ML20117P286: Difference between revisions

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| number = ML20117P286
| number = ML20117P286
| issue date = 09/16/1996
| issue date = 09/16/1996
| title = Clarifies 960830 Ltr Requesting Administrative Change to Unit 2 TSs by Deleting Ref to cycle-specific L* Criteria
| title = Clarifies Requesting Administrative Change to Unit 2 TSs by Deleting Ref to cycle-specific L* Criteria
| author name = Morey D
| author name = Morey D
| author affiliation = SOUTHERN NUCLEAR OPERATING CO.
| author affiliation = SOUTHERN NUCLEAR OPERATING CO.
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| contact person =  
| contact person =  
| document report number = NUDOCS 9609230029
| document report number = NUDOCS 9609230029
| title reference date = 08-30-1996
| package number = ML20117P288
| package number = ML20117P288
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
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{{#Wiki_filter:*    Southirn Nuct:ar Op+ rating Company Post Othc2 Box 1295
{{#Wiki_filter:*    Southirn Nuct:ar Op+ rating Company Post Othc2 Box 1295
.      Birmingham. Alabama 35201 Tellphons (205) 868-5131 h k Dave Morey Vice President Southern Nudear Operating Company Farley Project September 16, 1996                    e somem decmc vstem Docket No.: 50-364                                                                  10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph hi. Farley Nuclear Plant - Unit 2 Steam Generator Technical Specification Pages Ladies and Gentlemen:
.      Birmingham. Alabama 35201 Tellphons (205) 868-5131 h k Dave Morey Vice President Southern Nudear Operating Company Farley Project September 16, 1996                    e somem decmc vstem Docket No.: 50-364                                                                  10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph hi. Farley Nuclear Plant - Unit 2 Steam Generator Technical Specification Pages Ladies and Gentlemen:
By letter dated hiay 20,1996, the NRC issued amendment 110 to the Farley Unit 2 Technical Specifications. This exigent amendment allowed steam generator tubes to remain in service with bands of axial degradation in the tube sheet region for the remainder of Cycle 11 provided suflicient non-degraded tubing remained to satisfy the L*-type criteria restrictions. Since the amendment was cycle-specific for Cycle 11 only, a Southern Nuclear letter dated August 30, 1996 requested an administrative change to the Farley Unit 2 Technical Specifications to delete the references to the cycle-specific L* criteria. However, in order to clarify the requested changes, this letter supersedes the August 30 requests and provides additional clarification.
By letter dated hiay 20,1996, the NRC issued amendment 110 to the Farley Unit 2 Technical Specifications. This exigent amendment allowed steam generator tubes to remain in service with bands of axial degradation in the tube sheet region for the remainder of Cycle 11 provided suflicient non-degraded tubing remained to satisfy the L*-type criteria restrictions. Since the amendment was cycle-specific for Cycle 11 only, a Southern Nuclear {{letter dated|date=August 30, 1996|text=letter dated August 30, 1996}} requested an administrative change to the Farley Unit 2 Technical Specifications to delete the references to the cycle-specific L* criteria. However, in order to clarify the requested changes, this letter supersedes the August 30 requests and provides additional clarification.
Currently, the following Farley Unit 2 Technical Specification amendment requests have been submitted to the NRC Staff:
Currently, the following Farley Unit 2 Technical Specification amendment requests have been submitted to the NRC Staff:
: 1. ODSCC Alternate Repair              SNC letter dated hiarch 29,1996 Criteria
: 1. ODSCC Alternate Repair              SNC letter dated hiarch 29,1996 Criteria
: 2. F* Repair Criteria                  SNC letter dated April 22,1996 as revised by letter dated hiay 3,1996
: 2. F* Repair Criteria                  SNC {{letter dated|date=April 22, 1996|text=letter dated April 22,1996}} as revised by letter dated hiay 3,1996
: 3. L* Repair Criteria                  SNC letter dated April 7.2,1996 Note: A current RAI will require revision to the proposed technical speci'ication pages.                          i
