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=Text=
=Text=
{{#Wiki_filter:Nl]C I oRM 196{2 70)TO: Mr.Jame P.O'.Reilly.
{{#Wiki_filter:Nl]C I oRM 196                                     ,U.S. NUCLEAR AEOULATORY Co " SISSION DOCKET NUMBER
FROM;Rochester Gas&Electric" Co.Roches ter, New York L.D.White, Jr.@LETTER QOAIOINAL 38COP Y DESCRIPTION ONOTOAIZED JRJNCLASSIFIED PAOP INPUT FOAM ENCLOSURE ,U.S.NUCLEAR AEOULATORY Co" SISSION NRC DISTRIBUTION Fon PART EO DOCKET MATERIAL DOCKET NUMBER 50-244 F ILE NUMIIER INCIDIÃZ REPORT DATE OF DOCUMENT 8/19/76 DATL'ECEIVE D 8/23/76 NUMBER OF COPIES RECEIVED One{Iskgned copy Ltz, trans the following:
{2 70) 50-244 F ILE NUMIIER NRC DISTRIBUTION Fon PART EO DOCKET MATERIAL                                  INCIDIÃZ REPORT TO:                                        FROM;                                        DATE OF DOCUMENT Rochester    Gas &  Electric"    Co.                8/19/76 Mr. Jame P. O'.Reilly.                Roches ter, New York                        DATL'ECEIVED L. D. White, Jr.                                    8/23/76
ACKNOWLEDGED 90 NOT REMOVE Licensee Event Report (RO-50-244/76-22) on 8/5/76 concerning Westinghouse notifying RG&E of a change in the assumptions to-be used by Westinghouse'in the safety analysis methods for the LOCA.(1-P)(1>>P)PLANT NAME Ginna.Ol NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.COLLINS BRANCH CKlEF: W~CYR FOR ACTION LIC..ASST.:
@LETTER                ONOTOAIZED            PAOP                    INPUT FOAM          NUMBER OF COPIES RECEIVED QOAIOINAL        JRJNCLASSIFIED 38COP Y                                                                                    One{Iskgned copy DESCRIPTION                                                ENCLOSURE Ltz, trans the following:                                 Licensee Event Report (RO 244/76-22) on 8/5/76 concerning Westinghouse notifying RG&E of a change in the assumptions         to-be used by Westinghouse'in the safety analysis ACKNOWLEDGED                                    methods for the LOCA.
W CYS ACRS CYS HOLDING S FOR ACTION/INFORMATION 8 23 76 Schwencer Sheppard RJL REG FILE I RE 2 MIPC SCHROEDER IPPOLITO HOUSTON NOVAK CHECK GRIMES CASE INTERNAL D IST Rl BUTION~~.rr TEDESCO MACCARY EISENHUT 4 XAj SERO VOLL'MER EJNCH KREGER J.COLLINS'r LPDR!lyons, N.Y.LPDR: Rochester N.Y~TIC: EXTERNAL DISTRIBUTION CONTROL NUMBER---NAC FORM 195{2-73)
90 NOT REMOVE (1-P)       (1>>P)
P II~~*P I~PfP I~~P PP~P~
PLANT NAME                                           NOTE:     IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J .COLLINS Ginna. Ol FOR ACTION/INFORMATION            8 23 76            RJL BRANCH CKlEF:                   Schwencer W ~ CYR FOR ACTION LIC..ASST.:                     Sheppard W     CYS ACRS     CYS   HOLDING S INTERNAL D IST Rl BUTION REG FILE I RE     2 MIPC SCHROEDER IPPOLITO HOUSTON NOVAK CHECK GRIMES                                                                                                         ~
I'ch Qc+t t ROCHESI'ER GAS AND ELECTRiC CORPORhTIOH o 89 EAST A'lEHUE, ROCHESTER, H.Y.i I649 1CCE II>IC LKOII D.WHITE.JR, VICS PtcCSIDKNT II 1 f Pi Ct'At 1 c August 19, 1976 Mr.James P.O'Reilly, Director U.S.Nuclear Re ulato Commi g ssion 9 Office'of Inspection and Enforcement Region I p~,.631 Park Avenue King of Prussia, Pennsylvania 19406  
                                                                                                                    . rr
                                                                                                                          ~
CASE 4      XAj TEDESCO MACCARY EISENHUT SERO VOLL'MER EJNCH                                                                                                 '  r KREGER J. COLLINS LPDR! lyons, N.Y.
LPDR: Rochester     N.Y ~
EXTERNAL DISTRIBUTION                                           CONTROL NUMBER       --
TIC:
NAC FORM 195 {2-73)
 
