ML20127K680
| ML20127K680 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/17/1972 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Dienhart A NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9211200470 | |
| Download: ML20127K680 (3) | |
Text
{{#Wiki_filter:_. - ~ -, ~n-m:.. w .;7,y;. ; _ -- - - ~ r c- .g t.,. -;:.4 y'4' -6 4 s _y ,4 ....a s v ,z. -~ ; ( 3 .A _;t .., +... , y. 9 v_ t s, N 4 ( @e s 3 ha- ,o - y y Deeket No. 30-263 l' i. Northern States Power Company ATTH: Mr. Arthur V. Dienhart Vice President of gagineering 414 Nicollet Mall Minneapolis,Itinnesota 55401 f Gentlemen Prwisional Operating License No. DPR-22 for the Monticello Nuclear Plant will expire on July 19, 1972. This letter is to provide you with guidance in preparing your application for a full-term operating license and thereby expedite our review of it. 1. The application should provide detailed consideraties of the f acility operating history, including confirmation of design bases and objectives and discussion of any significant plant problems that may have occurred and the remedial actione taken. In addition, it should support the adequacy of the performance and congatence of the licensee's organization during the Provisional Operating License period, including onsite staff, technical support groups, advisory cosmittees and management. Further, it should discuss signiffeant changes that have been made to the facility since the Final Safety Analysis Report was prepared, however, extensive detail is generally not required regarding design and analysis of changes that already have been submitted to the Cossaission for approval. The status of comments and recomment'ations contained in past letters of the Advisory Consmittee on Reactor gafeguards concerning Monticello should be discussed i in your application. 2. The apN.ieation specifically should include an analysis of i the iollowias in relation to operating experience to data: 2.1 High 7tessure Coolant Injection (HPCI) reliability; 2.2 Steam flow measurements; b 2.3 Steam line flow restrictors; i M i 9211200470 720417 PDR ADOCK 05000263 P PDR 4 ...w. . - - -. +, .,.,., ~.
r s ..a APR 171972; yythern states Power Company ed ,e_ ~ h l-2.4 Main steam lime isolation valve reset switch 2.5 The affects of terms haffles resoval on blowdown characteristics; and 2.6 Reactiv!.ty measurements compared with predictions. 3. The application should include the results and conclusions of analyses or the status of investigations concerning; 3.1 The AEC Interim Acceptance Criteria for Emergency Core Cooling Syatems (ECCS); 3.2 liydrogen control after Loss-of-Coolant Accident (Reference Safety Guide No. 7); 3.3 Instrument linea penetrating the primary reactor con-tainment that do not have orifices to restrict flow in case of rupture and excess flow check valves that do not have indicators - (Reference Safety Guide No.11); 3.4 Performance of the radweste processing systems with respect to maintaining effluent releases as low as practicable, 3.5 Anticipated Transients without Scram (ATWS), including consideration of pump trip on high pressure signal; 3.6 Main staan isolation valve leakage tests and adequacy of valve performance; 3.7 Consequences of water contamination by structural materials and coatings in a Loss-of-Coolant Accident; 3.8 Rod drop accident consequences and rod worth minimizar reliability; 3.9 Reactor vibration testa conducted at Monticello and similar plants; and 3.10 Detection of leaks from the primary coolant system pressure boundary. d \\
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i 4. The application should include descripties of yours } 4.1 36ergemey Plas; f 4.2 Quality assurance progree; and 4.3 Industrial security program (Raforeece Safety Guide No. 17). Although you may have. dealt with some aspects of the above items in previous submittals, our review can be performed more expeditiously if your application for a full-tern license is complete and references to other documents are minimized. If we can be of further assistance, please contact Messrs. James J. Shea or Dennis L. Ziemann. Sincerely, w\\ Donald J. Skovbolt Assistant Director for Reactor Operations Division of laactor Licensing ec: Gerald Charnoff Distribution Shaw, Pittman, Potts, Trowbridge & Madden WDooly, DR 910 - 17th St-eat, N. W. "" g P ^; CO @) i Washington, D. C. 20006 HShapar, 000 JRBuchanan, ORNL PDR CLong, DRL Local PDR RVo11mer, DRL M cket File DLZiemann, DRL DRL Reading JJShea, DRL Branch Reading RMDiggs, DRL ACRS (16) KJGallo, OGC FSchroeder, DRL DJSkovholt, DRL TJCarter, DRL RTedesco, DRL RSliger, DRL i DRL DRL D_ __0GC omca > 3 ,,,,,._ D,R,L,,_ l SURNAME >.JJS,ea:sjh DLZiemann_,, ..J)JS w.lt. DATE > ...hllhI.71. ..kI!. [.2d..... l.71 -4/ p/72_ 'orna AIC-St8 (Rev. 9-53) AICM 0240
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