ML081960324

Millstone Technical Specifications to Amedment 304/Unit 2

ML081960324
Person / Time
Site:	Millstone
Issue date:	07/31/2008
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Sanders, Carleen, NRR/DORL 415-1603
Shared Package
ml081960318	List: ML081960312 ML081960324 ML082130702
References
TAC MD6113, TAC MD6114
Download: ML081960324 (3)

Text

-3-Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license;(2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for'storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts thermal.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.304 , are hereby incorporated in the renewed license.The licensee shall operate the facility in accordance with the Technical Specifications.

Renewed License No. DPR-65 Amendment No. 304 APPLICABILITY:

SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 Surveillance Requirements for inservice testing of ASME Code Class 1, 2 and 3 components shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) as follows: a. Deleted.b. Surveillance intervals specified in the ASME OM Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME OM Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually Biennially or every 2 years Required frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days At least once per 731 days c. The provisions of Specification 4.0.2 are applicable to the above required frequencies and to other normal and accelerated frequencies specified as 2 years or less in the inservice testing program for performing inservice testing activities.

d. Performance of the above inservice testing activities shall be in addition to other specified Surveillance Requirements.

e. Nothing in the ASME OM Code shall be construed to supersede the requirements of any Technical Specification.

f. The provisions of Specification 4.0.3 are applicable to inservice testing activities.

MILLSTONE

-UNIT 2 3/4 0-3 Amendment No. 6-2, 0, 4-64-, -152, 2-3-0, 24-1-, 27-1-, 304 PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.

The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on whichthey 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 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 4.7.8.d on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for the system.SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of the Inservice Inspection Program.a. Inspection Types As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.b. Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation.

Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-3. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-3 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 160.c. Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type MILLSTONE

-UNIT 2 3/4 7-21 Amendment No. 44, 4-1, 52, 96, 44-8, 4-6W,304