ML051950215
| ML051950215 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/15/2005 |
| From: | Stephen Monarque NRC/NRR/DLPM/LPD2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Monarque, S R, NRR/DLPM, 415-1544 | |
| Shared Package | |
| ML051950225 | List: |
| References | |
| Download: ML051950215 (12) | |
Text
July 15, 2005 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS ON RELOCATION OF INSERVICE INSPECTION AND TESTING REQUIREMENTS (TAC NOS. MC5034 AND MC5035)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 243 to Renewed Facility Operating License No. DPR-32 and Amendment No. 242 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively. The amendments change the Technical Specifications (TS) in response to your application transmitted by letter dated November 4, 2004, as supplemented on February 21 and June 2, 2005.
These amendments delete the Inservice Inspection (ISI) and Inservice Testing (IST) requirements in TS 4.0.5; relocate the IST requirements to the administrative section of the TS as a program; revise the TS to reference either the IST program or American Society of Mechanical Engineers Code,Section XI instead of TS 4.0.5; delete the individual TS references to the ISI program; and add a TS Bases Control Program to the TS Administrative Controls section.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Stephen Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosures:
- 1. Amendment No. 243 to DPR-32
- 2. Amendment No. 242 to DPR-37
- 3. Safety Evaluation cc w/encls: See next page
ML051950215 NRR-058 OFFICE PDII-1/PM PDII-2/LA EMEB/SC EMCB/SC IROB/SC OGC PDII-1/SC NAME SMonarque EDunnington DFischer TChan CSchulten KKannler LOlshan for EMarinos DATE 6/03/2005 7/13/05 6/6/2005 6/17/2005 6 /24 /2005 7/12/2005 7/15/05
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS ON RELOCATION OF INSERVICE INSPECTION AND TESTING REQUIREMENTS (TAC NOS. MC5034 AND MC5035)
DATED: July 15, 2005 DISTRIBUTION:
PUBLIC PDII-1 Rdg.
E. Dunnington S. Monarque E. Hackett E. Marinos OGC G. Hill (4), TWFN, 5/C/3 ACRS K. Landis, RII DLPM DPR
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 4, 2004, as supplemented on February 21 and June 2, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 243, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by LOlshan for/
Evangelos C. Marinos, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 15, 2005
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 242 Renewed License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 4, 2004, as supplemented on February 21 and June 2, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by LOlshan for/
Evangelos C. Marinos, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 15, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 LICENSE AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages TS ii TS ii TS iii TS iii TS 4.0-2 TS 4.0-2 TS 4.0-3 TS 4.0-3 TS 4.0-4 TS 4.0-4 TS 4.0-5 TS 4.0-5 TS 4.0-6 TS 4.0-7 TS 4.0-8 TS 4.1-1 TS 4.1-1 TS 4.1-9b TS 4.1-9b TS 4.2-1 TS 4.2-1 TS 4.2-2 TS 4.2-2 TS 4.2-4 TS 4.2-4 TS 4.3-1 TS 4.3-1 TS 4.3-2 TS 4.5-1 TS 4.5-1 TS 4.5-2 TS 4.5-2 TS 4.8-1 TS 4.8-1 TS 4.8-2 TS 4.8-2 TS 4.8-3 TS 4.8-3 TS 4.11-2 TS 4.11-2 TS 4.11-4 TS 4.11-4 TS 4.17-1 TS 4.17-1 TS 6.4-1 TS 6.4-1 TS 6.4-6 TS 6.4-6 TS 6.4-7 TS 6.4-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated November 4, 2004, as supplemented by letters dated February 21 and June 2, 2005, Virginia Electric and Power Company (the licensee) requested changes to the Technical Specifications (TS) for Surry Power Station, Units 1 and 2 pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.90. The licensee requested these changes in order to delete the Inservice Inspection (ISI) and Inservice Testing (IST) requirements in TS 4.0.5; relocate the IST requirements to the administrative section of the TS as a program; revise the TS to reference either the IST program or American Society of Mechanical Engineers Code (ASME Code),Section XI instead of TS 4.0.5; delete the individual TS references to the ISI program; and add a TS Bases Control Program to the TS Administrative Controls section.
The supplements dated February 21 and June 2, 2005, provided additional information that clarified the application as originally noticed and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 15, 2005 (70 FR 7771).
