ML20044E023
| ML20044E023 | |
| Person / Time | |
|---|---|
| Site: | Surry  (DPR-32-A-178, DPR-37-A-178) |
| Issue date: | 05/17/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044E024 | List: |
| References | |
| NUDOCS 9305210196 | |
| Download: ML20044E023 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION l
'2 WASHINGTON, D.C. 2066EM1001 I
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VIRGINIA ELECTRIC AND POWER COMPANY i
DOCKET N0. 50-280 j
SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.178 License No. OPR-32 l
i 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 10, 1992, complies with the standards and requirements of the Atoinic Energy Act of 1954, as
- i amended (the Act) and the Commission's rules and regulations set j
forth in 10 CFR Chapter 1 B.
The facility will operate in confonnity with the application,- the provisions of the Act, and the rules and regulations of~the t
Commission-j 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;
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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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9305210196 930517 i
PDR ADOCK 05000280 P
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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 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. 178, 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 f
H rbert N. Berkow, Director Project Directorate Il-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
I Changes to the Technical Specifications Date of Issuance: May 17, 1993 r
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION l
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WASHINGTON. D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY-i i
DOCKET N0. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 178' License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application!for amendment by Virginia Electric and Power Company (the licensee) dated hovember 10, 1992, complies with the-standards and requirements of the Atomic Energy Act of 1954, as
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amended (the Act) and the Commission's rules and regulations set i
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 (1) 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 comon 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.
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1
. 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-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, 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 Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 17, 1993 i
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 178 TO FACILITY OPERATisG LICENSE NO. DPR-32 AMEi>{Q5ENT NO. 178 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3.14-2 3.14-2 3.14-2a 3.14-3 3.14-3 5
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TS 3.14-2 5.
Two service water flow paths to the charging pump service water subsystem are OPERABLE.
6.
Two service water flow paths to the recirculation spray subsystems are OPERABLE.
B.
The requirements of Specification 3.14.A.4 may be modified to allow one Emergency Service Water pump to remain inoperable for a period not to exceed 7 days. If this pump is not OPERABLE in 7 days, then place both units in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The requirements of 3.14.A.4 may be modified to have two Service Water pumps OPERABLE with one unit in COLD SHUTDOWN with combined Spent Fuel pit and shutdown unit decay heat loads of 25 million BTU /HR or less. One of the two remaining pumps may be inoperable for a period not to exceed 7 days. If this pump is not OPERABLE in 7 days, then place the operating unit in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C.
There shall be an operating service water flow path to and from one operating main control and emergency switchgear rooms air conditioning condenser and at least one OPERABLE service water flow path to and from at least one OPERABLE main control and emergency switchgear rooms air conditioning condenser whenever fuel is loaded in the reactor core. Refer to Section 3.23.C for air conditioning system operability tequiremen'.s above COLD SHUTDOWN.
D.
The requirements of Specifications 3.14.A.5, 3.14.A.6, and 3.14.C may be modified to allow unit operation with only one OPERABLE flow path to the charging pump service water subsystem, the recirculation spray subsystems, and to the main control and emergency switchgear rooms air conditioning condensers.
If the.
affected systems are not restored to the requirements of Specifications 3.14.A.5, 3.14.A.6, and 3.14.C within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Amendment Nos.178 and 178
TS 3.14-3 i
the reactor shall be placed in HOT SHUTDOWN. If the requirements of Specifications 3.14.A.5, 3.14.A.6, and 3.14.C are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in COLD SHUTDOWN.
I i
Basis l
1 The Circulatirig and Service Water Systems are designed for the removal of heat resulting from the operation of various systems and components of either or both of the units. Untreated water, supplied from the James River and stored in the high level intake canal is circulated by gravity through the recirculation spray coolers and the bearing cooling water heat exchangers and to the charging pumps lubricating oil cooler service water pumps which supply service water to the charging pump lube oil coolers.
In addition, the Circulating and Service Water Systems supply cooling water to the component cooling water heat exchangers and to the main control and j
emergency switchgear rooms air conditioning condensers. The Component Cooling heat exchangers are used during normal plant operations to cool various station components and when in shutdown to remove residual heat from the reactor. Component Cooling is not required on the accident unit during a loss-of-coolant accident. If the loss-of-coolant accident is coincident with a loss of off-site power, the nonaccident unit will be maintained at HOT SHUTDOWN with the ability to reach COLD SHUTDOWN.
The long term Service Water requirement for a loss-of-coolant accident in one unit with simultaneous loss-of-station power and the second unit being brought to HOT SHUTDOWN is greater than 15,000' gpm. Additional Service Water is necessary to bring the nonaccident unit to COLD j
SHUTDOWN. Three diesel driven Emergency Service Water pumps with a design capacity of 15,000 gpm each, are provided to supply water to the 1
High Level Intake canal during a loss-of-station power incident.
- Thus, considering the single active failure of one pump, three Emergency Service Water pumps are required to be OPERABLE. The allowed outage time of 7 days provides operational flexibility to allow for repairs up to and Amendment Nos.178 and 178