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II>IC ROCHESI'ER GAS AND ELECTRiC CORPORhTIOH         o   89 EAST         A'lEHUE, ROCHESTER, H.Y. i I649 LKOII D. WHITE. JR,                                                                     II f Pi Ct' 1
VICS PtcCSIDKNT                                                                At 1 c August 19, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Re g ulato Commi ssion                                                               9 Office'of Inspection and Enforcement Region I                                                                             p~,
            . 631 Park Avenue King of Prussia, Pennsylvania       19406


==Subject:==
==Subject:==
Reportable Occurrence 76-22 (14-day report), Error in Westinghouse safety analysis methods as applied to Ginna Station R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244  
Reportable Occurrence 76-22 (14-day report), Error in Westinghouse safety analysis methods as applied to Ginna Station R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
 
==Dear Mr. O.'Reilly:==
 
ln accordance, with Technical Specifications, Article 6.9.2a, the attached report of Reportable Occurrence 76-22, 14-day, is he'reby submitted. Two additional copies of this letter and the attachment are enclosed.
Very truly yours, V
L. D. White, Jr.
Attachment            J cc: Dr. Ernst Volgenau (40)
Mr. William G. McDonald (3) acct'IO t  0  ' grab c.11  gIc+    a(oo II,o
 
0 A


==Dear Mr.O.'Reilly:==
J  ~
LER    76-22/1T LICENSEE EVENT REPORTS COiVXROL BLOCK:                                                                t'PLEAGE PAINT ALL AECIU!AEO INFORMATION) 1                          6
                        'LICENSEE                                                                                  LICENSE                EVENT NAME ggNY86G LICENSE NUMBEA l        0  0      0    0  0    0    0    0 0'                  l.
TYPE 1    1    1
                                                                                                                                          'TYPE
                    ~
7    89                              14    15                                              25      26                      30    31      32 REPOAT    REPORT CATEGORY        TYPE    SOURCE              DOCKET NUMBER                            EVENT DATE                        AEPOAT DATE
[OD1]ooN'T                        T      ~L.        0  6  0    0        2  4    4        0    8    0    8    7    6      0    8    1  9  7  6 7 8            57      58      59      60      61                                68    69                          74    75                      80 I
EVENT DESCRIPTION Qpg      Westinghouse notified RG&E of a change in the assumptions to be used by Westinghous 7    8 9 in the safety analysis methods for the LOCA. (Reportable Occurrence 50-244/76-22, 80 7    89                                                                                                                                                  80 t00j4      14-day)      .
7    8 9                                                                                                                                                80
[os 7    8 9 t00I 7    89                                                                PRME                                                                            80 SYSTEM      CAUSE                                        COMPONENT              COMPONENT CODE        CODE            COMPONENT CODE              SUPPUEA            MANUFACTllREA 7
[oO7I  ~am 8 9 10 8
12 8
17        43          44 W12            0              N 11                                                                              47          48 CAUSE DESCRIPTION Q~g ~The          ori inal anal sis assumed that u er head re ion fluid tern erature was at T-cold.
7    8 9                                                                                                                                                80
  ~09      LIt has been shown that for Westinghouse PWR's the actual upper head fluid temperature 7      8 9                                                                                                                                                80
  ~10        was somewhat greater.                     Westinghouse has reanalyzed (cont'd. under Additional Factors) 7      89
                                                                                                                                ~h FACIUTY                                                          METHOD OF 80 STATUS            % POWER                OTHER STATUS          OISCOVEAY                          OISCOVEAY DESCRIPTION Q~g 7      8      9
                ~G              ~oo 10 o
12 13 NA 44      45      46 ii              i FOAM OF                                                                                                                                      80 AMOUNT OF ACTIVITY                                                LOCATION OF AELEASE NA 7      8      9                10    11                                  44        45                                                                  80 PERSONNEL EXPOSURES 7      8 S              11      12    13 PERSONNEL INJURIES NUMBFR            DESCRIPTION I1141    ~oo          0                              NA 7      8 9              11  12                                                                                                                          80 OFFSITE CONSEQUENCES
[Qs 7      89                                                                                                                                                80 LOSS OR DAMAGE TO FACILITY TYPE      DESCRIPTION.
Q~g        H                                        NA 7      89          10                                                                                                                                    80 PUBLICITY NA 7      89                                                                                                                                                80 ADDITIDNAL FAOTDRs(cont'd.                from Cause Description) the LOCA with T-cold equal to T-hot
~18          on a      eneric basis, and found that the eak claddin tern erature increases b 40 F.
7 89                                                                                                                                                      BD Westinghouse has advised us that other accident calculations for Ginna are not affected.                                                            ~
~19        No further corrective action is necessary.
7      89                                                                                                                                                80 NAME:                 R. Eliasz                                                PHovE 7 1 6/546-2700,              eat. 2748 GPO  88t 68T


