ML17037B964

Nine Mile Point Generating Station, Units 1 and 2 - Request for Additional Information Related to the Design of the Containment of the Facility

ML17037B964
Person / Time
Site:	Nine Mile Point
Issue date:	04/21/1975
From:	Stolz J F Office of Nuclear Reactor Regulation
To:	Rhode G R Niagara Mohawk Power Corp
References
Download: ML17037B964 (8)

Text

9 Rocket 1lo, 50-410 APR 21 1975 k'iagara)Johann power Corporation AY'XV: Nr.Cerald Ti.Bho@e Vice President-Enpineerinp 3QO Erie boulevard Uest Syracuse', Petr York)3202 CentletEen:

Pursuant to 5 50.54(f)of 10 CP" Part 50, tho l'IuClear Regulatory Cormiasien (DEC)staff requires that, certain infozr ation related to the'esign of the containment for your facility'e submitted promptly to L,BC for its reviev..%isis requireE1ent results fgoa recent developr;ents associated with our on-going revieu area of Er,R plants with pressure supp'ression-typo contains.ento and the capability of the suppression pool retaininp structures to tolerate loads due to'operation of th~primary system pressure relief valves.Experience at several operating; Eblis planta has indicated that loads due to relief valve act1$ation ray not have been fully considered in the structural desi~a of the suppression chaw'ber.Xn addition, the Ceneral Electric Company is no19 Pr'eparing to start a series of srM111-scale relief valve tests ckich vill be used to verify analytical predictions of these loads aa applicable to al$classes of plants.Pool dynaoic loads du~to relief valve-operation are due to two distinct phenomena.

Pizat$pressure T1aves are generated within the suppression pool';hen, on first opening,$r@11+f valves discharge high pressure air fol1owed by el*eau into the pool eater.Those are, referred to as stear1 vent clearing loads."econ4$st,eaT3 quenching vibrations can accor pany e-tend d relief valve diacharpe into the pool if the water is at an elevated temperature.

The, enclosure specifies the infortation pertaining to these effects, T'hich ce vill require tt3 ceaplete our review of your,design vith regard to these phenomena.

Youp response to this request for information should be filed within ninety days, of'he date of receipt of this letter.Xf you cannot r1eet gg Ut1s schedule 9 please Bdv1se ua Qlthln f1fteen days., OFFICE%SURNAMEI$DATE+Form AEC-318 (Rev.9-53)AECM 02+*II.d.OOVddNNCNT JAINTINO OFTICd)1929~99,2$

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8 C~~H 0 Niagara Nohawk Power Corporation Please contact us if you desire additional discus'sion or clarification of the information requested.

Sincerely, Original Signed bg D.e.Id,4 cog John P.Stolz, Chief Light Water Reactors Branch 2-1 Division of Reactor Licensing

Enclosure:

'equest for Additional Information This request for Generic Information was approved by GAO under a blanket Clearance No.B-180225 (R0072);this clearance expires July 31, 1977.cc: LeBoeuf, Iamb, Leiby&HacRae ATTN: Hr.Arvi'n E.Upton, Esq.1737 N Street, N.W.Washington D.C.20036 J.Bruce HacDonald, Esq., Deputy Commissioner and Counsel New Yoik State Department of Commerce 99 Washington Avenue Albany, New York 12210 Carmine J.Clemente, Esq.New York State Atomic Energy'ouncil

" Department of Commerce 99 Washington Avenue Albany, New York 12210 Anthony Z.Roisman, Esq.'erlin, Roisman and Kessler 1712 N Street, N.IU.Washington, D.C.20036 t bcc: E Hiss Suzanne Weber ,78 West Senaca Street Oswego, New York 13126 Hr.Richard Goldsmith Syracuse University College of Law E.I.IUhite Hall, Campus Syracuse, New York 13210 J.R.Buchanan, ORNL Thomas B.A bernathy, DTIE DISTRIBUTION:

NRC PDR Local PDR Branch File Docket File R.Klecker F.IUilliams F.Schroeder V.Moore A.Kenneke R.DeYoung ELD IE (3)IU.kane H.Smith ACRS (14)TR Branches LIUR 2 BC's J.Norris L'L UR-1 Ir OFF ICED SURI4AMEQ bATEQ 4$ILU Form AEC-318 (Rev.9-53)AECM 0240 L: LIUR 2-1 J 44ZJ7S*V,S, COVCRNIICN2 PRIN2INO OPFICCI I52$~55~555 0 Q i)I, 8~.'-~lj;gi'~g H r""~w J 1/n' 0'RE UEST FOR ADDITIO lcK Li"OP~~fATIOal RELIEF VALVE LOwJ)S 1.Specify the number of safety relief valves, their design flow rate, and discharge line size.Provide a listing of operating conditions under which these:valves would be operated either manually or auto-matically.

Describe, with the aid discharge line to, and orientation of drawings, the routing o f the in, the suopression pool, and the design of the discharge line exit.2.Provide the load specification for the suppression cha ber structure to accommodate adtuation of one or more safety relief valves.I 3.Provide the design load capability for the suppression chamber structure.

4.Provide justification for the load specification given in (2)above by the use of appropriate experi-ental data and analysis.If the General Electric (GE)Company is responsible for specifying these loads, a statement to that effect is sufficient.'.

Identify, with the aid of drawings, any components or structures in the suppression pool region, other than the bounding walls of the suppression chamber, and the location of such components relative to the relief valve discharge line exits.Discuss the structural capability of these components to accommodate loads due to relief valve actuation.

6.Estimate the maximum number of single and multiple relief valve openings over the life of your plant.

~/+4 0-2-7.identify the maximum temperature limits of the suppression pool with the reactor at power.This temperature limit should include I provisions for the testing requirements of relief valves./8.Specify the operator actions that are planned when specified temperature limits are exceeded.9.Present the temperature transient of the suppression pool starting from the specified limits in (1)for the following transients: (a)main steam line isolation;(b)'emi-automtic blowdown;.

and, (c)stuck open relief valve..For purposes of this analysis, the minimum water level should be assumed in the suppression pool.10.The temperature instrumentation that will be installed in the pool and the sampling or averaging technique that will be applied to arrive at a definitive pool temperature.

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