ML17037B676

Letter Regarding a 10/01/1976 Letter Indicating Replacement Pages to the Plant Unique Analysis for the Torus Support System and Attached Revised Figures and Pages

ML17037B676
Person / Time
Site:	Nine Mile Point
Issue date:	10/14/1976
From:	Rhode G Niagara Mohawk Power Corp
To:	Lear G Office of Nuclear Reactor Regulation
References
TR-2271(a)
Download: ML17037B676 (12)

Text

DOCKCT NUMBER U.S.NUCLFAR REGULATORY C MISSION NRC FofiM 195 I2-7B)r 0-2 2.0 I'ILE NUMBER'iagara Mohawk Pwr Corp Syracuse, NY G K Rhode Mr Lear DATE OF DOCUMENT 10-14-76 DATE RECEIVED 10-19-76 QNOTORIZED KUNG LASS IF I ED f8fLETTER QfORIGINAL C3copv NUMBER OF COPIES RECEIVED INPUT FORM PROP one signed DESCRIPTION ENCLOSURE Revised pgs to their Report entitled Plant Unique Analysis for the Tourus Support SysteB).......to incorporate changes required by our 9-14-76 ltr......;(40 cys encl recfd)Ltr, re their 10-1-76 ltr....trans the follow PLANT NAME: Nine Mile Pt Ol FOR ACTION/INFORMATION SAFETY 10-2 ASSIGNED AD: BRANCH CHIEF: ASS ONED PROJECT MANAGER: PRO LXC~ASST'~'.Rl BUTION INTERNAL D IST SYSTEMS SAFETY ILE SITE A HEINEI IAN SCHROEDER NRC PDR X&E Z.ENVIRO NA BENAROYA F.OELD'.GOSSICK

&STAFF ENGINEERING MACCARRY IPPOLITO MIPC K RKWOO KNIGHT SIIWEIL PAWLXCKI REACTOR SAFE'IIY CASE'ANAUER OPERATIN ROC 0 S LE ROJEC IIANA EIIEN OPERA N ROSS BOYD~P COLLINS HOUSTON EISEN11 NOVAK ROSZTOCZY SIIAO BAER PETERSON CHECK BUTLER MELTZ HELTEMES RIMES AT&I SKOVHOLT SALTZMAN~MQLLI RUTBE'.RG CONTROL NUMBER EXTERNAL DISTRIBUTION NAT LA13: RL'G~VIE LPDR!w BROOKIIA ULRIKSON ORNL TXC: LA PDR CONSULTANTS ASLB~lLCIT-~4-0.>>4 f*I~."'>g-pz-" g<e"<<~'}>gl;~7)'b" 9')'g (0,,'~4"$~)e~~~~~~~I'g.'r 1 NIAGARA MOHAWK POWER CORPORATION 4>llitlIII NIAGARA~MOHAWK 300 ERIE 8OULEVARO WEST SYRACUSE, N.Y.13202 October 14, 1976 Director of Nuclear Reactor Regulation Attn: Hr.George Lear, Chief Operating Reactors Branch 0'3 U.S.Nuclear Regulatory Commission h'ashington, D.C.20555 Re: Nirie Mile Point Unit 1 Docket.No.

50-220 DPR-63 II yg<g(gb e g4

Dear Hr.Lear:

In our October 1, 1976 letter we indicated that'eplacement pages to" our Plant Unique Analysis for the Torus Support System would be provided to incorporate changes necessitated by your September 14, 1976 letter.Attached are revised Figures 14;15 and Pages 59 and 73.Page 73 has been corrected to incorporate the proper references used in the Plant Unique Anal ysi s.The effect of'ariation on water level has been investigated to ensure that the Torus Support System and attached piping remains within the criteria of the Short Term Program..For a 1.0 psid, t'e maximum allowable downcomer submergence is 4.0 feet.Operation at a downcomer submergence of 4.5 feet could be tolerated if the pressure differential were increased to 1.5 psig.Technical Specifications governing the above will be submitted by November 5, 1976 pursuant to your September 30, 1976 letter.Verification of input parameters has been completed.

