ML19224D413
| ML19224D413 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/07/1979 |
| From: | James Shea Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-05-12.A, TASK-RR NUDOCS 7907120091 | |
| Download: ML19224D413 (24) | |
Text
{{#Wiki_filter:. o UNITED STATES E' 'g NUCLE AR REGULATORY COMMISSION g E w ASHINGTON. O C.10MS %, *.. + p# June 7,1979 Docket No. 50-245 LICENSEE: Northeast Nuclear Energy Company (NNECo) FACILITY: Millstone Nuclear Power Station Unit No.1 SUBJECl: Surrmary of Meeting Held on May 17-18, 1979 Representatives of the Nuclear Regulatory Commission, Northeast Nuclear Energy Company, and the SEP Utility Owner's Group met at the Millstone Nuclear Power Station on May 17-18, 1979. is a list of the meeting attendees. The purpose of the meeting was to review the progress to date on the Systematic Evaluation Program (SEP) Topic III-5. A, " Effects of Pipe Break on Structures, Systems and Components Inside Containment". NRC representatives briefly reviewed the scope of the high energy line break criteria and sunmarized the progress of the Oyster Creek review as requested by the licensee. NNECo representatives distributed an outline of their presentation (Attachment
- 2) and stated their belief that their effort so far is in phase with the NRC schedule which calls for NNECo to complete the interaction study using single failure by November 1979.
NNECo stated that they will use a combination of all three approaches outlined in NRC letter to NNECo dated January 11, 1979. With the aid of containment piping drawings, high energy piping systems inside containment were identified. INECo noted that the recirculation loop is already protected from high energy pipe break effects as stated in Amendment 14 to the FSAR. Since the facility was shutdown or Reload No. 6, the NRC representatives entered containment to look at so,ae of the important high energy piping. NRC representatives expressed doubt that the Millstone 1 High Energy Pipe Break interaction study by NNECo will be completed satisfactorily by November 1979. NNECo suggested another meeting in Bethesda, Maryland, in August 1979 to review their progress (including identification of pipe breaks, consequences, S p 325 30'.; t 9 07 3 20cv.7,
, and corrective measures for selected breaks) to provide added assurance that the NNECo effort involting interaction studies and a report will be completed by November 1979. In summary, it was agreed that at the August 1979 meeting NNECo will identify all of the breaks, evaluate the break consequences, and present a schedule for completion of the task. NRC representatives cgreed t; provide a draf t copy of the NRC-SEP review of the ""'fe Shutdcen Systems for - d411 stone Nuclear Power Plant Unit 1", by ':oy 27,1979. The next schedui.:d ueeting on the SEP High Energy Line Break will be in August 1979. gtw24 ~ 16 - J ames J. h a, Project Manager perating actors Branch #2 x ivision of Operating Reactors Attachments: 1. List of Attendees 2. Outline of Presentation cc w/ attachments: See next page )L"
ATTACHMENT 1 LIST OF ATTENDEES MAY 17-18,1979 Northeast Nuclear Energy Company K. Thomas P. Przokop J. Nowell NUSCO
- 9. Ilbennan L. Nadeau W. Koste T. Dente R. McGuinnees D. Vail R. Artwell EG&G D. Morton R. Guenzler Woodward Clyde J. Stevenson K M C, Inc.
