ML19207A374
| ML19207A374 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/13/1979 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908170284 | |
| Download: ML19207A374 (6) | |
Text
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,3 NUCLEAR REGUL ATORY COMMISSION t
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o,, yJ:u g v 4y JUL 1 3 G79 MEMOP1.NDUM FOR R. Vollrner, Acting Assistant Director for Syste atic Evaluation Program, DDR FROM:
B. Grimes, Acting Assistant Director for Systems Engineering, DDR
SUBJECT:
RESPONSES TO MOTION TO SUSPEND PROVISIONAL OPERATING LICENSE DPR-45 Plant Name.
Lacrosse Boiling Water Reactor Docket No..
50-409 TAC Nos.-
11840, 11835, 11837 Project Manager:
J. Shea Status:
Complete Enclosed is the Plant Systems branch response' to two of the motions to suspend the LACPMR operating license (TACS 11840 and 11837).
In response to TAC 11835, we do not believe we are prepered to provide a technical response at this time.
We are currently reviewing the licensee's justification for unlinited purging (or ventilation).
Because the licensee did not conply with the generic letter directing them to cease purging or limit purging to an absolute ninirari, r.ot to exceed 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year, we may be required to take sor.e interin action while we continue our reviet We would like you to arrange a meeting with the licensee for him to discuss his justification for not complying with the above.
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y/7% w I'f B. Grimes, Acting Assistant Director for Systems Engineering Division of Operating R7 actors
Enclosure:
As stated
Contact:
E. Lantz X-2 7110 cc:
See next page D 3f U31
f cc w/ enclosure:
D. Eisenhut
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G. Lainas MIPC T. Tel ford W. Russell G. Knighton D. Ziemann E. Adensam J. Shea E. Lantz E. Reeves Y.S. Huang D. Shum
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I Item 3:
Whereas, LACBWR remains in violation of 10 CFR 50.54(b), which requires that " primary reactor containn ents for water cooled reactors shall be subject to the require: tents set forth in Appendix J",
and Whereas, LACBWR has by DPC's ovin admission f ailed to meet Appendix J requirements, as illus trated by at least ten repartohle occurrences since Septec ter 1975, (Reference 4-13)I and Whereas, DPC has been unable to arrive at any solutions to the electrical penetration leaks, and thus has no guarantee that such leak, will not continue, and Whereas, we believe that said leaks represent another breach of the containment integrity and as such present substantial dangers inimit al to the health and safety of the pu'olic, We, therefore, req 1est that the f!RC order DPC to cease cperation of LACBWd until such tin e as all leakage problems are pennanently resolved.
P.espo_nse to Iten 3-10 CFR 50.54(b) requires that primary reactor containments for water cooled reactors shall be subject to the requirements set forth in Appcndix J.
Appendix J to 10 CFR 50 specifies the requirements for testing proce-dures, testing frequency and testing method.
Appendix J also specifies the leakage limits for determining test failures, and associated reporting procedures for such failures including corrective action plans to ef f ect the repairs.
LACBWR has t,een conducting its containment leak test in accordance with the requiren en ts con ta ined in the Technical Sp cifications, v;hich were approved by tmC. LACBWR has also been reporting all test failures and associated corrective ac tions for repairs.
Appendix J recngnizes test failures.
Reporting test failures by the licensee is required by the Appendix J.
It is not an adoission by the licensee of failing to reet Appendix J requirements.
The specifically cited clectrical penetrations havn redundant leakage ba rr ie rs.
The leak occurred only through one of the barriers at e soll fr action of the allowable leakage limits.
The said leaks resulted in a loss of redundant leak tight barriers but did not represent a total breach of contair. ment integrity.
As such, it had no significant adverse ef fect upon public health and safety.
Based on the abovc discussion, the fiRC has concluded that LACBWR neets the regulation requirements and that the fiRC can not arbitrarily order LACBWR to cease its operation.
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j Whereas, the LACB',lR spent fuel storage pool is presently filled to capacity, and Whereas, there is no storage space available for the cight irradiated assemblies that are currently being stored at Morris, Illinois under a one-tirae-only three year te:r.norary contract, and Whereas, the irradiation of more assemblies vothout a guaranteed off-load capacity is generally regarded as irresponsible, and Whereas, a DPC request for the expansion of the LACRWR spent fuel stroege pool is currer tly under consideration by the fiRC, and Whereas, the production of any more spent fuel would only serve to increase the " sense of urgency" that DPC has in the past used as a justi-fication for the speedy approval of their proposed spent fuel expansion pl a n,
We, therefore, request that the tiRC order DPC to cease operation of LACBWR until such time as DPC's spent fuel pool expansion is approved by the tiRC.
