ML073100092
| ML073100092 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/02/2007 |
| From: | Katz B Southern California Edison Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NPF-10/15-572 | |
| Download: ML073100092 (14) | |
Text
Brian Katz JSOUTHERN EDISON CALIFORNIA An EDISON INTERNATIONAL Company Vice President November 2, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Docket Nos. 50-361 and 50-362 Submittal of Supplement 3 to Proposed Technical Specification Change Number NPF-10/15-572 License Amendment Request, "Proposed Technical Specification Change, Steam Generator Tube Surveillance Program, Tube Repair" San Onofre Nuclear Generating Station, Units 2 and 3
References:
Letter from Brian Katz (SCE) to Document Control Desk (NRC) dated September 26, 2007,
Subject:
Response to Request for Additional Information and Submittal of Supplement 2 to Proposed Technical Specification Change Number NPF-10/15-572 License Amendment Request, "Proposed Technical Specification Change, Steam Generator Tube Surveillance Program, Tube Repair" San Onofre Nuclear Generating Station, Units 2 and 3,
Dear Sir or Madam:
Enclosure 3, (Supplement 3 to this amendment request) provides a specific limitation in the San Onofre Units 2 and 3 Technical Specifications to identify dates by which all sleeves will be removed from service for each Unit.
Supplement 3 provides a revised Technical Specification page for San Onofre Units 2 and Unit 3 to incorporate this change. The revised pages are to replace the corresponding pages previously submitted in Supplement 2.
The No Significant Hazards Consideration and Environmental Evaluation provided with PCN-572 both remain bounding.
This Amendment request Technical Specification change will be incorporated by Southern California Edison within 30 days of NRC approval.
P.O. Box 128 San Clemente, CA 92674-0128 949-368-9275 AC)O I Fax 949-368-9881 KWUR
Document Control Desk November 2, 2007 Should you have any questions, or require additional information, please contact Ms. L. T. Conklin at (949) 368-9443.
Sincerely,
Enclosures:
- 1. Notarized affidavit, Unit 2
- 2. Notarized affidavit, Unit 3
- 3. Supplement 3 to the Proposed License Amendment Request, Proposed Change Number 572 with attachments A - D (Revised Technical Specification change pages) cc: E. E. Collins, Jr., Regional Administrator, NRC Region IV N. Kalyanam, NRC Project Manager, San Onofre Units 2 and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, California Department of Public Health, Radiologic Health Branch
Enclosure 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, ET AL. for a Class 103 ) Docket No. 50-361 License to Acquire, Possess, and Use ) Supplement 3 to a Utilization Facility as Part of ) Amendment Application Unit No. 2 of the San Onofre Nuclear ) No. 245 Generating Station )
SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Supplement 3 to Amendment Application No. 245. This amendment application consists of Supplement 3 to Proposed Change No. 572 which is a request to revise Facility Operating License NPF-10 to update the Technical Specification steam generator program.
State of California County of San Diego Brian Katz, Vice Preýident Subscribed and sworn to (or-affmied) before me on this :2_ day of Ao/v.-Ub- _, 2007.
by -c6,* i*,\ ý4s-personally known to me pro.ed t. me en t,,a,.s .f i idefiee to be the person who appeared before me.
DAWN A. FARRELL Notary Public *r v y
Commission # 1623105 Notary Public - Caii9floMI
~Son Diego County __
MV Comm. Fxim*No 2,2WO wvvvvvv E
Enclosure 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, ET AL. for a Class 103 Docket No. 50-362 License to Acquire, Possess, and Use ) Supplement 3 to a Utilization Facility as Part of ) Amendment Application Unit No. 3 of the San Onofre Nuclear ) No. 230 Generating Station )
SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Supplement 3 to Amendment Application No. 230. This amendment application consists of Supplement 3 to Proposed Change No. 572 which is a request to revise Facility Operating License NPF-15 to update the Technical Specification steam generator program.
State of California County of San Diego Brian Katz, Vice Presikent Subscribed and sworn to (*-aftitred) before me on this _ . day of
_______..e-._+ ,2007.
personally known to me or provcd to me on thc basis of sati ' to be the person who appeared before me.
DAWN A-NaPbcI on . cou 6 2 3n1 0 5 Notary Public.-Caoflfdfto Notary Public so D*Sniego county
ENCLOSURE 3 Supplement 3 to the Proposed License Amendment Request Proposed Change Number 572 with attachments A - D (Revised Technical Specification change pages)
LICENSEE'S EVALUATION DESCRIPTION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE NPF-10/15-572 SUPPLEMENT 3, STEAM GENERATOR TUBE SURVEILLANCE PROGRAM, TUBE REPAIR San Onofre Nuclear Generating Station Units 2 and 3 PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGE REVISIONS (changes indicated by highlight and strikeout)
Unit 2: see Attachment A Unit 3: see Attachment B PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATIONS PAGE (Replacement Page - to replace a corresponding page previously submitted to the NRC in Supplement 2)
Unit 2: see Attachment C Unit 3: see Attachment D
1.0 INTRODUCTION
Supplement 3 to PCN-572 provides a specific limitation that all sleeves will be removed from service by a specified date (in response to an NRC request for additional information).
2.0 PROPOSED CHANGE
Supplement 3 provides a revised page for each Unit to incorporate the provision of a specific limitation that all steam generator sleeves will be removed from service by a specified date. The revised Technical Specification pages included in Supplement 3 are to replace the corresponding page number 5.0-16 for each Unit previously submitted in Supplement 2 to this amendment request.