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(g)(5)(ii) require that, if a revised ISI program for a facility conflicts with the TS for that facility, the licensee shall apply to the Commission for amendment to the TS to conform the TS to the revised program. The licensee shall submit this application, as specified in 10 CFR 50.4, at least 6 months before the start of the period during which the provisions become applicable, as determined by 10 CFR 50.55(g)(4). The fourth interval ISI Program at Surry, Units 1 and 2 was updated to comply with the 1998 Edition with the 1999 and 2000 Addenda of the ASME Code as required by 10 CFR 50.55a(g)(4).
The regulations in 10 CFR 50.55a(f)(5)(ii) require that, if a revised IST program for a facility conflicts with the TS for that facility, the licensee shall apply to the Commission for amendment to the TS to conform the TS to the revised program. The licensee shall submit this application, as specified in 10 CFR 50.4, at least 6 months before the start of the period during which the provisions become applicable, as determined by 10 CFR 50.55a(f)(4).
The NRC staff also considered the following guidance:
NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 3, contains no references to ISI Program requirements since referencing ISI program requirements is redundant with the regulations under 10 CFR 50.55a.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendments, which are described in the November 4, 2004, submittal as supplemented by letters dated February 21 and June 2, 2005. The NRC staffs detailed evaluation follows.
3.1 Proposed TS Changes for the IST Program The licensee requested the following changes.
- 2. Change the references in TS 4.1.B.1, items 4 and 5 of TS Table 4.1-2A, TS 4.5.A.1, TS 4.5.A.2, TS 4.5.B.1, TS 4.5.B.2, TS 4.8.A.2.a, TS 4.8.A.3.a, TS 4.8.A.5.b, TS 4.11.C.1, TS 4.11.C.2, and TS 4.11.C.3 from TS 4.0.5 to the IST program.
- 3. Revise TS 4.8.B to delete reference to ASME Section XI.
3.1.1 NRC Staffs Evaluation for the IST Program TS 4.0.5 establishes the surveillance requirements for the IST of ASME Class 1, 2, and 3 components at Surry, Units 1 and 2. TS 4.0.5.a currently states that:
Inservice Testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(f), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(f)(6)(i).
In part, 10 CFR 50.55a(f), Inservice Testing Requirements, requires that Class 1, 2, and 3 components and their supports meet the requirements of the ASME Operation and Maintenance of Nuclear Power Plants (OM) Code.
The regulations in 10 CFR 50.55a(f)(4) establish the effective ASME Code edition and addenda to be used by licensees for performing IST of pumps and valves. Pursuant to 10 CFR 50.55a(f)(4)(ii), the licensee, in its letter dated June 25, 2003, submitted IST programs for the fourth interval at Surry, Units 1 and 2. The licensees IST Programs were updated to comply with the appropriate revisions of the ASME OM Code and included the 1998 Edition, the 1999 Addenda, and the 2000 Addenda as the new Code of Record for the fourth interval. As a consequence, the TS 4.0.5 reference to Section XI of the ASME Code results in a reference to a deleted portion of the Code. By letter dated November 4, 2004, the licensee submitted proposed license amendments to correct TS 4.0.5.
According to 10 CFR 50.55a(f)(5)(ii), if a revised IST program for a facility conflicts with the TS for the facility, the licensee shall apply to the Commission for amendment to the TS to conform the TS to the revised program. The licensee shall submit this application, as specified in 10 CFR 50.4, at least 6 months before the start of the period during which the provisions become applicable as determined by 10 CFR 50.55a(f)(4) of this section.
In 1990, the ASME published the initial edition of the ASME OM Code that provides rules for the IST of pumps and valves. The ASME Committee on OM of Nuclear Power Plants develops and maintains the OM Code. The ASME OM Code was developed in response to a directive from the ASME Board on Nuclear Codes and Standards. This directive transferred responsibility for development and maintenance of rules for the IST of pumps and valves from the ASME,Section XI, Subcommittee on Nuclear ISI to the ASME OM Committee. ASME intended for the ASME OM Code to replace the Section XI rules for the IST of pumps and valves. As a result, the IST requirements for pumps and valves have been deleted from Section XI. The fourth interval IST program at Surry, Units 1 and 2 was updated to comply with the 1998 Edition with the 1999 and 2000 Addenda of the ASME Code for OM as required by 10 CFR 50.55a(f)(4)(ii).
Consequently, the TS 4.0.5 reference to Section XI of the ASME Code for IST requirements results in a reference to a deleted portion of the ASME Code.