Re_sponse to Item 7:
It is the fiRC's position that the health and safety of the public is not impaired by leaving a core in the reactor vessel.
Thus, i f some tirne in the future the Dairylana Power Cooperative does not have any other place to store spent fuel assemblies it can leave them in the reactor vessel.
Because of this position, the fiRC does not have regulations requiring licensees to maintain room in the spent fuel pool for a full core offload Without such a regulation and viithout indication of a health and safety concern the fiRC can not arbitrerily order the cessation of the operation of a plant because of an impending shortage of storage space for spent fuel.
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PROFL5SIONAL QUALIFICATIONS OF Y.S. HUANG I am presently employed as a Senior Erajincering Systens Analyst in the Pl9t 5ystems Branch, Division of Operating Reactors, Office of Nuclear Reactor Regulation.
My duties and responsibilities involve the revicw and evaluation of cor.tainment leak testing, post accident hydrogen controls inside containxnt, and associated containt.ent systems.
I joined the Commissicn in February 1977, as a Nuclear / Mechanical Engineer in the Of fice of Standards Development where rr.y duties were developirjg regulatory guides and regula tions relating te containment system designs.
From.lanuary 197A to January 19/7, I was associated with Gilbert / Con;on-wea i t.h Associa tes, Inc. as a staf f specialist responsible for the design of nuc' oar po'.ter plants. especially in the fluid and heat transfer areas relatir.g to reactor containrr.ent designs.
From July 1971 to December 1973, I was associated with 5 tone and Webster Engineering Company as a r.echnical engineer responsible for the design and perforc.ance evaluation of power plants including fossil and nucle r fuelcd plants.
My job responsibilities also involved special studies concerning fluid dynamics, heat transfer, and feasibility evaluations.
I have a Ph.D'. in Mechanical Engineering from Case Western Reserve University (1971), specializing in fluid and heat transfen 1a1 a raember of the /cerican Society of Mechanical Engineers.
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E DW A R D_L.A. N_i. 2-t DIVISION OF OPEPATING REACTOPS U.S. NUCLEAP REGULATCRY COMMISSION f
_P R_O.F E S_S.10_N A L_ _O_U_A L_I F I C AT_I O_N S.
As an Engineering Sys ter s Analyst in the Plant Systems Srancn I an responsible for tecr.nical resiews and evaluations of compor,en,t and system designs and operating characteristics of licensed nuclear power reactors.
I heve a Bachelor of Science degree in Ergineering Physics from the Case Institute of Tecnnology and a Maste-s of Science degree in Pnysics fron Unicn College and a total of 28 years of professional experience, with over 20 years in thc nuclear field.
My experierice includes work on reactor transients and safeguards analysis, nuclear reactor analysis and design, researcn and development on nuclear reactor and reactor control concents and inves tigations of their operational and safety aspects.
I havc held cy present pusition with the Corr.ission since Decerber 1975.
My previous position, which I held for about two and one half years, was Projec t Manager in the Gas Coolcd Reactors Branch, Division of Reactor Licer. sing, U. S. Nuclear Regulatory Commission, where I was responsible for the technical reviev., analysis, ar.d evaluation of the nuclear safety aspects of applications for construction and operation of nuclear power olants.
For about ten years prior to that I was Head of the Nuclear Reactor Section in NASA.
My section was responsible for the develop cnt and verifica tion of nuclear reactor analysis computer programs, conceptual design engineerina, and develoonent engineering contracting.
Prior to my ecoloyment with NASA, I was a nuclear engineer at tne Kr.olls Atomic PC,.er L a bo ra to ry for about six yea rs, where I worke d on the sa feguards and nu: lear design of the 53G reactors and the initial development of the nucicir dcsign of the SEG reactors.
Previous experience includes system engineering and electrical engineering with the General Electric Company ard eitctronic cEvelo pent enginc ; ring wi th thc Victorecn Instrument Co nar.j.
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