3.0 REGULATORY SAFETY ANALYSIS The No Significant Hazards Consideration and Environmental Evaluation provided with PCN-572 both remain bounding.
Page 1 of 1
Attachment A PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGE REVISIONS (Supplement 3 Changes indicated by highlight and strikeout)
SONGS Unit 2
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Program (continued) type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective'full power months or one refueling outage (whichever is less) without being inspected.
- 3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whicheVer is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates:that'a crack-like-indication is not associated with a crack'(s), then the indication need not be treated as a crack.
- 4. All sleevesýshal1 beinspected with-eddy current prior to initial,,operation .. This includes pressure-retaining portions of'the parent tube in contact with the sleeve, the sleeve-to-tube weld and the pressure retaining portion of the sleeve.
- e. Provisions for' rmonitoriing.'operational primary to secondary LEAKAGE.
- f. Provisions for SG.tube repair methods. Steam generator tube repair methods shall provide the means to re-establish the RCS pressure boundary'integrity of SG tubes without removing the tube from service. For the purposes of these Specifications, tube plugging is not a repair. All acceptable tube repair methods arelisted below.,
- 1. TIG welded sleeving with heat treatment, as described in ABB/CE Topical Report. CEN-630-P. Rev. 2. iss "rrq'j y a roved bvytheNRC until December' 2009. All1 sleeves, shal'l b6,renmoved'from ser~vice' by Decembb~r,2009.:
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the entire length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
SAN ONOFRE--UNIT 2 5.0-16 Amendment No. 14O,204
Attachment B PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGE REVISIONS (Supplement 3 Changes indicated by highlight and strikeout)
SONGS Unit 3
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG)fLiProgram (continued) type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.
- 3. If crack indications are found in any SG tube, then the next inspection for leach SG for the degradation mechanism that caused. the crack indication shall not exceed 24 effective full power months or one refueling
. outage.(whichever is less. 'If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication .is not associated with a crack(.s), then the indication need not be treated as a-crack.
- 4. All sleeves~shall be inspected with eddy current prior to initial operation.,-..This..includes pressure retaining portions of the parent tube in contact with the sleeve, the sleeve-to-tube weld and the pressure retaining portion of the sleeve.
- e. Provisions for monitoring operational primary to secondary LEAKAGE.
- f. Provisions for SG tube repair methods. Steam generator tube repair methods shall provide the means to re-establish the RCS pressure boundary integrity of SG 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. TIG welded sleeving wi.th heat treatment, as described in ABB/CE Topical Report. CEN-.630-P.,.-Rev..... 2., i's eurrei9+y aooDroved bv the NRC until December. 2010., All sle6ves, shall be removed from-service by December 2010..
Tube repair can be performed, on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the entire length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
SAN ONOFRE--UNIT 3 5.0-16 Amendment No. 32,1-96
Attachment C PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATIONS PAGE (Replacement Page for the Corresponding Supplement 2 Page)
SONGS Unit 2
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Program (continued) type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The, first sequential period shall be considered to begin after the first inservice inspection of. the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less): wi~thout being inspected.
- 3. If crack indications are found in any SG tube, then the next inspection for each SG fo-r the degradation mechanism that, caused the crack indication shall not exceed 24 effective full powermonths, or one refueling outage (Whichever is less'). I.:f: defini~t.ive information, such as from examination.of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates, that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.-
- 4. All sleeves shall be inspected. with eddy current prior to initial operat~ion .This includes pressure retaining portions of the parent tube in contact with the sleeve,,
the sleeve-to-tube weld and the:pressure retaining portion of.the.sleeve. '
- e. Provisions for monitoring operational primary to secondary LEAKAGE. . .
- f. Provisions for SG tube repair methods. Steam generator tube repair methods shall provide the means to re-establish the RCS pressure boundary integrity of SG 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. TIG welded sleeving with heat treatment, as described in ABB/CE Topical' Report, CEN-630-P, Rev. 2,'is approved by the NRC until December 2009. All' sleeves shall be removed from service by December 2009.
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the entire length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
SAN ONOFRE--UNIT 2 5.0-16 Amendment No.
Attachment D PCN-572 SUPPLEMENT 3 PROPOSED TECHNICAL SPECIFICATIONS PAGE (Replacement Page for the Corresponding Supplement 2 Page)
SONGS Unit 3
Procedures, Programs- and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Program (continued) type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first.sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.
- 3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the. crack indication shal.l not exceed 24 effective full power months or one refueling outage *(whichever is less).. If definitive information, such as from examination ,of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-likeindication. is not associated with a.crack(s), then .the iindication need not be treated as a crack.
- 4. All sl~ee-ves shallbe ihspected with eddy current~prior to initial operation..-:This 'inc.l~udes pressure retaining portions of the parent tube in contact with the sleeve, the sleeve-to-tube weld:and the pressure retaining portion of the sleeve.
- e. Provisions for monitoring operational primary to secondary LEAKAGE.
- f. Provisions for SG tube.repair methods. Steam generator tube repair methods shall provide the means to re-establish the RCS pressure boundary integrity of SG 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. TIG welded sleeving with heat treatment, as described in ABB/CE Topical Report, CEN-630-P, Rev. 2, is approved by the NRC until December 2010. All sleeves shall be removed from service by December 2010.
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the entire length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
SAN ONOFRE--UNIT 3 5.0-16 Amendment No.