ML20059E885
| ML20059E885 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 01/05/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E887 | List: |
| References | |
| NUDOCS 9401130016 | |
| Download: ML20059E885 (8) | |
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iJ,k;j.,i NUCLEAR REGULATORY COMMISSION UNITED STATES (MgJg' f
WASHINGTON, D C 20 % 5-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-280 SURRY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Aroendment No.1B4 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 September 29, 1993, 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 j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable e3quirements have been satisfied.
9401130('6 940105 PDR ADDCK 05000280 P
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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 Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix h, as revised through Amendment No.184, are hereby incorporated in the 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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H bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 5, 1994 i
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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ylBGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 EURRY POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendmen
.40. 184 License No. DPR-37 u
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 29, 1993, complies with the i
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 amendmeat will not be inimical to the common defense and security or to the health and safety of the public;
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i and.
l 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.
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. 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 f acility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Igchnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.184, are hereby incorporated in the 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 icplemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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H
'ert N. Berkow, Director Project Directorate II-2 l
Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 1
Specifications Date of Issuance: January 5, 1994 i
4
r-ATTACHMENT T0 LICENSE AMENDMENT AMENQMENT NO. 1 B4 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 1 84 TO FACILITY OPERATING LICENSE NO.-DPR-37 DOCVET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes 4.2-1 4.2-1 4.2-4 4.2-4 l
4.2-5 4.2-5 9
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TS 4.21 4.2 AUGMENTED INSPECTIONS Acolicability Applies to inservice inspections which augment those required by ASME Section XI.
Objective To provide the additional assurance necessary for the continued integrity of important components involved in safety and plant operation.
Soecifications A.
Inspections shall be performed as specified in TS. Table 4.2-1.
Nondestructive examination techniques and acceptance criteria shall be in j
compliance with the requirements of TS 4.0.5.
B.
The normal inspection interval is 10 yours.
C.
Detailed records of each inspection shall be maintained to allow a continuing evaluation and comparison with future inspections.
Bases The inspection program for ASME Section XI of the ASME Boiler and Pressure Vessel Code limits its inspection to ASME Code Class 1,2, and 3 components and supports, Certain components, under Miscellaneous inspections in thT section, were added because of no corresponding code requirement. This added requirement provides the inspection necessary to insure the continued integrity of these components.
Item 1.4 l
The low pressure turbine rotor blades are normally inspected concurrent with the disk and hub inspections. The disk and hub inspection frequency is based on existing crack size, crack growth rate, and system operating conditions. ASME Section XI does not provide specific examination requirements or acceptance criteria for turbine rotor inspections. Procedures and acceptance criteria for turbine rotor inspections are consistent with general industry practices.
Amendment Nos. 184, 184,
1 TABLE 4.2-1 SECTION A. MISCELLANEOUS INSPECTIONS Required Required Examination Examination Tentative inspection frem No.
Area Methods Durino 10-Year Interval Remarks 1.1 Deleted I
1.2 Lcw Head SIS Visual Non-applicable This pipe shall be visuafy piping located inspected at each refuelirg in valve pit shutdown.
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