ML20137D300
| ML20137D300 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1985 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137D302 | List: |
| References | |
| NUDOCS 8601160606 | |
| Download: ML20137D300 (7) | |
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VIRGINIA [LECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 A_MENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (thelicensee)datedAugust9,1985,assupplemented November 8, 1985, 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 Comission; 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 Comission'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 Comission'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 paragrach 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
8601160606 e51231 yDR ADOCM 05000280 PDR
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. (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION GQ Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 31, 1985 e
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NUCLEAR REGULATORY COMMISSION 5
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VIRGINIA ELECTRIC AND POWER COMPANY i
j DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMEhDMENT TO FACILITY OPERATING LICENSE i
Amendment No.105 I
License No. DPR-37 i
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated August 9, 1985, as supplemented November 8, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the l
Comission'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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common 4
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 Comission's regulations and all applicable requirements have been satisfied.
3 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 l
No. DPR-37 is hereby amended to read as follows:
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c (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
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Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: December 31, 1985 s
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 105 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 105 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET N05. 50-280 AN9 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages TS 3.1-18 TS 3.1-18 3.1-19 3.1-19 1
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TS 3.1-18 E.
Minimum Temperature for Criticality Specifications 1.
Except during low power physics tests, the reactor shall not be made critical at any temperature above which the moderator temperature coefficient is more positive than:
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a.
+ 3 pen /*F at less than 50% of rated power, or b.
+ 3 pcm/'F at 50% of rated power and linearly decreasing to O pcm/*F at rated power.
2.
In no case shall the reactor be made critical with the reactor coolant temperature below DTT + 10*F, where the value of DTT 1
+ 10*F is as determined in Part B of this specification.
3.
When the reactor coolant temperature is below the minimum temperature as specified in E-1 above, the reactor shall be suberitical by an amount equal to or greater than the potential reactivity insertion due to primary coolant depressurization.
4.
The reactor shall not be made critical when the reactor coolant temperature is below 522'F.
l Basis l
During the early part of a fuel cycle, the moderat'or temperature coefficient may be calculated to be slightly positive at coolant temperatures in the power operating range.
The moderator coeffi-cient will be most positive at the beginning of cycle life, when the boron concentration in the coolant is the greatest.
Later in the cycle, the boron concentration in the coolant will be lower and the moderator coefficient will be less positive or will )e negative in
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the power operating range. At the beginning of cyc14 life, during pre-operational phycies tests, measurements are made to determine that the moderator coefficient is less than + 3 pcm/*F in the power operating range.
Amendment No. 105
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TS 3.1-19
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The requirement that the reactor is not to be made critical when the moderator coefficient is greater than + 3 pcm/*F has been impose'd to j
prevent any unexpected power excursion during normal operations as a result of either an increase of moderator temperature or. decrease of coolant pressure.
This requirement is waived during low power physics test to permit measurement of reactor moderator coefficient and other physics design parameters of interest.
During physics tests, special operation precautions will be taken.
In addition, the strong negative Doppler coefficient (2)(3) and the small integrated Delta k/k would limit the magnitude of a power excursion resulting from a reduction of moderator density.
The requirement that the reactor is not to be made critical with a reactor coolant temperature below DTT + 10*F provides increased assurance that the proper relationship between reactor coolant pressure and temperature will be maintained during system heatup and pressurisation whenever the reactor vessel is in the nil ductility transition temperature range.
Bestup to this temperature is accomplished by operating the reactor coolant pumps.
The requirement that the reactor is not to be made critical with a reactor coolant temperature below 522*F provides added assurance that the assumptions made in the safety analyses remain bounding by maintaining the moderator temperature within the range of those analyses.
If a specified shutdown reactivity margin is maintained (TS Section 3.12), there is no possibility of an accidental criticality as a result of an increase of moderator temperature or a decrease of coolant pressure.
(1) FSAR Figure 3.3-8' (2) FSAR Table 3.3-1 (3) FSAR Figure 3.3-9 I
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Amendment No.105
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