3F0307-11, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction: Difference between revisions

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| number = ML071030140
| number = ML071030140
| issue date = 03/30/2007
| issue date = 03/30/2007
| title = License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction
| title = License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction
| author name = Infanger P
| author name = Infanger P
| author affiliation = Progress Energy Florida, Inc
| author affiliation = Progress Energy Florida, Inc
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==Subject:==
==Subject:==
Crystal River Unit 3 - License Amendment Request #264, Revision 2:
Crystal River Unit 3 -
License Amendment Request #264, Revision 2:
Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity (TAC No. MD2054) - Administrative Correction
Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity (TAC No. MD2054) - Administrative Correction


Line 29: Line 30:


==Dear Sir:==
==Dear Sir:==
 
By {{letter dated|date=March 14, 2007|text=letter dated March 14, 2007}}, Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., submitted the referenced License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC). This LAR is requesting a modification to the Crystal River Unit 3 (CR-3) Improved Technical Specifications (ITS) regarding steam generator tube integrity.
By letter dated March 14, 2007, Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., submitted the referenced License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC). This LAR is requesting a modification to the Crystal River Unit 3 (CR-3) Improved Technical Specifications (ITS) regarding steam generator tube integrity.
During a review of the LAR, after it had been submitted to the NRC, an incorrect page number in the footer was discovered in both the mark-up and revision bar sections.
During a review of the LAR, after it had been submitted to the NRC, an incorrect page number in the footer was discovered in both the mark-up and revision bar sections. The error was discovered on the page numbered 5.0-18. The correct footer for this page should be 5.0-17A (existing page number).
The error was discovered on the page numbered 5.0-18. The correct footer for this page should be 5.0-17A (existing page number).
In accordance with the provisions of 10 CFR 50.90, FPC hereby provides an administrative correction for the proposed Page 5.0-18, only.
In accordance with the provisions of 10 CFR 50.90, FPC hereby provides an administrative correction for the proposed Page 5.0-18, only.
Attachment A provides the proposed marked-up ITS page to show the proposed change, and Attachment B provides those same changes presented more formally with revision bars. The footer in both attachments has been corrected to reflect that the page number should be 5.0-17A.
Attachment A provides the proposed marked-up ITS page to show the proposed change, and Attachment B provides those same changes presented more formally with revision bars. The footer in both attachments has been corrected to reflect that the page number should be 5.0-17A.
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Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428


U.S. Nuclear Regulatory Commission                                                   Page 2 of 2 3F0307-11 This letter establishes no new regulatory commitments.
U.S. Nuclear Regulatory Commission Page 2 of 2 3F0307-11 This letter establishes no new regulatory commitments.
If you have any questions regarding this submittal, please contact me at (352) 563-4796.
If you have any questions regarding this submittal, please contact me at (352) 563-4796.
Sincerely, Paul E. Infang Supervisort Licensing & Regulatory Programs PEI/ff Attachments:
Sincerely, Paul E. Infang Supervisort Licensing & Regulatory Programs PEI/ff Attachments:
A.     Proposed Improved Technical Specification Changes (Mark-up)
A.
B.     Proposed Improved Technical Specification Changes (Revision Bar Format) xc:     NRR Project Manager Regional Administrator, Region II Senior Resident Inspector
Proposed Improved Technical Specification Changes (Mark-up)
B.
Proposed Improved Technical Specification Changes (Revision Bar Format) xc:
NRR Project Manager Regional Administrator, Region II Senior Resident Inspector


PRORESS ENERGY FLORIDA, INC.
PRORESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT A Proposed Improved Technical Specification Changes (Mark-up)
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT A Proposed Improved Technical Specification Changes (Mark-up)
St   eei-e*u   indicates deleted text.
St eei-e*u indicates deleted text.
ighlighted t-ext indicates added text.
ighlighted t-ext indicates added text.


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CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT B Proposed Improved Technical Specification Changes (Revision Bar Format)
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT B Proposed Improved Technical Specification Changes (Revision Bar Format)


