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| issue date = 02/06/1976
| issue date = 02/06/1976
| title = LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
| title = LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
| author name = White L D
| author name = White L
| author affiliation = Rochester Gas & Electric Corp
| author affiliation = Rochester Gas & Electric Corp
| addressee name = O'Reilly J P
| addressee name = O'Reilly J
| addressee affiliation = NRC/IE, NRC/RGN-I
| addressee affiliation = NRC/IE, NRC/RGN-I
| docket = 05000244
| docket = 05000244
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ROCHESTER GAS AHD ELECTRIC CORPORATION o S9 EAST AVEMUE, ROCHESTER, H.Y.14649 LEON O.WHITE.JR.VICE PRCSIDEtlT TCLEPHDNC AREA CODE T C 546 2700 February 6, 1976 Mr.James P.O'Reilly, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406~<<Gttb'Q FPByg 1976~V o So l4ICLRAR REGlRAIORT COHUAISSIOH jp IAol I Sedloa
{{#Wiki_filter:ROCHESTER GAS AHD ELECTRIC CORPORATION         o S9 EAST AVEMUE, ROCHESTER, H.Y. 14649 LEON O. WHITE. JR.                                                           TCLEPHDNC VICE PRCSIDEtlT                                                   AREA CODE T C     546 2700 February 6, 1976
                                                                ~        <<Gttb                    '
Mr. James P. O'Reilly, Director                                     FPByg            1976    ~
U. S. Nuclear Regulatory Commission                           Q V o So l4ICLRAR REGlRAIORT Office of Inspection and Enforcement                                       COHUAISSIOH          jp IAolI Sedloa Region I 631 Park Avenue King of Prussia, Pennsylvania         19406


==Subject:==
==Subject:==
Reportable Occurrence 76-03 (30-day report)Residual Heat Removal System low pressure piping excessive leakage.R.E.Ginna Nuclear Power Plant, Unit No.1~Docket No.50-244  
Reportable Occurrence 76-03 (30-day report) Residual Heat Removal System low pressure piping excessive leakage.
R. E. Ginna Nuclear Power Plant, Unit No. 1
                  ~
Docket No. 50-244


==Dear Mr.O'Reilly:==
==Dear Mr. O'Reilly:==
In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-03, 30-day, is hereby submitted.
 
Two additional copies of this letter and'the attachment are enclosed.Very truly yours, L.D.@hi e, Jr.Attachment cc: Mr.John G.Davis (30)Mr.William G.McDonald (3), 1363 M~M~M~M r'~M~~~a f~~~M'M-v r rr~,(~~I~M l/rr'1MM M CONTROL BLOCK: 1 LICENSEE NAME Jog N Y R 9 G 1 0 7 89 14 15 REPORT REPORT CATEGORY TYPE SOURCE[oD71ooN'T
In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-03, 30-day, is hereby submitted. Two additional copies of this letter and 'the attachment are enclosed.
~L~L 7 8 57 58 59 60 Ll>ENBEE EVENT REPORT)TJLEASE RIIIIT ALL REQUIREO INFORMATION)
Very truly yours, L. D. @hi e, Jr.
LICENSE NUMBER 0-0 0 0 0 0-0 0 4 25 26 LICENSE TYPE EVENT TYPE 1 1 1 1.~03 30 31 32 OOCKFT NUMBER EVENT DATE REPORT DATE 0 5 0-0 2 4 4 0 1 1 5 7 6 0 2 0 6 7 6 61 68 69 74 75 80 EVENT DESCRIPTION During routine 105 psig hydro test of residual heat removal (RHR)suction piping from~CU 7 8 9 80[QQ3]sump B to reactor coolant drain tank pumps, 2~85 gal./hr.was measured at"A" pump 80 7 89[os]suction flan e.Flan e bolts were ti htened and leakage was reduce'd to zero.7 8 9 Qpg (Reportable Occurrence 76-03, 30-day)7 8 9 Jog 7 89 PRME SYSTEM CAUSE COMPONENT CODE CODE COMPONENT CODE SUPPUER VGLATCN[os]~WG A P I P 9 X X~N E 9 9 9 Y 7 8 9 10 11 12 17 43 48 CAUSE DESCRIPTION toDB]Maintenance personnel had tightened flange bolts after maintenance for proper perform-COMPONENT MANUFACTURER 44 47 80 80 80 7 8 9 tOOI ance at normal o eratin 80 ressure, but had failed to do so sufficientl to withstand test 7 89 FA Cli ITY STATUS 69 POWER 9~OS O 7 8 9 10 12 13 FORM OF ACTIVITY COATENT 7 8 9.10 11 PERSONNEL EXPOSURES 7 8 9 11 12 13 PERSONNEl INJURIES NUMBER DESCRIPTION
Attachment cc: Mr. John G. Davis (30)
[iia]~00 0 NA 7 89 11 12 METHOD OF DISCOVERY DISCOVERY DESCRIPTION OTHER STATUS NA NA b 44 45 46 80 LOCATION OF RELEASE AMOUNT OF ACTIVITY 44 45 80 80 80 OFFSITE CONSEQUENCES 7 8 9 80~10 pressure.The PORC recommended that maintenance (cont.'d.under Additional Factors)80 7 89 LOSS OR DAMAGE TO FACILITY TYPE-DESCRIPTION t116I H 7 89 10 PUBLICITY NA eo 80 7 89 ADDITIONAL FACTORS t11I (cont'd.from Cause Description) procedure used for inspection of pump would include 7 89~19 verification that flanges were properly tightened.
Mr. William G. McDonald (3),
80 7 89 NAME: Charles U.Hartlieb 80.PH0NE.716 546-2700 ext.291-216 GPO 88 I 667}}
1363
 