The TS change deletes TS 4.0.5, relocates the IST program to Section 6 of the TS, and deletes the reference to TS 4.0.5 in the individual TS. The TS changes do not eliminate any inservice tests and do not relinquish the licensee of its responsibility to seek relief from Code test requirements when they are impractical. The changes will eliminate the ASME Code inconsistency between the IST program and the TS as required by 10 CFR 50.55a(f)(5)(ii). The proposed changes will maintain consistency with the ASME Code requirements. Therefore, the NRC staff finds these proposed changes to be acceptable.
3.2 Proposed TS Changes for the ISI Program The licensee requested the following changes.
- 2. Revise TS 4.2 and TS Table 4.2-1 items 2.1.1, 2.1.2, and 2.1.3 to replace references to TS 4.0.5 with ASME Section XI.
- 3. Delete TS 4.3 and its Basis.
3.2.1 NRC Staffs Evaluation for the ISI Program The licensee stated that TS 4.0.5 establishes the surveillance requirements for the ISI of ASME Class 1, 2, and 3 components for Surry, Units 1 and 2. TS 4.0.5.a currently states that:
Inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
The licensee stated that when the Improved TS (ITS) were developed the ISI requirements were removed since they were identical to the 10 CFR 50.55a requirements and were, therefore, considered redundant. Thus, the ISI requirements of TS 4.0.5 are being deleted consistent with the ITS.
In part, 10 CFR 50.55a(g) requires that Class 1, 2, and 3 components and their supports meet the requirements of the ASME Code. The ASME publishes a new edition of the ASME Code every 3 years, and a new addendum every year. The fourth interval ISI Programs for Surry, Units 1 and 2 were updated to comply with the 1998 Edition with the 1999 and 2000 Addenda of the ASME Code as required by 10 CFR 50.55a(g)(4).
The licensees proposed TS change deletes TS 4.0.5, which refers to the ISI Program, ASME Section XI, and 10 CFR 50.55a. These changes do not eliminate any ISI not covered by 10 CFR 50.55a and do not relinquish the licensee of its responsibility to seek relief from Code requirements when they are impractical. The changes will eliminate the redundancy between the TS and 10 CFR 50.55a.
The proposed amendments continue to maintain section 4.2, Augmented Inspections, which pertains to ISIs that augment those required by ASME Section XI. In this case, the licensee maintains the TS in an ISI area not covered by either the ASME Section XI Code or 10 CFR 50.55a specific to Surry, Units 1 and 2.
The licensees proposed changes eliminate the redundancy of ISI requirements from the TS as these requirements are already covered under 10 CFR 50.55a. Therefore, the NRC staff finds these proposed changes to be acceptable.
3.3 Proposed TS Changes for Administrative Reasons The licensee requested the following changes.
- 1. Delete the title of SR 4.3 on page ii.
- 2. Change the title of TS 6.4 on pages iii and TS 6.4-1 from Unit Operating Procedures to Unit Operating Procedures and Programs.
- 3. Delete TS page 4.3-3.
These proposed changes are completely administrative in nature. As such, the NRC staff finds these proposed changes acceptable.
3.4 Proposed Addition of TS Section 6.4.J In its submittal dated November 4, 2004, the licensee proposed to add TS Section 6.4.J in order to establish a Bases Control Program. The licensee stated that the TS changes that are approved by the NRC Consolidated Line Item Improvement Program (CLIIP) often include the requirement for a TS Bases Control Program as a condition for implementing a particular Technical Specification Task Force (TSTF) traveler (e.g., TSTF-358 associated with missed surveillances, TSTF-359 associated with mode changes). The licensee requested this change because it anticipates that future CLIIP opportunities will invoke a similar requirement for a TS Bases Control Program, and it seeks to establish consistency with ITS and existing station administrative procedures.
The proposed changes will implement a TS Bases Control Program consistent with NUREG-1431. The guidance contained in NUREG-1431 maintains no specific reference to the ISI Program or ASME Section, XI; therefore, the licensees removal of the references is consistent with NUREG-1431. Also, the addition of TS Section 6.4.J does not affect the IST Program. As such, the NRC staff finds this proposed change to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comment.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (70 FR 7771). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: W. K. Poertner T. K. Steingass Date: July 15, 2005
Surry Power Station, Units 1 & 2 cc:
Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711