ML20140B063: Difference between revisions

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| number = ML20140B063
| number = ML20140B063
| issue date = 01/16/1986
| issue date = 01/16/1986
| title = Application for Amend to License NPF-12,changing Tech Specs Section 3/4.4.5 Re Steam Generator Tube Plugging Criteria. Application Dtd 851016 Withdrawn on 851025.Stated Westinghouse Topical Repts Provide Technical Discussion
| title = Application for Amend to License NPF-12,changing Tech Specs Section 3/4.4.5 Re Steam Generator Tube Plugging Criteria. Application Withdrawn on 851025.Stated Westinghouse Topical Repts Provide Technical Discussion
| author name = Nauman D
| author name = Nauman D
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 8601230450
| document report number = NUDOCS 8601230450
| title reference date = 10-16-1985
| package number = ML20140B066
| package number = ML20140B066
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
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In a let ter from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton dated October 16, 1985, South Carolina Electric and Gas Company (SCE6G) requested an amendment to the Virgil C. Summer Nuclear Station Technical Specifications, Section 3/4.4.5,
In a let ter from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton dated October 16, 1985, South Carolina Electric and Gas Company (SCE6G) requested an amendment to the Virgil C. Summer Nuclear Station Technical Specifications, Section 3/4.4.5,
             " Steam Generators," and its bases. This amendment was in part to revise the tube plugging limit definition in item 4.4.5.4.a. to exclude from plugging those tubes with indications greater than 1.25 inches below the top of the tubesheet which have an intact tube above them (one row higher in number, same column) .
             " Steam Generators," and its bases. This amendment was in part to revise the tube plugging limit definition in item 4.4.5.4.a. to exclude from plugging those tubes with indications greater than 1.25 inches below the top of the tubesheet which have an intact tube above them (one row higher in number, same column) .
By a letter dated October 25, 1985, SCE&G withdrew that reques t based on eddy-current testing results indicating no immediate need and concerns raised by the NRC Staf f. Based on further discussions with the NRC Staf f, SCE6G hereby requests the Technical Specifications be revised as indicated in Attachment A.
By a {{letter dated|date=October 25, 1985|text=letter dated October 25, 1985}}, SCE&G withdrew that reques t based on eddy-current testing results indicating no immediate need and concerns raised by the NRC Staf f. Based on further discussions with the NRC Staf f, SCE6G hereby requests the Technical Specifications be revised as indicated in Attachment A.
This amendment request, similar to that included in the October 16, 1985 submittal, permits SCE&G not to plug certain steam generator tubes containing defects in the tubesheet region of the tube.
This amendment request, similar to that included in the October 16, 1985 submittal, permits SCE&G not to plug certain steam generator tubes containing defects in the tubesheet region of the tube.
Included as Attachment II of the October 16, 1985 submittal were Topical Report WCAP's 10949 and 10950, "Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes." These documents were prepared by Westinghouse Electric Corporation to provide the technical discussion and justification for allowing certain tubes with degradations within the tubesheet region to remain in service. These WCAPs again provide the support for the amendment now being proposed and additional copies of the documents can be provided to the NRC Staff upon their request. Please be reminded that WCAP 10949 is pr,prietary to Westinghouse and the information contained within the WCAP should be treated accordingly.
Included as Attachment II of the October 16, 1985 submittal were Topical Report WCAP's 10949 and 10950, "Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes." These documents were prepared by Westinghouse Electric Corporation to provide the technical discussion and justification for allowing certain tubes with degradations within the tubesheet region to remain in service. These WCAPs again provide the support for the amendment now being proposed and additional copies of the documents can be provided to the NRC Staff upon their request. Please be reminded that WCAP 10949 is pr,prietary to Westinghouse and the information contained within the WCAP should be treated accordingly.
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Mr. Harold R. Den ton Steam Generator Tube Plugging Criteria January 16, 1986                                                            Page 2 not affect steam generator chemistry. No significant increases in the potential for or consequences from radiological accidents will occur due to the proposed amendment. Tube bundle integrity was demonstrated in WCAP 10949 and therefore precluded the probability for an increase in radiological events. Furthermore, the requirements for containment integrity and ef fluent systems are not altered by this amendment and provide further assurances that potentials for and consequences from radiological accidents are not significantly increased.
Mr. Harold R. Den ton Steam Generator Tube Plugging Criteria January 16, 1986                                                            Page 2 not affect steam generator chemistry. No significant increases in the potential for or consequences from radiological accidents will occur due to the proposed amendment. Tube bundle integrity was demonstrated in WCAP 10949 and therefore precluded the probability for an increase in radiological events. Furthermore, the requirements for containment integrity and ef fluent systems are not altered by this amendment and provide further assurances that potentials for and consequences from radiological accidents are not significantly increased.
These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee. The application fee for the review of the amendment request has been submitted previously as detailed in the August 30, 1985 letter from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton.
These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee. The application fee for the review of the amendment request has been submitted previously as detailed in the {{letter dated|date=August 30, 1985|text=August 30, 1985 letter}} from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton.
If you should have any additional questions, please advise.
If you should have any additional questions, please advise.
ul yo  s,
ul yo  s,

