ML13002A472
| ML13002A472 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/06/2013 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Heacock D Dominion Nuclear Connecticut |
| Kim J NRR/DORL/LPL1-1 301-415-4125 | |
| References | |
| TAC ME8320 | |
| Download: ML13002A472 (21) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION UNIT 3 -ISSUANCE OF AMENDMENT RE:
SNUBBER SURVEILLANCE REQUIREMENTS (TAC NO. ME8320)
Dear Mr. Heacock:
The Commission has issued the enclosed Amendment No. 257 to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit NO.3 (MPS3), in response to your application dated April 2, 2012.
The proposed amendment would revise Technical Specification surveillance requirements for snubbers to conform to the MPS3 Snubber Examination, Testing, and Service Life Monitoring Program Plan.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, r~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 257 to NPF-49
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO.3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 257 Renewed License No. NPF-49
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the applicant dated April 2, 2012, 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;
- 8.
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 0) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and Oi) 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
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 257, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the renewed license. DNC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
..La GLt,v0 George A. Wilson, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: February 6, 2013
ATTACHMENT TO LICENSE AMENDMENT NO. 257 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 4 Page 4 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 Insert 3/47-22 3/47-22 3/47-23 3/47-23 3/47-24 3/47-24 3/47-25 3/47-25 3/47-26 3/47-26 3/47-27 3/47-27 3/47-28 3/47-28 3/47-29 3/47-29 6-17e 6-17e 6-17f
- 4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, revised through Amendment No. 257 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DNC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
DNC shall not take any action that would cause Dominion Resources, Inc.
(DRI) or its parent companies to void, cancel, or diminish DNC's Commitment to have sufficient funds available to fund an extended plant shutdown as represented in the application for approval of the transfer of the licenses for MPS Unit NO.3.
(4)
Immediately after the transfer of interests in MPS Unit NO.3 to DNC, the amount in the decommissioning trust fund for MPS Unit NO.3 must, with respect to the interest in MPS Unit No.3, that DNC would then hold, be at a level no less than the formula amount under 10 CFR 50.75.
(5)
The decommissioning trust agreement for MPS Unit NO.3 at the time the transfer of the unit to DNC is effected and thereafter is subject to the following:
(a)
The decommissioning trust agreement must be in a form acceptable to the NRC.
(b)
With respect to the decommissioning trust fund, investments in the securities or other obligations of Dominion Resources, Inc. or its affiliates or subsidiaries, successors, or assigns are prohibited.
Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.
(c)
The decommissioning trust agreement for MPS Unit NO.3 must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee until the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.
(d)
The decommissioning trust agreement must provide that the agreement can not be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.
Renewed License No. NPF-49 Amendment No. 257
PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers shall be OPERABLE. The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only iftheir failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES 1, 2, 3, and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance ofthe Snubber Examination, Testing, and Service Life Monitoring Program Plan.
MILLSTONE - UNIT 3 3/47-22 AmendmentNo.~
+l,Ml-; 257
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~
257
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ADMINISTRATIVE CONTROLS PROCEPURES AND PROGRAMS (Continued)
RG 1.183), which were considered in completing the vulnerability assessments, are documented in the UFSARIcurrent licensing basis. Compliance with these RGs is consistent with the current licensing basis as described in the UFSAR and other licensing basis documents.
- d.
Measurement, at designated locations, ofthe CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode ofoperation by one train of the CREV s, operating at the flow rate required by the Surveillance Requirements, at a Frequency of48 months on a STAGGERED TEST BASIS. The results shall be trended and used as part ofthe 24 month assessment of the CRE boundary.
- e.
The quantitative limits on unfiltered air inleakage into the CRE.
These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses ofDBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure ofCRE occupants to these hazards will be within the assumptions in the licensing basis.
The provisions of Surveillance Requirement 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c. and d., respectively.
- 1.
Snubber Examination, Testing, and Service Life Monitoring Program Plan This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (lSI) requirements for supports. The program shall be in accordance with the following:
- a.
This program shall meet 10 CFR 50.55a(g) lSI requirements for supports.
- b.
The program shall meet the requirements for lSI ofsupports set forth in subsequent editions ofthe Code ofRecord and addenda ofthe American Society ofMechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance ofNuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b), subject to its limitations and modifications, and subject to Commission approval.
MILLSTONE - UNIT 3 6-17e Amendment No. ~ 257
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- c.
The program shall, as allowed by 10 CFR SO.SSa(b )(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Pre service and Inservice Examination and Testing ofDynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" in lieu ofSection XI ofthe ASME BPV Code lSI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR SO.SSa(a)(3).
- d.
The 120-month program updates shall be made in accordance with 10 CFR SO.SSa (including 10 CFR S0.5Sa(b)(3)(v)) subject to the limitations and modifications listed therein.