: 3. L* Repair Criteria                  SNC letter dated April 7.2,1996 Note: A current RAI will require revision to the proposed technical speci'ication pages.                          i
: 4. Elevated Tube Sheet Sleeve SNC letter dated August 23,1996 The first three amendments listed were all submitted prior to submittal of the cycle-specific L*
: 4. Elevated Tube Sheet Sleeve SNC {{letter dated|date=August 23, 1996|text=letter dated August 23,1996}} The first three amendments listed were all submitted prior to submittal of the cycle-specific L*
amendment. Consequently, the technical specificatien pages forwarded with those amendment requests require revision to reflect the cycle-specific L* amendment. Since the first two            3 amendments listed above may be approved prior to shutting down for the next Unit 2 refu outage, revised technical specification pages which include the cycle-specific L* amendment are included in Attachments 1 and 2 for both the ODSCC alternate repair criteria and the F*
amendment. Consequently, the technical specificatien pages forwarded with those amendment requests require revision to reflect the cycle-specific L* amendment. Since the first two            3 amendments listed above may be approved prior to shutting down for the next Unit 2 refu outage, revised technical specification pages which include the cycle-specific L* amendment are included in Attachments 1 and 2 for both the ODSCC alternate repair criteria and the F*
5 repair criteria.                                                                                    t 9609230029 960916 PDR ADOCK 05000364 P                          PDR
5 repair criteria.                                                                                    t 9609230029 960916 PDR ADOCK 05000364 P                          PDR
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U.S. Nuclear Regulatory Commission                                                          Page 2 Attachment 3 provides technical specification pages for the permanent L* repair criteria. The          :
U.S. Nuclear Regulatory Commission                                                          Page 2 Attachment 3 provides technical specification pages for the permanent L* repair criteria. The          :
marked-up pages also reflect the deletion of the cycle-specific L* repair criteria. Removal of        l the cycle-specific L* repair criteria, which expire at the start of the next Unit 2 refueling outage, does not affect the conclusions of the significant hazards evaluation which was provided with the original L* submittal. These technical specification changes also include suggested wording changes contained in the NRC Staff s request for additional information concerning L* contained in a letter dated August 12,1996.
marked-up pages also reflect the deletion of the cycle-specific L* repair criteria. Removal of        l the cycle-specific L* repair criteria, which expire at the start of the next Unit 2 refueling outage, does not affect the conclusions of the significant hazards evaluation which was provided with the original L* submittal. These technical specification changes also include suggested wording changes contained in the NRC Staff s request for additional information concerning L* contained in a {{letter dated|date=August 12, 1996|text=letter dated August 12,1996}}.
Attachment 4 contains technical specification pages associated with the elevated tubesheet laser welded sleeve technical specification amendment request. The cycle-specific L*
Attachment 4 contains technical specification pages associated with the elevated tubesheet laser welded sleeve technical specification amendment request. The cycle-specific L*
amendment is not included in this amendment. Additionally, the date of the Southern Nuclear submittal has been included where appropriate in the technical specification pages. This date was inadvertently left offin the original submittal.
amendment is not included in this amendment. Additionally, the date of the Southern Nuclear submittal has been included where appropriate in the technical specification pages. This date was inadvertently left offin the original submittal.

