ML20198E674

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Submits Listed Tasks Developed by Mechanical Engineering Branch to Respond to 850723 Operating Reactor Events Briefing Re Inadequate Capacity of Main Steam Safety Valves at Facility
ML20198E674
Person / Time
Site: Seabrook, 05000000
Issue date: 05/08/1986
From: Bosnak R
NRC
To: Crutchfield D
NRC
Shared Package
ML20151L176 List:
References
FOIA-86-266 NUDOCS 8605280171
Download: ML20198E674 (17)
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{{#Wiki_filter:. _. MEMORANDUM FOR: Dennis Crutchfield, Assistant Director for Safety Assessment Division of Licensing FROM: Robert J. Bosnak, Acting Assistant Director for Components and Structures Engineering Division of Engineering hy ? 3 I%~CPMM'M lLwTat:, SvGtm 8es tm n.:- epto tw

SUBJECT:

-INADEQUATE' MAIN STEAM SAFETY VALVE CAPACITY AT SEABROOK At the Operating Reactor Events briefing on the subject issue on July 23, 1985. DE was asked to investigate the adequacy of testing of PWR main steam safety valves (MSSVs) and the validity of extrapolating test data from small valves to larger full size MSSVs. The Mechanical Engineering Branch (MEB) has i planned the following tasks which we think adequately respond to this request: E (1) MEB has prepared a proposed Ih Information Notice to advise the industry of the MSSV capacity problem as it relates to proper ring settings. The proposed Notice was transmitted to DL with our August 9,1985 memorandum from R. Bosnak to D. Crutchfield. (2) MEB will fonnally request DST to prioritize a potential generic issue dealing with MSSV operability problems including that of inadequate flow capacity. The procedure outlined in Office Letter No. 40 will be fol1 owed.. 3 MEBwilldiscusswiththeASMESectionIIISubgf. ass 2safetyvalv (3) up on Pressure Relief possible changes to the ASME Section III Code C certification requirements. Currently Cl.2 safety valves can be capacity, certified based on tests perfonned on prototypical valves much smaller in size and at much lower pressures than are applicable for PWR, Main Steam Safety Valves. The ring adjustment problem encountered with the Seabrook MSSVs raises one of the same questions that arose during the recent EPRI testing of ASME Section IrI C1.1 pressurizer safety valves. That is, do the valve manufacturers have an adequate understanding of how to extrapolate ring adjustments, that affect lift and blowdown, from very small test valves to the veiy large safety valves used on PWR plants? hp2 1 860508 NURPHY86-266 PDR

Dennis Crutchfield. /'Recently changes to the Code safety valve certification procedure, proposed by ( MEB, to address this concern for Cl. I safety valves were accepted by ASME for i incorporation into the Code. The change will require that new C1. I safety __ ___ valve designs be prototypical tested in sizes and at pressures, temperatures, / and flow rates that envelope those that the valve design will be used for in service. ,I li MEB will explore with the Code Committee the. feasibility / desirability of making similar changes to the Code C1.1 'saf valve certification i requirements. '~ / s We believe these actions should adequately resolve the problem of inadequate MSSV capacity. Robert J. Bosnak, Acting Assistant Director l for Components and Structures Engineering i Division of Engineering' l cc: J. Knight F. Cherny B. Sheron 3 G. Holahan D. Tarnoff 4 = ik 64. / 15 pv ub 'A* * ( 3). ' TL l, a, ,i

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Document Name: INADEQUATE MAIN STEAM MEMO Requestor's ID: DEMEB01 Author's Name: GHanner Document Connents: Inadequate Main Steam Safety Valve Capacity at Seabrook O e i 6 S e A

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6 y What actions are being taken (if any) or should b'e taken on operaNng 6. plants to correct the suggested deficiency?these actions being take By whom c*- o. W *~Q. f J* -*~,--4) akt individual -t.h p ic' iYu'%gl'iHI^ hcTio'7 tan ~ W /x-f 4 p W w m If th'e issue l'sieidteYtYadIfd[g'en ii,ki.g. N* ' 7. n Item) identify the, generic issue and the area of issue overlap. t..',s cL-a.s-. m y,~: o t u a c + 2 ~ v*.p.e ~ C /.i.br.%&n

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11. The concurrence of tha respon,sible organization, if possible.

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