The Design Basis Break Area was corrected to 5.446 square f'eet and the Vent Header outside diameter was corrected to 58.5 inches.These changes have a negligible effect on the results of the analysis.Very truly yours, NIAGARA HONAWK WER COR 8 TION oi (r y HGH/sz/At tachment G RALD K.R DE Vice President-E ineering/of 1'-1 r'm 1P N LEDYNE ATERIALS RESEARCH>&I~~I-LaJ UJ.0",', l5 t/)CI~9'i on<0~00~QQ~~TINE (seconds)Fig.14 Anchor Bolt Displacement vs Time I

-pq" I t-LLUY lMe.~MATERwLs REsEARci cngrnn na Or'r 0-2SGQ'a Ognr 7C Onr n 1 QQQQr-12500'1'5000r

-17'iGOr-"GO@'TIME (Seconds)Fig.15 Column Load vs Time.

1 Technical Report TR-227)(a)6.2.4.Ancl>nr Ool ts Each colun!n of the)line Hile Point l.orus is tied to the~concrete floor by two')1/2 inch dia!<eter hoo):-type anchor bolts e!nbedded 40 inches into the concrete.Th<<bolts are n!ade ol'-36 steel;Evaluation of the structural capacity of the anchor bolts to the STP criteria re<)uires the use of t)r<'.1-0!nodel res<<its.Response plots of total anchor bol t del'lection (ir!cludi>>g eff<<..'ts<rl'oncrete) and total column load (including

<!eadweight) are prese!!Led in figures'l4 and 15.Evaluatior!

of the a>>chor I:o)L's acceptabi1 i ty is greatly simplified by examir!ing the col;!mn forces first.1le find that the n!ax-irnum upward colun!n fore is eqllal t<r 255,000 lbs and occurs at.55 sec.Applying this loa<l~l:at&:a>)v Lo th<!four anc>>o<bol ts ar!>d!')rat the anclror bo)ts are w<.ll below yield arrd have experienced only 0.0013 strvin.T)r<l: is well lreluw Ll!>>slrai>>lirnit-ations of tire SlP criteria!'!n.l t)<erefo!<:

.,atisl'ies the re<luire!nents for the bolts themselves.

Fvaluatinr!

of column')oads d!<>>L<r fallback presents no problem since they never reac)r the<<xia)co)!Imrl loa<ls"flown in section 6.2.1;i.e., 1012.2 KfPS for two co]un!ns.

Technical Report TR-2271(a)

~-73-ri TELEDYNE MATERIALS RESEARCH REFERENCES 1."Description of Short Term Program Plant Unjque Torus Support Systems and Attached Piping Analysis," Nutech Peport HK 1-02-12 Rev.2, June 1976.2."Hark I Containment Program Loads for Plant Unique Torus Evaluation," Rev.2, General Electric Co., June, 1976.3,"Mark I Containment Evaluation

-Short Term Final Report, Agdendums 2 and 3" NEDC-20989-P.

4.Torus to Vent Pipe Matrix Data, transmitted to Hr.J.A.Wayward, Teledyne Materials Research, from Hr.K.Wiedner, Bechtel Power Corp., 4 September 1975.5."General Description of a Boiling Water Reactor," General Electric Atomic Equipment Department.

6.Letter from Mr-.M.G.Hosier, Niagara Mohawk Power Corp., to Mr.N.Celia, Teledyne Materials Research, ll June 1976.7.ASME Boiler and Pressure Vessel Code,Section III, Subsections NA and NE, 1974 Edition with addenda through Summer 1975.8."Extrapolated Load-Displacement Curve for 1.5 Inch Diameter Anchor Bolts," transmitted to Mr.R.H.Buchholz, General'Electric Co,, from-Mr: R.W.Wulf, Jersey Centra'l Power 5 Light Co., with copy to Hr.R.Smart, Northeast Utilities Service Co., 17 May 1976.9.Pathway Bellows Inc., Dwg.g-2892 Rev.D, 90" Dia.Tandem Weld End Assembly 10."Hark I Containment Evaluation--Short Term Program," NEDC-20989-P, General Electric Co.

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