ln accordance, with Technical Specifications, Article 6.9.2a, the attached report of Reportable Occurrence 76-22, 14-day, is he'reby submitted.
a ~ l"'
Two additional copies of this letter and the attachment are enclosed.Very truly yours, V L.D.White, Jr.Attachment J cc: Dr.Ernst Volgenau (40)Mr.William G.McDonald (3)grab acct'IO c.11 gIc+a(oo t 0'II,o 0 A J~COiVXROL LER 76-22/1T LICENSEE EVENT REPORTS BLOCK: t'PLEAGE PAINT ALL AECIU!AEO INFORMATION) 1 6'LICENSEE NAME ggNY86G l 14 15 7 89 LICENSE NUMBEA 0 0-0 0 0 0 0-0 LICENSE TYPE 0'l.1 1 1 25 26 30 EVENT'TYPE 31 32 REPOAT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE AEPOAT DATE[OD1]ooN'T
l}}
~T~L.0 6 0-0 2 4 4 0 8 0 8 7 6 0 8 1 9 7 6 7 8 57 58 5960 61 68 69 74 75 80 EVENT DESCRIPTION Qpg Westinghouse notified RG&E of a change in the assumptions to be used by Westinghous 7 8 9 80 I in the safety analysis methods for the LOCA.(Reportable Occurrence 50-244/76-22, 7 89 t00j4 14-day).7 8 9[os 7 8 9 t00I 7 89 SYSTEM CAUSE CODE CODE[oO7I~am 8 8 7 8 9 10 11 12 CAUSE DESCRIPTION Q~g~The ori inal anal COMPONENT CODE 17 PRME COMPONENT SUPPUEA 43 44 COMPONENT MANU FACTllREA W12 0 47 N 48 sis assumed that u er head re ion fluid tern erature was at T-cold.80 80 80 7 8 9 80~09 LIt has been shown that for Westinghouse PWR's the actual upper head fluid temperature 7 8 9 80~10 was somewhat greater.Westinghouse has reanalyzed (cont'd.under Additional Factors)OTHER STATUS NA AMOUNT OF ACTIVITY OFFSITE CONSEQUENCES
[Qs 7 89 FACIUTY STATUS%POWER Q~g~G~oo o 7 8 9 10 12 13 FOAM OF 7 8 9 10 11 PERSONNEL EXPOSURES 7 8 S 11 12 13 PERSONNEL INJURIES NUMBFR DESCRIPTION I1141~oo 0 NA 7 8 9 11 12 METHOD OF OISCOVEAY 44 45 46 44 45 NA LOCATION OF AELEASE 80 80 80 OISCOVEAY DESCRIPTION ii i~h 80 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION.
Q~g H 7 89 10 PUBLICITY NA NA 80 80 7 89 ADDITIDNAL FAOTDRs(cont'd.
from Cause Description) the LOCA with T-cold equal to T-hot~18 on a eneric basis, and found that the eak claddin tern erature increases b 40 F.80 7 89 BD Westinghouse has advised us that other accident calculations for Ginna are not affected.~~19 No further corrective action is necessary.
7 89 NAME: R.Eliasz 80 PHovE 7 1 6/546-2700, eat.2748 GPO 88t 68T a~l"''%, l}}

Latest revision as of 00:34, 3 February 2020

LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods
ML18142B253
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/19/1976
From: White L
Rochester Gas & Electric Corp
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1976-022-00
Download: ML18142B253 (6)


Text

Nl]C I oRM 196 ,U.S. NUCLEAR AEOULATORY Co " SISSION DOCKET NUMBER

{2 70) 50-244 F ILE NUMIIER NRC DISTRIBUTION Fon PART EO DOCKET MATERIAL INCIDIÃZ REPORT TO: FROM; DATE OF DOCUMENT Rochester Gas & Electric" Co. 8/19/76 Mr. Jame P. O'.Reilly. Roches ter, New York DATL'ECEIVED L. D. White, Jr. 8/23/76

@LETTER ONOTOAIZED PAOP INPUT FOAM NUMBER OF COPIES RECEIVED QOAIOINAL JRJNCLASSIFIED 38COP Y One{Iskgned copy DESCRIPTION ENCLOSURE Ltz, trans the following: Licensee Event Report (RO 244/76-22) on 8/5/76 concerning Westinghouse notifying RG&E of a change in the assumptions to-be used by Westinghouse'in the safety analysis ACKNOWLEDGED methods for the LOCA.