6.8.S Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, ofthe REMODCM.
6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 6.8.S above shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.
Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP, within 14 days of implementation.
MILLSTONE - UNIT 3 6-17f Amendment No. 257
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 257 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NO.3 DOCKET NO. 50-423
1.0 INTRODUCTION
By application dated April 2, 2012 (Accession No. ML12097A200), Dominion Nuclear Connecticut, Inc. (DNC), the licensee, submitted a request for changes to the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs). The proposed amendment would revise the TS 3/4.7.10, specifically TS Surveillance Requirement (SR) 4.7.10 to reference the newly added Administrative Control, TS Section 6.8.i, "Snubbers Testing Program." This addition includes the planned revisions to the MPS3 snubber inservice inspection (lSI), testing, and service life monitoring programs and removes the specific snubber inservice examination and testing requirements from the TSs.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical Specifications," provides the regulatory requirements for the contents in a licensee's TSs. Regulations in 10 CFR 50.36(c)(3) provides in part, that Surveillance Requirements (SRs) are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained.
In determining the acceptability of revising TS 3/4.7.10, the NRC staff used the accumulation of generically approved guidance in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors," dated Fall 1981, and NUREG-1431, "Standard Technical Specifications, Westinghouse Plants, Revision 4.0," dated April 2012.
Regulations in 10 CFR 50.55a(g)(5)(ii) require that, if a revised lSI program for a facility conflicts with the TS for that facility, the licensee shall apply to the Commission for amendment of the TS to conform the TS to the revised program.
Regulations in 10 CFR 50.55a(b)(3)(v) note that a licensee may use Subsection ISTD, "Preservice and Inservice Testing of Dynamic Restraints (Snubbers) in Light-Water Reactors Power Plants, " ASME OM Code, 1995 Edition through the latest edition and addenda incorporated by the reference in paragraph 10 CFR 50.55a(b)(2), in place of the requirements for snubbers in ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, IWF-5200(a) and
- 2 (b) and IWF-S300(a) and (b), by making appropriate changes to the their technical specifications or licensee-controlled documents. Preservice and inservice examinations must be performed using the VT-3 visual examination method described in IWA-2213.
MPS3 is currently in the third 10-year lSI interval. The third 10-year lSI interval at MPS3 began on April 23, 2009 and is scheduled to end on April 22, 2019. For the rest of the third 10-year lSI interval at MPS3, the snubber program will meet the requirements of the ASME OM Code, Subsection ISTD, and Edition 2004 in lieu of the current requirements of ASME B&PV Code,Section XI, Edition 2004.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Proposed TS Changes and Basis Information The proposed changes to the MPS3 TSs are summarized below:
Reference to TS SR 4.7.1 Og in TS ACTION 3.7.10 will be replaced with reference toSR4.7.10.
- TS SR 4.7.10 will be revised to replace specific surveillance requirements for demonstrating snubber operability with reference to the newly added Administrative Control Section 6.8.i "Snubber Examination, Testing, and Service Life Monitoring Program Plan," as follows:
TS SR 4.7.10: Each snubber shall be demonstrated OPERABLE by performance of the Snubber Examination, Testing, and Service Life Program Plan.
(Note: All other details about snubber visual inspection, functional testing and service life program requirements as described in original TS SR 4.7.10 a, b, c, d, e, f, g and h will be deleted).
Section 6.8.i, "Snubber Examination, Testing and Service Life Monitoring Program,"
will be added to the Administrative Controls Section 6.8, "Procedures and Programs,"
to provide a description of the snubber testing program, as follows:
6.8.i SNUBBER EXAMINATION. TESTING. AND SERVICE LIFE MONITORING PROGRAM This program conforms to the examination, testing, and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR SO.SSa inservice inspection (lSI) requirements for supports. The program shall be in accordance with the following:
- a. This program shall meet 10 CFR SO.SSa(g) lSI requirements for supports.
- b. The program shall meet the requirements of lSI for supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV)
- 3 Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b),
subject to its limitations and modifications, and subject to Commission approval.
- c. The program shall, as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" in lieu of Section XI of the ASME BPV Code lSI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).
- d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications listed therein.
At MPS3, snubber visual inspection and functional testing are performed in accordance with the specific requirements ofTS 3/4.7.10. As requested by the licensee, in Relief Request IR-3-01, the NRC authorized use of TS 3/4.7.10 for the third 10-year lSI interval in lieu of the requirements contained in the 2004 Edition (no Addenda) of ASME B&PV Code Section XI, Articles IWF-5300(a), 5300(b) and 5300(c) (Note: DNC did not seek relief from the requirements of IWF-5200(a), 5200(b) and 5200(c)).