Procedures, Programs and Manuals 5.6 5.6   Procedures,   Programs and Manuals 5.6.2.10   OTSG Program (continued)
Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Program (continued)
: e. Provisions for monitoring operational   primary to secondary LEAKAGE.
: e.
: f. Provisions for OTSG tube repair methods. Steam generator tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of OTSG tubes without removing the tube from service. For the purposes of these Specifications, tube plugging is not a repair.     All acceptable tube repair methods are listed below.
Provisions for monitoring operational primary to secondary LEAKAGE.
: 1. Sleeve installation in accordance with the B&W process (or method) described in report BAW-2120P. No more than five thousand sleeves may be installed in each OTSG.
: f.
: 2. Installation of repair rolls in the upper and lower tubesheets in accordance with BAW-2303P, Revision 4.
Provisions for OTSG tube repair methods.
The repair process (single, overlapping, or multiple roll) may be performed in each tube. The repair roll area will be examined using eddy-current methods following installation. The repair roll must be free of flaws for the repair to be considered acceptable. If the repair roll is unacceptable, the tube must be repaired or plugged.
Steam generator tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of OTSG tubes without removing the tube from service.
For the purposes of these Specifications, tube plugging is not a repair.
All acceptable tube repair methods are listed below.
: 1.
Sleeve installation in accordance with the B&W process (or method) described in report BAW-2120P.
No more than five thousand sleeves may be installed in each OTSG.
: 2.
Installation of repair rolls in the upper and lower tubesheets in accordance with BAW-2303P, Revision 4.
The repair process (single, overlapping, or multiple roll) may be performed in each tube.
The repair roll area will be examined using eddy-current methods following installation.
The repair roll must be free of flaws for the repair to be considered acceptable.
If the repair roll is unacceptable, the tube must be repaired or plugged.
(continued)
(continued)
Crystal River Unit 3                   5.0-17A                   Amendment No.}}
Amendment No.
Crystal River Unit 3 5.0-17A}}

Latest revision as of 03:09, 15 January 2025

License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction
ML071030140
Person / Time
Site: Crystal River 
Issue date: 03/30/2007
From: Infanger P
Progress Energy Florida
To:
Document Control Desk, NRC/NRR/ADRO
References
3F0307-11, TAC MD2054
Download: ML071030140 (5)


Text

0Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.90 March 30, 2007 3F0307-11 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 -

License Amendment Request #264, Revision 2:

Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity (TAC No. MD2054) - Administrative Correction

Reference:

Crystal River Unit 3 to NRC Letter, 3F0307-07, dated March 14, 2007, "Crystal River Unit 3 - License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information (TAC No.

MD2054)"

Dear Sir:

By letter dated March 14, 2007, Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., submitted the referenced License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC). This LAR is requesting a modification to the Crystal River Unit 3 (CR-3) Improved Technical Specifications (ITS) regarding steam generator tube integrity.

During a review of the LAR, after it had been submitted to the NRC, an incorrect page number in the footer was discovered in both the mark-up and revision bar sections.

The error was discovered on the page numbered 5.0-18. The correct footer for this page should be 5.0-17A (existing page number).

In accordance with the provisions of 10 CFR 50.90, FPC hereby provides an administrative correction for the proposed Page 5.0-18, only.

Attachment A provides the proposed marked-up ITS page to show the proposed change, and Attachment B provides those same changes presented more formally with revision bars. The footer in both attachments has been corrected to reflect that the page number should be 5.0-17A.

This submittal is purely administrative in nature and does not impact the No Significant Hazards Consideration Determination made for LAR #264.

Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

U.S. Nuclear Regulatory Commission Page 2 of 2 3F0307-11 This letter establishes no new regulatory commitments.

If you have any questions regarding this submittal, please contact me at (352) 563-4796.

Sincerely, Paul E. Infang Supervisort Licensing & Regulatory Programs PEI/ff Attachments:

A.

Proposed Improved Technical Specification Changes (Mark-up)

B.

Proposed Improved Technical Specification Changes (Revision Bar Format) xc:

NRR Project Manager Regional Administrator, Region II Senior Resident Inspector

PRORESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT A Proposed Improved Technical Specification Changes (Mark-up)

St eei-e*u indicates deleted text.

ighlighted t-ext indicates added text.

PRORESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #264, REVISION 2 Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity Administrative Correction ATTACHMENT B Proposed Improved Technical Specification Changes (Revision Bar Format)

Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Program (continued)

e.

Provisions for monitoring operational primary to secondary LEAKAGE.

f.

Provisions for OTSG tube repair methods.

Steam generator tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of OTSG tubes without removing the tube from service.

For the purposes of these Specifications, tube plugging is not a repair.

All acceptable tube repair methods are listed below.

1.

Sleeve installation in accordance with the B&W process (or method) described in report BAW-2120P.

No more than five thousand sleeves may be installed in each OTSG.

2.

Installation of repair rolls in the upper and lower tubesheets in accordance with BAW-2303P, Revision 4.

The repair process (single, overlapping, or multiple roll) may be performed in each tube.

The repair roll area will be examined using eddy-current methods following installation.

The repair roll must be free of flaws for the repair to be considered acceptable.

If the repair roll is unacceptable, the tube must be repaired or plugged.

(continued)

Amendment No.

Crystal River Unit 3 5.0-17A