Latest revision as of 20:28, 12 December 2021

Application for Amend to License NPF-12,changing Tech Specs Section 3/4.4.5 Re Steam Generator Tube Plugging Criteria. Application Withdrawn on 851025.Stated Westinghouse Topical Repts Provide Technical Discussion
ML20140B063
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/16/1986
From: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20140B066 List:
References
NUDOCS 8601230450
Download: ML20140B063 (2)


Text

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South Caronna Electric & Gas Company Dan A. Nauman P.O Box 764 Vice President Columbia. SC 29218 Nuclear Operations (803) 748-3513 SCE&G

^===>*a January 16, 1986 Mr. ' Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Steam Generator Tube Plugging Criteria

Dear Mr. Denton:

In a let ter from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton dated October 16, 1985, South Carolina Electric and Gas Company (SCE6G) requested an amendment to the Virgil C. Summer Nuclear Station Technical Specifications, Section 3/4.4.5,

" Steam Generators," and its bases. This amendment was in part to revise the tube plugging limit definition in item 4.4.5.4.a. to exclude from plugging those tubes with indications greater than 1.25 inches below the top of the tubesheet which have an intact tube above them (one row higher in number, same column) .

By a letter dated October 25, 1985, SCE&G withdrew that reques t based on eddy-current testing results indicating no immediate need and concerns raised by the NRC Staf f. Based on further discussions with the NRC Staf f, SCE6G hereby requests the Technical Specifications be revised as indicated in Attachment A.

This amendment request, similar to that included in the October 16, 1985 submittal, permits SCE&G not to plug certain steam generator tubes containing defects in the tubesheet region of the tube.

Included as Attachment II of the October 16, 1985 submittal were Topical Report WCAP's 10949 and 10950, "Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes." These documents were prepared by Westinghouse Electric Corporation to provide the technical discussion and justification for allowing certain tubes with degradations within the tubesheet region to remain in service. These WCAPs again provide the support for the amendment now being proposed and additional copies of the documents can be provided to the NRC Staff upon their request. Please be reminded that WCAP 10949 is pr,prietary to Westinghouse and the information contained within the WCAP should be treated accordingly.

Attachment B to this letter is SCE&G's no significant hazards determination for this amendment. This amendment will not change or increase the amounts of ef fluents that may be released of fsite. The WCAP evaluation supporting this amendment demonstrates that tube integrity is maintained under postulated limiting conditions and therefore precludes the potential for radioactive releases. The types of effluents will not change because the amendment should hO 8601230450 860116 I g

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Mr. Harold R. Den ton Steam Generator Tube Plugging Criteria January 16, 1986 Page 2 not affect steam generator chemistry. No significant increases in the potential for or consequences from radiological accidents will occur due to the proposed amendment. Tube bundle integrity was demonstrated in WCAP 10949 and therefore precluded the probability for an increase in radiological events. Furthermore, the requirements for containment integrity and ef fluent systems are not altered by this amendment and provide further assurances that potentials for and consequences from radiological accidents are not significantly increased.

These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee. The application fee for the review of the amendment request has been submitted previously as detailed in the August 30, 1985 letter from Mr. O. W. Dixon, Jr. , to Mr. H. R. Denton.

If you should have any additional questions, please advise.

ul yo s,

._Ad Nauman DAN /AMM/tdh/csw Attachments c: V. C. Summer O. W. Dixon, Jr./T. C. Nichols , Jr.

E. H. Crews, Jr.

E. C. Roberts J. G. Connelly, Jr.

W. A. Williams , Jr.

J. Nelson Grace Group Managers

0. S. Bradham C. A. Price C. L. Ligun (NSRC)

R. M. Campbell K. E. Nodland R. A. Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr.

H. G. Shealy NPCF File