 113 spent fuel assemblies in the storage pool.
Exposures received during these maintenance jobs did not show any appreciable increase after the modificatien.
The average man-rem exposuxe for resin sluicing is 0.06 and frst filter changing is 0.7.
The annual man-rem exposure for these jobs is 1.5, assuming routine changes at 6-month intervals.
f/GURE O
a s
g SHIELD WATER QUALITY CONTROL A.
Nuclide Analysis The spent fuel pool is sampled monthly for gross S y activity analysis.
Since 1975, these activities have averaged about 1 x 10-3 uCi/ml.
No increase in pool activity has been detected since the first modification in December 1976.
The results of a gamma nuclide analysis taken on April 26, 1978, follow:
Nuclide Concentrations, uCi/ml Mn-54 7.7 x 10-6 Co-58 2.5 x 10-5 Co-6 0 6.4 x 10-5 Sb-122 2.1 x 10-5 Cs-134 2.1 x 10-"
Cs-137 5.8 x 10-"
Ce-144 9.2 x 10-5 Tritium concentrations are determined on a monthly basis, the average value being 3.3 x 10-3 uCi/ml E.
Chemistry Analysis (Monthly)
Administrative Analysis Average Limits (1) pH 6.10 4.5 - 8.0 (2)
Conductivity, umho/cm 0.40 10.0 (3)
Chloride, ppm
< 0.02 0.5 (4)
Turbidity, FTU 0.05 NONE (5)
Gross S y, uCi/ml 1 x 10-3 NONE (6)
Gamma Spectrum, pCi/ml (7)
Tritium, pCi/ml 3.3 x 10-3 NONE Baron concentrations are determined twice per year, the average value being < 0.02 ppm.
FicuRE $
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