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Ll>ENBEE EVENT REPORT CONTROL BLOCK:                                                                    )TJLEASE     RIIIIT ALL REQUIREO INFORMATION) 1 LICENSEE                                                                                    LICENSE                EVENT NAME                                    LICENSE NUMBER                                     TYPE                  TYPE Jog N Y                R    9 G        1        0   0  0       0   0   0     0   0         0         4   1   1   1   1   .   ~03
                  ~
7 89                                    14    15                                                25    26                    30     31     32 REPORT    REPORT CATEGORY            TYPE    SOURCE              OOCKFT NUMBER                             EVENT DATE                       REPORT DATE
[oD71ooN'T                          L      ~L        0   5   0   0       2   4     4       0   1     1   5     7   6         0   2   0   6   7 6 7 8              57        58        59      60      61                                   68     69                         74     75                     80 EVENT DESCRIPTION During routine 105 psig hydro test of residual heat removal (RHR) suction piping from~CU 7   8 9                                                                                                                                                       80 sump         B to   reactor       coolant     drain   tank   pumps,       2 85 gal./hr. was measured at "A" pump
                                                                                          ~
[QQ3]
7 89                                                                                                                                                           80
[os] suction flan e. Flan e bolts were ti htened and leakage was reduce'd to zero.
7 8 9                                                                                                                                                         80 Qpg     (Reportable               Occurrence         76-03,     30-day) 7   8 9                                                                                                                                                       80 Jog 7   89                                                                     PRME                                                                               80 SYSTEM         CAUSE                                         COMPONENT              COMPONENT CODE           CODE               COMPONENT CODE             SUPPUER               MANUFACTURER            VGLATCN
[os] ~WG                   A             P   I   P 9 X     X         ~N                 E 9     9   9             Y 7   8 9 10                 11         12                       17         43           44                  47          48 CAUSE DESCRIPTION toDB]   Maintenance personnel had tightened flange bolts after maintenance for proper perform-7   8 9                                                                                                                                                       80 tOOI ance at normal o eratin                             ressure,     but had failed to do so sufficientl to withstand test 7 8 9                                                                                                                                                          80
~10 pressure.                  The PORC recommended                  that maintenance (cont.'d. under Additional Factors) 7    89                                                                           METHOD OF 80 FA Cli ITY STATUS                 69 POWER               OTHER STATUS          DISCOVERY                          DISCOVERY DESCRIPTION 9               ~OS         O               NA                      b                            NA 7   8       9                 10             12 13                         44      45        46                                                          80 FORM OF ACTIVITY         COATENT AMOUNT OF ACTIVITY                                                LOCATION OF RELEASE 7   8       9     .             10     11                                   44        45                                                                  80 PERSONNEL EXPOSURES 7   8 9                 11       12     13                                                                                                                 80 PERSONNEl INJURIES NUMBER               DESCRIPTION
[iia] ~00             0                               NA 7   89                 11     12                                                                                                                           80 OFFSITE CONSEQUENCES 7   89                                                                                                                                                       eo LOSS OR DAMAGE TO FACILITY TYPE         -
DESCRIPTION t116I   H                                             NA 7   89           10                                                                                                                                         80 PUBLICITY 7   89                                                                                                                                                       80 ADDITIONAL FACTORS t11I     (cont'd. from Cause Description) procedure used for inspection of pump would include 7   89
~19     verification that flanges were properly tightened.
7   89                                                                                                                                                       80  .
NAME:               Charles U. Hartlieb                                               PH0NE. 716 546-2700             ext. 291-216 GPO 88 I 667}}