For the remainder of the third 1 O-year lSI interval, as permitted by 10 CFR 50.55a(b)(3)(v), DNC intends to adopt Subsection ISTD, of the ASME OM Code, 2004 Edition (no Addenda), in place of the requirements for snubbers in ASME B&PV Code,Section XI, Articles IWF-5200(a) and (b) and IWF-5300(a) and (b). Regulations in 10 CFR 50.55a(b)(3)(v) also requires that when using this permitted alternative, preservice and inservice examination of snubbers must be performed using the VT-3 method specified in ASME B&PV Section XI, IWA-2213. As such, the proposed changes to TS 3/4.7.10 are required to conform the TSs to the revised snubber program.
As identified above, Relief Request IR-3-01 granted relief from the requirements of the 2004 Edition (no Addenda) of ASME B&PV Code Section XI, Articles IWF-5300(a), 5300(b) and 5300(c) for the third 10-year lSI interval since the use of TS 3/4.7.10 provided an acceptable level of quality and safety. With the adoption of ISTD, the requirements of Articles IWF-5200(a) and (b) and IWF-5300(a) and (b) will be met for the snubbers at MPS3.
3.2 NRC Staff Evaluation of Proposed Changes The licensee has developed a detailed "Snubber Examination, Testing, and Service Life Monitoring Program," as a licensee-controlled document at MPS3, which will be implemented in lieu of the deleted TS snubber examination, testing and service life program requirements. This snubber examination, testing and service life monitoring program will be based on the requirements referenced in the TS Administrative Control Section 6.8.i.
The NRC staff has reviewed the requirements for "Snubber Examination, Testing, and Service Life Monitoring Program," as described in the submittal and as proposed in the new TS 6.8.L The staff finds that the program requirements are consistent with the lSI and testing requirements for snubbers as required by 10 CFR 50.55a. The staff also notes that the snubber
- 4 lSI and testing program at MPS3 will be performed per the requirements of the ASME OM Code (2004 Edition), Subsection ISTD in lieu of ASME B&PV Section XI requirements, as allowed by 10 CFR 50.55a(b)(3)(v). Therefore, the NRC staff concludes that the proposed new TS 6.8.i is acceptable.
Based on the above finding that the "Snubber Examination, Testing, and Service Life Monitoring Program," is consistent with 10 CFR 50.55a, the NRC staff further finds that the examination, testing and service life monitoring for snubbers in accordance with the Snubber Testing Program, as required by SR 4.7.10, is sufficient to assure that the necessary quality of the snubber is maintained. Therefore, the NRC staff concludes that the proposed changes to SR 4.7.10 are consistent with the requirements in 10 CFR 50.36(c)(3} and are acceptable.
The NRC staff finds that the proposed change to LCO 3.7.10 to revise its existing reference to "Specification SR 4.7.10" is administrative in nature. Therefore, the staff concludes that this change is acceptable.
As specified in this submittal, the licensee shall revise the snubber inservice inspection and testing program at MPS3 for the remainder of the third 1 O-year interval, which is scheduled to end on April 22, 2019, to meet the requirements of the ASME OM Code, Edition 2004, Subsection ISTD. These requirements will be in lieu of the requirements of the ASME B&PV Code Section XI, 2004 Edition. All the applicable documents at MPS3 should be revised to incorporate the new ASME OM Code ISTD requirements.
Based on the above considerations, the NRC staff concludes that the proposed amendment is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (77 FR 31657). Accordingly, the amendment meets 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 needs to be prepared in connection with the issuance of the amendment.
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) there is reasonable assurance that such activities will be
- 5 conducted in compliance with the Commission's regulations, and {3} the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: G. Bedi Date: February 6, 2013
February 6, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen. VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION UNIT 3 -ISSUANCE OF AMENDMENT RE:
SNUBBER SURVEILLANCE REQUIREMENTS (TAC NO. ME8320)
Dear Mr. Heacock:
The Commission has issued the enclosed Amendment No. 257 to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station. Unit No.3 (MPS3), in response to your application dated April 2, 2012.
The proposed amendment would revise Technical Specification surveillance requirements for snubbers to conform to the MPS3 Snubber Examination, Testing. and Service Life Monitoring Program Plan.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely.
IRA!
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 257 to NPF-49
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC R. Bellamy, RI RidsRgn1 MailCenter RidsNrrDorlLpl1-1 Resource RidsNrrLAKGoldstein Resource RidsNrrDeEptb Resource RidsNrrDorlDpr Resource RidsNrrPMMilistone Resource RidsNrrDssStsb Resource RidsAcrsAcnw_MailCenter RidsOgcRp Resource RidsNrrDirsltsb Resource Accession No.: ML13002A472