3F0994-02, Forwards Form NIS-1 Owner Rept for ISI & Calculation 32-4100461-00, CR-3 Pressurizer Surge Nozzle Flaw Evaluation. Encl Withheld: Difference between revisions

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              . September 2, 1994
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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC       20555
. September 2, 1994 3F0994-02 L
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555


==Subject:==
==Subject:==
Line 33: Line 34:


==Dear Sir:==
==Dear Sir:==
 
Attached please find a Summary Report of the inspections performed at Crystal River Unit 3 since the preceding (July 1992) summary report on Class 1 and 2 pressure retaining components' and their supports.
Attached please find a Summary Report of the inspections performed at Crystal River Unit 3 since the preceding (July 1992) summary report on Class 1 and 2 pressure retaining components' and their supports.                 .The Summary Report is submitted in accordance with the 1983 Edition of the ASME Boiler and Pressure Vessel Code, Section
.The Summary Report is submitted in accordance with the 1983 Edition of the ASME Boiler and Pressure Vessel Code, Section
              . XI,z Article IWA-6000. The Summary Report provides the NIS-1 form, "0wner's Data Report for Inservice Inspection" and supplemental sheets. Supplemental Sheet 3                                   7 contains. a ~ summary of +he attached NIS-2 forms, "0wner's Reports for Repairs and                             .
. XI,z Article IWA-6000.
Replacements". This submittal also includes a summary of the examinations performed
The Summary Report provides the NIS-1 form, "0wner's Data Report for Inservice Inspection" and supplemental sheets.
              'by B&W Nuclear Technologies (BWNT) on Code : lass 1 and 2 components.
Supplemental Sheet 3 7
BW1T prepared for- Florida Pon .         Corporation (FPC) an evaluation analysis of the examination results of the pressurizer surge nozzle ISI inspection performed in May 1994. During that inspection, a subsurface flaw was detected in the weld connecting the nozzle to the pressurizer lower head. The flaw was characterized as 1.47 inches long and a depth of 0.31 inches.             The evaluation analysis is being provided in accordance with Subsection IWB-3125, Summer 1983' Addenda of'ASME Section XI.                               The analysis shows that the flaw indication detected during Refuel 9 is acceptable and will not reach critical length during the next 1.6 Effective full Power Years. This analysis demonstrates the w' eld to be acceptable for service until approximately December 1995.     FPC intends to complete by August 1995 an additional comprehensive evaluation of the cyclic stresses affecting the weld to demonstrate the flaw detected during the Refuel 9 inspection will not reach critical length during the remainder of plant life. These evaluations are consistent with work performed by the B&W Owners
contains. a ~ summary of +he attached NIS-2 forms, "0wner's Reports for Repairs and Replacements". This submittal also includes a summary of the examinations performed
    ..          Group regarding. thermal stratificatien.
'by B&W Nuclear Technologies (BWNT) on Code : lass 1 and 2 components.
94o913o41e 940902 PDR     ADOCK 05'>00302 0   ;              PDR CRYSTAL RIVER ENEROY COMPLEX
BW1T prepared for-Florida Pon.
Corporation (FPC) an evaluation analysis of the examination results of the pressurizer surge nozzle ISI inspection performed in May 1994. During that inspection, a subsurface flaw was detected in the weld connecting the nozzle to the pressurizer lower head. The flaw was characterized as 1.47 inches long and a depth of 0.31 inches.
The evaluation analysis is being provided in accordance with Subsection IWB-3125, Summer 1983' Addenda of'ASME Section XI.
The analysis shows that the flaw indication detected during Refuel 9 is acceptable and will not reach critical length during the next 1.6 Effective full Power Years. This analysis demonstrates the w' eld to be acceptable for service until approximately December 1995.
FPC intends to complete by August 1995 an additional comprehensive evaluation of the cyclic stresses affecting the weld to demonstrate the flaw detected during the Refuel 9 inspection will not reach critical length during the remainder of plant life. These evaluations are consistent with work performed by the B&W Owners Group regarding. thermal stratificatien.
94o913o41e 940902 PDR ADOCK 05'>00302 0
PDR CRYSTAL RIVER ENEROY COMPLEX
* 15760 W. Power une Street
* 15760 W. Power une Street
* Crystal River
* Crystal River
* Florida 34428-6708 * (904)795-6486
* Florida 34428-6708 * (904)795-6486
                                                      ' A Florida Progress Company
' A Florida Progress Company
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i LU. S. Nuclear Regulatory Commission                                                     ,
i LU. S. Nuclear Regulatory Commission 3F0994-02 Page 2.
3F0994-02                                                                               :
l FPC is submitting - an affidavit from BWNT requesting Enclosure 1. containing the i
Page 2.                                                                                 l FPC is submitting - an affidavit from BWNT requesting Enclosure 1. containing the
~
                    ~
evaluation analysis of the pressurizer surge nozzle be withheld from public disclosure i
i evaluation analysis of the pressurizer surge nozzle be withheld from public disclosure   i on the' grounds that contains proprietary information. The affidavit is submitted in. t accordance with 10 CFR 2.790 (b)(1).
on the' grounds that contains proprietary information. The affidavit is submitted in.
Sincerely,                                                                               ;
t accordance with 10 CFR 2.790 (b)(1).
P. M. Beard, Jr.                                                                         :
Sincerely, P. M. Beard, Jr.
Senior Vice President                                                                   !
Senior Vice President Nuclear Operations PMB:LVC 1
Nuclear Operations PMB:LVC                                                                                 1 Attachments XC: Regional Administrator NRR Project Manager                                                               i Senior Resident inspector                                                         ;
Attachments XC: Regional Administrator NRR Project Manager i
                                                                                                    }
Senior Resident inspector
}
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Latest revision as of 04:23, 15 December 2024

