ML20249B823
| ML20249B823 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/19/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249B824 | List: |
| References | |
| NUDOCS 9806240273 | |
| Download: ML20249B823 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 i
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 5,1997, as supplemented January 28,1998, and May 12,1998, 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 satisfugl.
m oo273 9eo619 ADOCK O go gDR
i 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 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. 214, are hereby incorporated in the license. The licensee i
shall operate the facility in accordance with the Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
~
o-Tsin Kuo, Acting Director roject Directorate ll-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: June 19,1998 y
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UNITED STATES p
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wAsnimoTow, o.c. soses.coes NUCLEAR REGULATORY COMMISSION VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
l Amendment No. 214 l
Ucense 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 5,1997, as supplemented January 28,1998, and May 12,1998, 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 I
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.
l
- l 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 Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications l
l The Technical Specifications contained in Appendix A, as revised through Amendment No. 214, 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 P -Tsin Kuo, Acting Director P ect Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
June 19,1998 6
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ATTACHMENTTO LICENSE AMENDMENT AMENDMENT NO. 214 TO FACjkfTY OPERATnNG LICENSF NO. DPR-32 AMENDMENT NO. 214 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paoes y,.M Paoes TS 5.3-2 TS 5.3-2 TS 5.4-2 TS 5.4-2 TS Figure 5.4-1 TS Figure 5.4-1
l TS 5.3-2
- 3. Reload fuel will be similar in' design to the initial core. The enrichment of reload fuel will not exceed 4.3 weight percent of U-235.
l
- 4. Burnable poison rods are incorporated in the initial core. There are 816 poison rods in the form of 12 rod clusters, which are located in vacant control rod assembly guide thimbles. The burnable poison roos consist of pyrex clad with stainless steel.
- 5. There are 48 full-length control rod assemblies in the reactor com. The full-length control rod assemblies contain a 144-inch length of silver-indium-cadmium alloy clad with stainless s ect.
- 6. Surry Unit 1, Cycle 4, Surry Unit 2, Cycle 3, and subsequent cores will meet the following criteria at all times during the operation lifetime.
- a. Hot channel factor lunits as specified in Section 3.12 shall be met.
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l Amendment Nos. 214 and 214
s.
TS 5.4-2 sr.semblies to ensure k,g s 0.95, even if unborated water were used to fill the spent fuel l
storage pit. The spent fuel pool is divided into a two-region storage pool. Region 1 comprises the first three rows of fuel racks (324 storage locations) adjacent to the Fuel Building Trolley Load Block. Region 2 comprises the remainder of the fuel racks in the fuel' pool. During spent fuel cask handling, Region 1 is limited to storage of spent fuel assemblies which have decayed at least 150 days after discharge and shall be restricted to l
those assemblies in the " acceptable" domain of Figure 5.4-1. Administrative controls with written procedures will be employed in the selection and placement of these assemblies.
The enrichment of the fuel stored in the spent fuel racks shall not exceed 4.3 weight l
percent of U-235.
C.
Whenever there is spent fuel in the spent fuel pit, the pit shall be filled with borated water r:. boron concentration not less than 2300* ppm to match that used in the reactor cavity and refueling canal during refueling operations.
D.
The only drain which can be connected to the spent fuel storage area is that in the reactor cavity. The strict step-by-step procedures used during refueling ensure that the gate valve on the fuel transfer tube which connects the spent fuel storage area with the reactor cavity is closed before draining of the cevity commences. In addition, the procedures require placing the bolted blank flange on the fuel transfer tube as soon as the reactor cavity is drained.
This limit takes effect at the time the Unit 2 reactor cavity is flooded following the end of Operating Cycle 10.
References FSAR Section 9.5 Fuel Pit Cooling System FSAR Section 9.12 Fuel Handling System Amendment Nos. 214 and 214
T.S. Figure 5.4-1 35000 2250, ppm Eoron in PoolWatar
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25000 K<0.05 Region:
Acceptable Region
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Unacceptable Region i
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5000 l
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0 1.9 2.1 2.3 2.5 2.7 2.9 3.1 3.3 3.5 3.7 3.9 4.1 4.3 initial Fuel Enrichment (wlo U 235)
FIGURE 5.4-1 MINIMUM FUEL EXPOSURE VERSUS INITIAL ENRICHMENT TO PREVENT CRITICALITY IN DAMAGED RACKS Amendment Nos.214 and 214 l
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