90 NOT REMOVE (1-P) (1>>P)

PLANT NAME NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J .COLLINS Ginna. Ol FOR ACTION/INFORMATION 8 23 76 RJL BRANCH CKlEF: Schwencer W ~ CYR FOR ACTION LIC..ASST.: Sheppard W CYS ACRS CYS HOLDING S INTERNAL D IST Rl BUTION REG FILE I RE 2 MIPC SCHROEDER IPPOLITO HOUSTON NOVAK CHECK GRIMES ~

. rr

~

CASE 4 XAj TEDESCO MACCARY EISENHUT SERO VOLL'MER EJNCH ' r KREGER J. COLLINS LPDR! lyons, N.Y.

LPDR: Rochester N.Y ~

EXTERNAL DISTRIBUTION CONTROL NUMBER --

TIC:

NAC FORM 195 {2-73)

P II ~ ~

  • P I

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~ ~ P PP ~

P ~

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II>IC ROCHESI'ER GAS AND ELECTRiC CORPORhTIOH o 89 EAST A'lEHUE, ROCHESTER, H.Y. i I649 LKOII D. WHITE. JR, II f Pi Ct' 1

VICS PtcCSIDKNT At 1 c August 19, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Re g ulato Commi ssion 9 Office'of Inspection and Enforcement Region I p~,

. 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 76-22 (14-day report), Error in Westinghouse safety analysis methods as applied to Ginna Station R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O.'Reilly:

ln accordance, with Technical Specifications, Article 6.9.2a, the attached report of Reportable Occurrence 76-22, 14-day, is he'reby submitted. Two additional copies of this letter and the attachment are enclosed.

Very truly yours, V

L. D. White, Jr.

Attachment J cc: Dr. Ernst Volgenau (40)

Mr. William G. McDonald (3) acct'IO t 0 ' grab c.11 gIc+ a(oo II,o

0 A

J ~

LER 76-22/1T LICENSEE EVENT REPORTS COiVXROL BLOCK: t'PLEAGE PAINT ALL AECIU!AEO INFORMATION) 1 6

'LICENSEE LICENSE EVENT NAME ggNY86G LICENSE NUMBEA l 0 0 0 0 0 0 0 0 0' l.

TYPE 1 1 1

'TYPE

~

7 89 14 15 25 26 30 31 32 REPOAT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE AEPOAT DATE

[OD1]ooN'T T ~L. 0 6 0 0 2 4 4 0 8 0 8 7 6 0 8 1 9 7 6 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT DESCRIPTION Qpg Westinghouse notified RG&E of a change in the assumptions to be used by Westinghous 7 8 9 in the safety analysis methods for the LOCA. (Reportable Occurrence 50-244/76-22, 80 7 89 80 t00j4 14-day) .

7 8 9 80

[os 7 8 9 t00I 7 89 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTllREA 7

[oO7I ~am 8 9 10 8

12 8

17 43 44 W12 0 N 11 47 48 CAUSE DESCRIPTION Q~g ~The ori inal anal sis assumed that u er head re ion fluid tern erature was at T-cold.

7 8 9 80

~09 LIt has been shown that for Westinghouse PWR's the actual upper head fluid temperature 7 8 9 80

~10 was somewhat greater. Westinghouse has reanalyzed (cont'd. under Additional Factors) 7 89

~h FACIUTY METHOD OF 80 STATUS  % POWER OTHER STATUS OISCOVEAY OISCOVEAY DESCRIPTION Q~g 7 8 9

~G ~oo 10 o

12 13 NA 44 45 46 ii i FOAM OF 80 AMOUNT OF ACTIVITY LOCATION OF AELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 8 S 11 12 13 PERSONNEL INJURIES NUMBFR DESCRIPTION I1141 ~oo 0 NA 7 8 9 11 12 80 OFFSITE CONSEQUENCES

[Qs 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION.

Q~g H NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIDNAL FAOTDRs(cont'd. from Cause Description) the LOCA with T-cold equal to T-hot

~18 on a eneric basis, and found that the eak claddin tern erature increases b 40 F.

7 89 BD Westinghouse has advised us that other accident calculations for Ginna are not affected. ~

~19 No further corrective action is necessary.

7 89 80 NAME: R. Eliasz PHovE 7 1 6/546-2700, eat. 2748 GPO 88t 68T

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