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{{#Wiki_filter:NRC FoRM 195 U S NUCLEAR REGULATORY COI iSION I,.6)..A AAIRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL DOCKET NUMBER 50>>220 FILE NUMBER TO: Mr.George Lear FROM: Niagara Mohawk Power Corp.Syracuse, New York R.R.Schneider DATE OF DOCUMENT 12/1/76 DATE RECEIVED 12876@LETTER QOR I G INAI OCOPV DESCRIPTION QNOTORI2ED IRfUNC LASSIF I E D PROP INPUT FORM ENCI.OSURE NUMBER OF COPIES RECEIVED One signed Ltr.w/attached....re their ll/3/76 ltr....concerning"Plant Unique Analysis Report for Torus~Support System and Attached Piping for Nine Mile Point Nuclear Station.ACED@EDGED (2-P)PLANT NAME: Nine Hile Point Unit No.1 SAFETY ASSXGNED AD!H&iX L~CASST Lear Nowicki Parrish FOR ACTION/INFORMATION PROJECT MANAGER LIC ASST 129 6 RJL INTERNAL DISTR I BUTION NRC PDR X&E OELD GOSSICK&STAFF MIPC CASE HANAUER~HARLESS PROJECT MANAGEMENT BOYD PE COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR~Oswe o N.Y.T IC!NSIC!hSLB!SYSTEMS SAFETY HEINEMAN SCHROEDER ENGINEERING HACARRY KNIGHT SIHWEIL PA ICK REACTOR SAFE ROSS NOVAK ROSZTOCZY C11ECK AT&I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NAT LAS REG V IE LA PDR CONSULTANTS:
{{#Wiki_filter:U S NUCLEAR REGULATORY COI   iSION DOCKET NUMBER NRC FoRM 195 I,.6) ..                                                             A                                 50>>220 FILE NUMBER AAIRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL TO:                                               FROM:                                     DATE OF DOCUMENT Niagara Mohawk Power Corp.                         12/1/76 Mr. George Lear                              Syracuse, New York                       DATE RECEIVED R. R. Schneider                                   12876 QNOTORI2ED                PROP                    INPUT FORM        NUMBER OF COPIES RECEIVED
PLANT SYSTEMS TEDES 0 0 A IPPOL TO OPERATING REACTORS STELLO OPERATING TECH EISENHUT BUTLE.S B 0 ULR KSON OR STESA E 0 ERNST BALLARD SPANGLER SXTE TECH GAMHILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J~COLLINS KREGER CONTROL NUMBER/A gD~ACRS CYS~e&9%86/E T NRC FORM 196 (2.76)
@LETTER QOR I G INAI         IRfUNC LASSIF I E D                                                           One  signed OCOPV DESCRIPTION                                                      ENCI.OSURE Ltr. w/attached....re their ll/3/76 ltr....
concerning "Plant Unique Analysis Report for Torus~Support System and Attached Piping ACED@ EDGED for Nine Mile Point Nuclear Station.
(2-P)
PLANT NAME:
Nine   Hile Point Unit     No. 1 SAFETY                                   FOR ACTION/INFORMATION                    129    6          RJL ASSXGNED AD!
H&iX                             Lear Nowicki                      PROJECT MANAGER L~CASST                                 Parrish                     LIC ASST INTERNAL DISTR   I BUTION SYSTEMS SAFETY                PLANT SYSTEMS              STESA NRC PDR                               HEINEMAN                      TEDES 0 X&E                                   SCHROEDER                              0 A OELD GOSSICK & STAFF                       ENGINEERING                    IPPOL TO                  E      0 MIPC                                 HACARRY                                                  ERNST CASE                                 KNIGHT                                                    BALLARD HANAUER     ~
SIHWEIL                        OPERATING REACTORS        SPANGLER HARLESS                               PA    ICK                      STELLO SXTE TECH PROJECT MANAGEMENT                   REACTOR SAFE                    OPERATING TECH            GAMHILL BOYD                                 ROSS                          EISENHUT                  STEPP PE COLLINS                           NOVAK                                                    HULMAN HOUSTON                               ROSZTOCZY PETERSON                             C11ECK                        BUTLE                      SITE ANALYSIS MELTZ                                                                       .S                  VOLLMER HELTEMES                             AT &    I                                                BUNCH SKOVHOLT                             SALTZMAN                                                  J ~ COLLINS RUTBERG                                                  KREGER EXTERNAL DISTRIBUTION                                            CONTROL NUMBER LPDR ~ Oswe o   N. Y.           NAT LAS                          B 0 T IC!                             REG V IE                          ULR KSON      OR NSIC!
hSLB!
LA PDR CONSULTANTS:
                                                                                                      /A gD~
ACRS       CYS ~e&9%86/     E T NRC FORM 196 (2.76)
 
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  .".V.'OMTF. "'<<".K('j gg
"'<<".K('j gg C NIAGAR MOHAWK POWER CORPORATION ee'0 S'0$jg6/NIAGARA~MOHAWK 300 ERIE 80UI.EVARO WEST SYRACUSE, N.Y.I3202 December 1, 1976 Gp Director of Nuclear Reactor Regulation Attn: Mr.George Lear, Chief Operating Reactors Branch&#xb9;3 U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63  
 
