ML20064C674
| ML20064C674 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/07/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064C675 | List: |
| References | |
| NUDOCS 9403100158 | |
| Download: ML20064C674 (11) | |
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION i
j WASHINGTON, D.C. 20566-0i90' VIRGINIA ELECTRIC AND POPER COMPANY DOCKET _.NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the 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 (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 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.
9403100158 940307 PDR ADOCK 05000280 p
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 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.190, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
0 3.
This license amendment is effective as of its date of issuanto c"th:11 be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 7, 1994 e
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UNITED STAYES j.'iq L[. 5j NUCLEAR REGULATORY COMMISSION -
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WASHINGTON, D.C. 7/2 001
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DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. DPR-37 1.
ihe Nuclear Regulatory Commission (the Commissicn) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 10, 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 compliarce with the Commission's regulations; D.
The issuance of thh 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.
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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 SDecifications
-The Technical Specifications contained in Appendix A, as revised through Amendment No.190, 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 II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attacht ent; Char.ge', to the Technical
'ipecifications Date of Issuance: March 7, 1994 l
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ATTACHMENT TO LICENSE AMENDMENT AME;;DMENT NO.
190 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.
190 TO FACILITY OPERATING LICENSE NO. DPR-37
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DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 1.0-8 TS 1.0-8 TS 1.4-9d TS 4.1-9d TS 4.8-1 TS 4.8-1 TS 4.8-2 TS 4.8-2 TS 4.8-3 TS 4.8-3 TS 4.8-4
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STAGGERED TEST BASIS l
l A staggered test basis shall consist of:
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a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
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TS 4.8-1 4.8 AUXILIARY FEEDWATER SYSTEM Acolicability i
Applies to the periodic testing requirements of the Auxiliary Feedwater System, i
Objective To verify the operability of the auxiliary feedwater pumps.
l Soecification A.
Tests and Frecuencies l
1.
At least once per 31 days:
I Verify that the Auxiliary Feedwater System manual, power a.
operated, and automatic valves in each flow path are in the l
correct position. This verification includes valves that are not locked, sealed, or otherwise secured in position, valves in the the cross-connect from the opposite unit and valves in the steam supply paths to the turbine driven auxiliary feedwater pump.
2.
At least once per 92 days:
Verify that each motor-operated valve in the auxiliary i
a.
feedwater flow paths, including the cross-connect from the opposite unit, performs satisfactorily when tested in accordance with Specifications 4.0.5.
3.
At least once per 92 days on a STAGGERED TEST BASIS:
Verify that the auxiliary feedwater pumps perform a.
satisfactorily when tested in accordance with Specification 4.0.5.
The provisions of Specification 4.0.4 are not applicable for the turbine driven pump.
j Amendment Nos.190 and 190
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TS 4.8-2 4a.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to Reactor Coolant System Nmperature and pressure exceeding 350*F and 450 psig, respectively, the motor driven auxiliary feedwater pumps shail be flow tested from the 110,000 gallon above ground Emergency Condensate Storage Tank to the steam generators.
4 b.
Wthin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving reactor criticality, the steam turbine driven auxiliary feedwater pump shall be flow tested from the 110,000 gallon above ground Emergency Condensate Storage Tank to the steam generators. The provisions of Specification 4.0.4 are not applicable.
5.
During periods of reactor shutdown with the opposite unit's Reactor Coolant System temperature and pressure greater than 350 F and 450 psig, respectively:
a.
Continue to verify that the motor driven auxiliary feedwater cumps perform satisfactorily when tested at the frequency defined in Specification 4.8.A.3.
b.
Verify that each motor-operated valve in the auxiliary feedwater cross connect flow path for the opposite unit performs satisfactorily when tested in accordance with Specifications 4.0.5.
B.
Acceotance Criteria The pump and valve tests, except the system flow test, shall be considered satisfactory if they meet the ASME Section XI inservice Testing Program acceptance criteria.
l The system flow tests during unit startup from COLD SHUTDOWN or REFUELING SHUTDOWN shall be considered satisfactory if the control board indication demonstrates that flow paths exist to each steam generator.
Amendment Nos.190 and 190
T S 4.8-3 U
1 The correct alignrnent for manuej, power operated, and automatic valves in the Auxiliary Fesd.vator Systern steam and water flow paths, loduding the cross-
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connect flow path, wi!! provide essurance that the proper flow pmhs exist for system operation. This oosition check does not include: 1) valves that are locked, sealed or ciherwise secured in position since they are verified to be in their correct position prior to locking, sealing or otherwise securing; 2) vent, drain or relief valves on those flow paths; and, 3) those valves that cannot be inadvertently misaligned such as check valves. This surveillance does not require any testing or valve madpulation. It involves verification that those valves capable of being mispositioned are in the correct position.
The auxiliary feedwater pump will be tested periodically in accordance with ASME Section XI to demonstrate operability. The pumps are flow tested on recirculation to the 110,000 gallon Emergency Condensate Storage Tank.
Valves in the flow path to the steam generators and cross-connect flow path are tested periodically in accordance with ASME Section XI.
l The auxiliary feedwater pumps are capable of supplying feedwater to the opposite units steam generators. For a main steam line break or fire event in the Main Steam Valve House, one of the opposite units auxiliary feedwater pumps is required to supply feedwater to mitigate the consequences of those accidents.
4 l
Therefore, when considering a single failure, both motor driven auxiliary
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feedwater pumps are required to be OPERABLE
- during shutdown to support the 1
opposite unit if the Reactor Coolant System temperature or pressure of the opposite unit is greater than 350*F and 450 psig, respectively. Thus, to establish i
operability
- the motor driven auxiliary feedwater pumps will continue to be tested l
quarterly on the same STAGGERED TEST BASIS when the unit is shutdown to support the opposite unit. The turbine driven pump is not required to be OPERABLE when the unit is shutdown and therefore, is not tested during periods of shutdown.
- excluding automatic initiation instrumentation Amendment Nos.190 and 190
TS 4.8-4 l i
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The capacity of the Emergency Condensate Storage Tank and the flow rate of j
any one of the three auxiliary feedwater pumps in conjunction with the water j
inventory of the steam generators is capable of maintaining the plant in a safe l
condition and sufficient to cool the unit down.
i i
Proper functioning of the steam turbine admission valve and the ability of the auxiliary feedwater pumps to start will demonstrate the integrity of the system. l Verification of correct operation can be made both from instrumentation within the j
Main Control Room and direct visual observation of the pumps.
1 i
j Referenqes
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UFSAR Section 10.3.1 Main Steam System
]
UFSAR Section 10.3.2 Auxiliary Steam System I
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4 4
Amendment Nos.190 and 199 l
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