Forwards Form NIS-1 Owner Rept for ISI & Calculation 32-4100461-00, CR-3 Pressurizer Surge Nozzle Flaw Evaluation. Encl Withheld
ML20072S094
Person / Time
Site: Crystal River 
Issue date: 09/02/1994
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304C528 List:
References
3F0994-02, 3F994-2, NUDOCS 9409130418
Download: ML20072S094 (2)
v • d • e


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. September 2, 1994 3F0994-02 L

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

Inservice Inspection (ISI) Summary Report, 1994 Inspection

Dear Sir:

Attached please find a Summary Report of the inspections performed at Crystal River Unit 3 since the preceding (July 1992) summary report on Class 1 and 2 pressure retaining components' and their supports.

.The Summary Report is submitted in accordance with the 1983 Edition of the ASME Boiler and Pressure Vessel Code, Section

. XI,z Article IWA-6000.

The Summary Report provides the NIS-1 form, "0wner's Data Report for Inservice Inspection" and supplemental sheets.

Supplemental Sheet 3 7

contains. a ~ summary of +he attached NIS-2 forms, "0wner's Reports for Repairs and Replacements". This submittal also includes a summary of the examinations performed

'by B&W Nuclear Technologies (BWNT) on Code : lass 1 and 2 components.

BW1T prepared for-Florida Pon.

Corporation (FPC) an evaluation analysis of the examination results of the pressurizer surge nozzle ISI inspection performed in May 1994. During that inspection, a subsurface flaw was detected in the weld connecting the nozzle to the pressurizer lower head. The flaw was characterized as 1.47 inches long and a depth of 0.31 inches.

The evaluation analysis is being provided in accordance with Subsection IWB-3125, Summer 1983' Addenda of'ASME Section XI.

The analysis shows that the flaw indication detected during Refuel 9 is acceptable and will not reach critical length during the next 1.6 Effective full Power Years. This analysis demonstrates the w' eld to be acceptable for service until approximately December 1995.

FPC intends to complete by August 1995 an additional comprehensive evaluation of the cyclic stresses affecting the weld to demonstrate the flaw detected during the Refuel 9 inspection will not reach critical length during the remainder of plant life. These evaluations are consistent with work performed by the B&W Owners Group regarding. thermal stratificatien.

94o913o41e 940902 PDR ADOCK 05'>00302 0

PDR CRYSTAL RIVER ENEROY COMPLEX

  • 15760 W. Power une Street
  • Crystal River

' A Florida Progress Company

(

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-. ~.-

i s.

o.

i LU. S. Nuclear Regulatory Commission 3F0994-02 Page 2.

l FPC is submitting - an affidavit from BWNT requesting Enclosure 1. containing the i

~

evaluation analysis of the pressurizer surge nozzle be withheld from public disclosure i

on the' grounds that contains proprietary information. The affidavit is submitted in.

t accordance with 10 CFR 2.790 (b)(1).

Sincerely, P. M. Beard, Jr.

Senior Vice President Nuclear Operations PMB:LVC 1

Attachments XC: Regional Administrator NRR Project Manager i

Senior Resident inspector

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