C NIAGAR MOHAWK POWER CORPORATION NIAGARA 300
                                      ~       MOHAWK ERIE 80UI.EVARO WEST SYRACUSE, N.Y. I3202 ee December     1, 1976
    '0 S'0$  jg6        /
Gp Director of Nuclear Reactor Regulation Attn: Mr. George Lear, Chief Operating Reactors Branch &#xb9;3 U. S. Nuclear Regulatory Commission Washington, D. C.         20555 Re:   Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
 
==Dear Mr. Lear:==
 
My  letter of  November 3, 1976 transmi        tted additional information regarding the "Plant Unique Analysis Report for Torus Support System and Attached Piping for Nine Mile Point Nuclear Station." The heading for Question 3, Table C, should be corrected to read as follows: "...BP = 1.5 psi..."
Attached is'a revised Table C.
Very      truly yours, NIAGARA MOHAWK POWER CORPORATION R. R. SCHNEIDER Vice President-Electric Production MGM/sz Attachment
 
L TABLE      C SUtltlARY OF MALYSIS RESULTS BASE CASE LOAD hP            =~l~n')
t<AXIHUtl  DOWN LOADS For 4'-6"        Submer ence Component                            ~a Load/Stress                Strength 4J cU      5 Ratio Evaluation                CR 0 CL Cl c( O  E/l '~
Ca 1 cul.a ted    Capacity          Act. Al 1 ow,.
Ring Girder Stress,      psi tteoIbrane + Bending                                    34,800          81,600            ,43        ,50
                            'hear 9,170        40,800            .23        .50 Torus Shel.l Stress,      psi 21,700          64,000            .33        .50 tlembrane + Bending                        X X        ,  15,600          40,800          .38        .50 Shear Column-Torus Meld      Joint, Inner Column
    .
Web  Weld (kips)                                                        678.0        .75        1.0 Flange Meld (in.-kips)                                                2,213.0        .05      ~
1.0 65;5          7OO.O,      :10        1.0 Outer Column
        'lfeb Meld  (kips)                                                                  .87        1.0 Flange  Meld'(in.-kips)                                            z,NI:8                      1.0 158.7          700. 0                  1.0 Column      Buckling Inner Column Fquation 19                          X                N/A              H/A        .40        0.5
      . Equation 20                          H/A                H/A              t(/A  ~
t(/A        N/A Outer Column Equatidn 19                          X                H/A              H/A        .38        0.5 Equation 20                          /A                i'(/A            t(/A      N/A          N/A Column Base        Joint Inner Column Down Load (k1ps)                                        508.2          1602.0      .31          .50 Up Load (kips)                                          124.7*          461 45    .27          .50 Outer Column Down Load (kips)                                        595,1          1602.0    -
                                                                                            .37          .50 Up Load '(kips)                                          111- 3*        .461.45    .24          .50
*Conservatively computed by multiplying values in original Plant Unique Ana1ys i s Tab I e 9 by Hap, 01d


==Dear Mr.Lear:==
        ~
My letter of November 3, 1976 transmi tted additional information regarding the"Plant Unique Analysis Report for Torus Support System and Attached Piping for Nine Mile Point Nuclear Station." The heading for Question 3, Table C, should be corrected to read as follows: "...BP=1.5 psi..." Attached is'a revised Table C.Very truly yours, NIAGARA MOHAWK POWER CORPORATION R.R.SCHNEIDER Vice President-Electric Production MGM/sz At tachment L
0
TABLE C SUtltlARY OF MALYSIS RESULTS BASE CASE LOAD hP=~l~n')t<AXIHUtl DOWN LOADS For 4'-6" Submer ence Component Evaluation 4J cU CR 0 c(O~a 5 CL Cl E/l'~Load/Stress Strength Ratio Ca 1 cul.a ted Al 1 ow,.Capacity Act.Ring Girder Stress, psi tteoIbrane
      ~
+Bending'hear Torus Shel.l Stress, psi tlembrane+Bending Shear X X 34,800 9,170 21,700 , 15,600 81,600 40,800 64,000 40,800 ,43.23.33.38 ,50.50.50.50 Column-Torus Meld Joint, Inner Column.Web Weld (kips)Flange Meld (in.-kips)
4 a K.~}}
Outer Column'lfeb Meld (kips)Flange Meld'(in.-kips)
Column Buckling Inner Column Fquation 19.Equation 20 Outer Column X H/A 65;5 158.7 N/A H/A z,NI:8 700.0.87 H/A.40 t(/A~t(/A 678.0.75 2,213.0.05 7OO.O,:10 1.0~1.0 1.0 1.0 1.0 1.0 0.5 N/A Equatidn 19 Equation 20 X/A H/A i'(/A H/A t(/A.38 N/A 0.5 N/A Column Base Joint Inner Column Down Load (k1ps)Up Load (kips)Outer Column Down Load (kips)Up Load'(kips)508.2 124.7*595,1 111-3*1602.0.31 461 45.27 1602.0-.37.461.45.24.50.50.50.50*Conservatively computed by multiplying values in original Plant Unique Ana1ys i s Tab I e 9 by Hap, 01d 4 0~~a K.~}}