Latest revision as of 00:20, 23 September 2022

Clarifies Requesting Administrative Change to Unit 2 TSs by Deleting Ref to cycle-specific L* Criteria
ML20117P286
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 09/16/1996
From: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20117P288 List:
References
NUDOCS 9609230029
Download: ML20117P286 (2)


Text

  • Southirn Nuct:ar Op+ rating Company Post Othc2 Box 1295

. Birmingham. Alabama 35201 Tellphons (205) 868-5131 h k Dave Morey Vice President Southern Nudear Operating Company Farley Project September 16, 1996 e somem decmc vstem Docket No.: 50-364 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph hi. Farley Nuclear Plant - Unit 2 Steam Generator Technical Specification Pages Ladies and Gentlemen:

By letter dated hiay 20,1996, the NRC issued amendment 110 to the Farley Unit 2 Technical Specifications. This exigent amendment allowed steam generator tubes to remain in service with bands of axial degradation in the tube sheet region for the remainder of Cycle 11 provided suflicient non-degraded tubing remained to satisfy the L*-type criteria restrictions. Since the amendment was cycle-specific for Cycle 11 only, a Southern Nuclear letter dated August 30, 1996 requested an administrative change to the Farley Unit 2 Technical Specifications to delete the references to the cycle-specific L* criteria. However, in order to clarify the requested changes, this letter supersedes the August 30 requests and provides additional clarification.

Currently, the following Farley Unit 2 Technical Specification amendment requests have been submitted to the NRC Staff:

1. ODSCC Alternate Repair SNC letter dated hiarch 29,1996 Criteria
2. F* Repair Criteria SNC letter dated April 22,1996 as revised by letter dated hiay 3,1996
3. L* Repair Criteria SNC letter dated April 7.2,1996 Note: A current RAI will require revision to the proposed technical speci'ication pages. i
4. Elevated Tube Sheet Sleeve SNC letter dated August 23,1996 The first three amendments listed were all submitted prior to submittal of the cycle-specific L*

amendment. Consequently, the technical specificatien pages forwarded with those amendment requests require revision to reflect the cycle-specific L* amendment. Since the first two 3 amendments listed above may be approved prior to shutting down for the next Unit 2 refu outage, revised technical specification pages which include the cycle-specific L* amendment are included in Attachments 1 and 2 for both the ODSCC alternate repair criteria and the F*

5 repair criteria. t 9609230029 960916 PDR ADOCK 05000364 P PDR

__ ~

i I

U.S. Nuclear Regulatory Commission Page 2 Attachment 3 provides technical specification pages for the permanent L* repair criteria. The  :

marked-up pages also reflect the deletion of the cycle-specific L* repair criteria. Removal of l the cycle-specific L* repair criteria, which expire at the start of the next Unit 2 refueling outage, does not affect the conclusions of the significant hazards evaluation which was provided with the original L* submittal. These technical specification changes also include suggested wording changes contained in the NRC Staff s request for additional information concerning L* contained in a letter dated August 12,1996.

Attachment 4 contains technical specification pages associated with the elevated tubesheet laser welded sleeve technical specification amendment request. The cycle-specific L*

amendment is not included in this amendment. Additionally, the date of the Southern Nuclear submittal has been included where appropriate in the technical specification pages. This date was inadvertently left offin the original submittal.

In the attachments, if a change is to a previously issued technical specification page, the changes are indicated by pen and ink markups. If the change is to a proposed amendment that has not been issued, the changes are in bold, italics on the technical specification page.

If there are any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY p Jyj,p-us 1

Dave Morey Sworn to and subscribed before me this /b day af d & 1996 h>A Us -

' Notary Public' /

l My Commission Expires: br A4. /4 9 7

] O j REM / cit:ZIMMER1. DOC )

! Attachments:

, 1. Unit 2 TS Pages for Voltage-Based Repair Criteria

} 2. Unit 2 TS Pages for F* Repair Criteria

) 3. Unit 2 TS Pages for L* Repair Criteria and Deletion of Cycle-Specific L* j i 4. Unit I and 2 TS Pages for Elevated Tubesheet Laser Welded Sleeve i )

j cc: Mr. S. D. Ebneter, Region II Administrator l Mr. J. I. Zimmerman, NRR Project Manager l Mr. T. M. Ross, Plant Sr. Resident Inspector

. Mr. T. A. Reed, NRR - Materials and Chemical Engineering Branch Dr. D. E. Williamson, State Department of Public Health

. _ . -