J. McEwen NRC J. Shea R. Kiessel K. Jabbour P. Diti?nedetto D. Allison ACRS H. Walker c e -, 0 o, 32r3 3
ATTACHMENT 2 AGEriDA MILLSTONE UNIT NO. 1 NRC MEETING HEPB IllSIDE C0r4TAINMENT IMY 18,1979 e INTRODUCTION / BACKGROUND e EVALUATION PROGRAM AND CRITERIA e IDENTIFICATION OF SAFE SHUTDOWN SYSTEMS / METHODS e IDENTIFICATION OF HIGH Ef4ERGY LIr4ES e PIPING LAYOUTS 325 309
IDENTIFICATION OF ll.E. SYSTEMS SHUTDOWN METHODS POSTULATED RUPTURES EFFECTS OF RUP'URES CHANGES TO EQUIPMEis'T AND PROCEDURES 325 310
TERMINAL ENDS WELDED JOINTS (TEES, ELBOWS, ETC.) PIPE FITTINGS (FLANGES, ETC.) 325 31'-
CRITERIA HIGH ENERGY SYSTEMS PIPE WHIP PROTECTION TYPES OF BREAKS PIPE RUPTURE ORIENTATION 325 3'2
ISOLATION CONDENSER ONLY IF THE INVENTORY OF WATER IN THE VESSEL IS MAINTAINED, ASSURANCE OF FUEL INTEGRITY IS MAINTAlfiED. THEREFORE, WITH THE REACTOR SCRAM USED AND THE VESStL ISOLATED, USE OF THE ISOLATION CONDENSER RETAINS THE INVENTORY OF WATER BY CONDENSING THE STEAM AND RETURNING THE CONDENSATE TO THE VESSEL WITH NO LOSSES. TEMPERATURES CAN BE REDUCED TO AND MAINTAINED AT APPROXIMATELY 2000F FOR THE DURATION Or DECAY HEAT PRODUCTION. }2[j bs
NORMAL SHUTDOWN (STEAM DUMP TO FIAIN CONDENSER) WITH THE REACTOR SCRAMMED OUT AND NOT ISOLATED, A SAFE SHUTDOWN MAY PROCEED BY USlur-THE MAIN CONDENSER AS A HEAT SINK Fod PRESSURE REDUCTION AND CONTROL, WITH THE CONDENSATE /FEEDWATER SYSTEMS SUPPLYING MAKEUP WATER TO THE VESSEL FOR LEVEL CONTROL. )}(y !) \\.
AUTO PRESSURE RELIEF (APR) AND ' CONTROL R0D DRIVE (CRD) SYSTEM WITH THE REACTOR dCR/,MMED AND THE VESSC'. !E0 LATED, A SAFE SHUTDOWN MAY BE MADE BY USING ONE (1) AUTO PRESSURE RELIEF VALVE FOR PRESSURE REDUCTION AND CONTROL, WITH THE CONTROL ROD DRIVE SYSTEM SUPPLYING V!ATER TO THE VESSEL FOR LEVEL CONTROL. IHE CONTROL ROD DRIVE PUMPS (2) CAN SUPPLY MORE THAN 200 GPM AT 1200 PSIG FOR THIS SHUTDOWN METHOD. } ^f 5 3 i I)
EMERGENCY CORE COOLING SYSTEM (APR & CORE 3 PRAY /LPCI) !!ITH THE REACTOR SCRAMMED AND THE VESSEL ISOLATED, A E,AFE SHUTDOWN MAY PROCIED, WITH ONE (1) CORE SPRAY OR LPCI (LOW PRESSURE COOLANT INJECTION) PUMP FOR MAKEUP WATER TO THE VESSEL FOR LEVEL CONTROL, )'j) b\\N
A. FEEDWATER SYSTEM B. MAIN STEAM SYSTEM r. CONTROL ROD DRIVE flYDRAULIC SYSTEM D. REACTOR RECIRCULATING SYSTEN E. PRfMARY CONTAINf1ENT COOLING (LPCI) SYSTEM F. SHUTDOWN COOLING SYSTEN G. ISOLATION CONDENSER SYSTEM H. REACTUR CLEANUP SYSTEf1 I. CORE SPRAY SYSTEf1 325 la
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liEETING
SUMMARY
DISTRIBUTIJN Docket NRC PDR Local PDR ORB #2 Reading NRF Reading H. R. Denton E. S. Case V. Stello R. Vollmer W. Russell B. Grimes T. J. Carter D. Eisenhut A. Schwencer D. Ziemann P. Check G. Lainas D. Davis T. Ippolito R. Reid V. Noonan G. Knighton Project Manage > - J. Shea OELD OI&E (3) H. Smith R. Fraley, ACRS (16) NRC Participants Buchanan TERA h. Walker, ACRS ,, (. ,9 Cl '~ .,}}