Revision as of 08:22, 30 October 2019

Letter Regarding a Correction to the Heading for Question 3, Table C in Plant Unique Analysis Report for Torus Support System and Attached Piping for Nine Mile Point Nuclear Station.
ML17037B664
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/01/1976
From: Schneider R
Niagara Mohawk Power Corp
To: Lear G
Office of Nuclear Reactor Regulation
References
Download: ML17037B664 (6)


Text

U S NUCLEAR REGULATORY COI iSION DOCKET NUMBER NRC FoRM 195 I,.6) .. A 50>>220 FILE NUMBER AAIRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Niagara Mohawk Power Corp. 12/1/76 Mr. George Lear Syracuse, New York DATE RECEIVED R. R. Schneider 12876 QNOTORI2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED

@LETTER QOR I G INAI IRfUNC LASSIF I E D One signed OCOPV DESCRIPTION ENCI.OSURE Ltr. w/attached....re their ll/3/76 ltr....

concerning "Plant Unique Analysis Report for Torus~Support System and Attached Piping ACED@ EDGED for Nine Mile Point Nuclear Station.

(2-P)

PLANT NAME:

Nine Hile Point Unit No. 1 SAFETY FOR ACTION/INFORMATION 129 6 RJL ASSXGNED AD!

H&iX Lear Nowicki PROJECT MANAGER L~CASST Parrish LIC ASST INTERNAL DISTR I BUTION SYSTEMS SAFETY PLANT SYSTEMS STESA NRC PDR HEINEMAN TEDES 0 X&E SCHROEDER 0 A OELD GOSSICK & STAFF ENGINEERING IPPOL TO E 0 MIPC HACARRY ERNST CASE KNIGHT BALLARD HANAUER ~

SIHWEIL OPERATING REACTORS SPANGLER HARLESS PA ICK STELLO SXTE TECH PROJECT MANAGEMENT REACTOR SAFE OPERATING TECH GAMHILL BOYD ROSS EISENHUT STEPP PE COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON C11ECK BUTLE SITE ANALYSIS MELTZ .S VOLLMER HELTEMES AT & I BUNCH SKOVHOLT SALTZMAN J ~ COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR ~ Oswe o N. Y. NAT LAS B 0 T IC! REG V IE ULR KSON OR NSIC!

hSLB!

LA PDR CONSULTANTS:

/A gD~

ACRS CYS ~e&9%86/ E T NRC FORM 196 (2.76)

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.".V.'OMTF. "'<<".K('j gg

C NIAGAR MOHAWK POWER CORPORATION NIAGARA 300

~ MOHAWK ERIE 80UI.EVARO WEST SYRACUSE, N.Y. I3202 ee December 1, 1976

'0 S'0$ jg6 /

Gp Director of Nuclear Reactor Regulation Attn: Mr. George Lear, Chief Operating Reactors Branch ¹3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Lear:

My letter of November 3, 1976 transmi tted additional information regarding the "Plant Unique Analysis Report for Torus Support System and Attached Piping for Nine Mile Point Nuclear Station." The heading for Question 3, Table C, should be corrected to read as follows: "...BP = 1.5 psi..."

Attached is'a revised Table C.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION R. R. SCHNEIDER Vice President-Electric Production MGM/sz Attachment

L TABLE C SUtltlARY OF MALYSIS RESULTS BASE CASE LOAD hP =~l~n')

t<AXIHUtl DOWN LOADS For 4'-6" Submer ence Component ~a Load/Stress Strength 4J cU 5 Ratio Evaluation CR 0 CL Cl c( O E/l '~

Ca 1 cul.a ted Capacity Act. Al 1 ow,.

Ring Girder Stress, psi tteoIbrane + Bending 34,800 81,600 ,43 ,50

'hear 9,170 40,800 .23 .50 Torus Shel.l Stress, psi 21,700 64,000 .33 .50 tlembrane + Bending X X , 15,600 40,800 .38 .50 Shear Column-Torus Meld Joint, Inner Column

.

Web Weld (kips) 678.0 .75 1.0 Flange Meld (in.-kips) 2,213.0 .05 ~

1.0 65;5 7OO.O, :10 1.0 Outer Column

'lfeb Meld (kips) .87 1.0 Flange Meld'(in.-kips) z,NI:8 1.0 158.7 700. 0 1.0 Column Buckling Inner Column Fquation 19 X N/A H/A .40 0.5

. Equation 20 H/A H/A t(/A ~

t(/A N/A Outer Column Equatidn 19 X H/A H/A .38 0.5 Equation 20 /A i'(/A t(/A N/A N/A Column Base Joint Inner Column Down Load (k1ps) 508.2 1602.0 .31 .50 Up Load (kips) 124.7* 461 45 .27 .50 Outer Column Down Load (kips) 595,1 1602.0 -

.37 .50 Up Load '(kips) 111- 3* .461.45 .24 .50

  • Conservatively computed by multiplying values in original Plant Unique Ana1ys i s Tab I e 9 by Hap, 01d

~

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