Latest revision as of 00:31, 3 February 2020

LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B894
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/06/1976
From: White L
Rochester Gas & Electric Corp
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1975-003-00
Download: ML18142B894 (3)
v • d • e


Text

ROCHESTER GAS AHD ELECTRIC CORPORATION o S9 EAST AVEMUE, ROCHESTER, H.Y. 14649 LEON O. WHITE. JR. TCLEPHDNC VICE PRCSIDEtlT AREA CODE T C 546 2700 February 6, 1976

~ <<Gttb '

Mr. James P. O'Reilly, Director FPByg 1976 ~

U. S. Nuclear Regulatory Commission Q V o So l4ICLRAR REGlRAIORT Office of Inspection and Enforcement COHUAISSIOH jp IAolI Sedloa Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 76-03 (30-day report) Residual Heat Removal System low pressure piping excessive leakage.

R. E. Ginna Nuclear Power Plant, Unit No. 1

~

Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-03, 30-day, is hereby submitted. Two additional copies of this letter and 'the attachment are enclosed.

Very truly yours, L. D. @hi e, Jr.

Attachment cc: Mr. John G. Davis (30)

Mr. William G. McDonald (3),

1363

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Ll>ENBEE EVENT REPORT CONTROL BLOCK: )TJLEASE RIIIIT ALL REQUIREO INFORMATION) 1 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE Jog N Y R 9 G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 . ~03

~

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

[oD71ooN'T L ~L 0 5 0 0 2 4 4 0 1 1 5 7 6 0 2 0 6 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION During routine 105 psig hydro test of residual heat removal (RHR) suction piping from~CU 7 8 9 80 sump B to reactor coolant drain tank pumps, 2 85 gal./hr. was measured at "A" pump

~

[QQ3]

7 89 80

[os] suction flan e. Flan e bolts were ti htened and leakage was reduce'd to zero.

7 8 9 80 Qpg (Reportable Occurrence 76-03, 30-day) 7 8 9 80 Jog 7 89 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VGLATCN

[os] ~WG A P I P 9 X X ~N E 9 9 9 Y 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION toDB] Maintenance personnel had tightened flange bolts after maintenance for proper perform-7 8 9 80 tOOI ance at normal o eratin ressure, but had failed to do so sufficientl to withstand test 7 8 9 80

~10 pressure. The PORC recommended that maintenance (cont.'d. under Additional Factors) 7 89 METHOD OF 80 FA Cli ITY STATUS 69 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 9 ~OS O NA b NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT AMOUNT OF ACTIVITY LOCATION OF RELEASE 7 8 9 . 10 11 44 45 80 PERSONNEL EXPOSURES 7 8 9 11 12 13 80 PERSONNEl INJURIES NUMBER DESCRIPTION

[iia] ~00 0 NA 7 89 11 12 80 OFFSITE CONSEQUENCES 7 89 eo LOSS OR DAMAGE TO FACILITY TYPE -

DESCRIPTION t116I H NA 7 89 10 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS t11I (cont'd. from Cause Description) procedure used for inspection of pump would include 7 89

~19 verification that flanges were properly tightened.

7 89 80 .

NAME: Charles U. Hartlieb PH0NE. 716 546-2700 ext. 291-216 GPO 88 I 667

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