ML20246K175
| ML20246K175 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/28/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246K180 | List: |
| References | |
| NUDOCS 8909050397 | |
| Download: ML20246K175 (9) | |
Text
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,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The cyplication for amendment by Virginia Electric and Power Company (the licensee) dated April 6,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules ano regulations set forth in 10 CFR Chapter I; B.
The facility will cperate 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 anendnent 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 anenonent will not be inimical to the comon defense end 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, ano paragraph 3.B of Facility Operating License i
No. DPR-32 is hereby anended to read as follows:
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-2 (B) Technical Specifications The Technical Specifications contained in Appendix A.
.as revised through Anendment No.132_, are hereby incorporated in the license. The licensee shall-y
. operate the facility in accordance with the Technical Specificaticas.
1 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0le!SSION
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rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Speci fica tions Date of Issuance: ' August 28, 1989 1
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VIRGINIA ELECTPIC AND POWER COMPANY DOCKET NO. 50-281 SUPRY POWER STATION, UNIT NO. 2
, AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 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 license () dated April 6,1989, 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 '
CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules anc 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 witn the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon H
defense and security or to the health and safety of the public; and E.
The issuance of this amennment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license L
amenament, and paragraph 3.B of facility Operating License No. DPR-37 is hereby anended to read as follows:
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., (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.132, 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 M
h Herbert N. Berkow, Director Project Directorate 11-2 Division of Reector Projects-I/II-Office of Nuclear Reactor Regulation Attachu Changes
.e Teichnical Specifications Date of Issuance: August 28, 1989 l
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'l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.132 FACILITY OPERATlhG LICENSE NO. DPR-32 AMENDMENT NO. 132 FACILITY OPERATING LICENSE N0. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appencix A as follows:
Remove Pages Insert Pages TS 4.5-2 TS 4.5-2 TS 4.5-3 TS 4.5-3 TS 4.5-4 TS 4.5-4 TS'4.11-2 TS 4.11-2
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-TS 4.5-2 y
2.
By ' verifying that each motor-operated valve in the recirculation spray flow paths performs satisfactorily when tested in accordance with Specification 4.0.3.
3.
At least once per 5 years, coincident with the closest refueling outage, by performing on air or smoke flow test and verifying each spray nozzle is unobstructed.
C.
Each' weight-loaded check valve in the containment spray and outside containment recirculation spray subsystems shall be. demonstrated operable > at least once per 18 months, during shutdown, by cycling the valve one complete cycle of full travel and verifying that each valve opens when the discharge line of the pump is pressurized with air-and seats when a vacuum is applied.
D.
A visual inspection of the containment-sump and the inside containment recirculation spray pump wells and the-engineered safeguards suction inlets shall be performed at least once each refueling period ~ and/or after major maintenance activities in the
. containment. The~ inspection should verify that the containment sump and pump wells are free of debris that could degrade system operation and that the sump components (i.e., trash racks, screens) are properly installed and show no sign of structural distress or excessive corrosion.
Basis The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank.
The containment spray pump is operated and a quantity of water recirculated to the refueling water storage tank.
The discharge to the tank is divided into two fractions; one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are identical with those used in the containment spray headers.
The purpose of the recirculation through the test nozzles is to assure that there are no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles.
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TS 4.5-3 l
Due to the physical arrangement of the recirculation spray pumps inside I
the containment, it is impractical to flow-test them other than on a.
refueling outage frequency.
Flow testing of these. pumps requires the physical modification of the pump discharge piping and the erection of :.
l temporary dike to contain recirculated water.
The length of time required to setup for the test, perform the test, and then reconfigure the system for normal operation is prohibitive to performing the flow-test on even the cold shutdown frequency.
Therefore. the flow-test of the inside containment recirculation spray pumps will be performed on a refueling outage frequency.
The inside. containment recirculation spray pumps are capable of being operated dry -for. approximately 60 seconds without-significantly overheating and/or degrading the pump bearings.
During this dry pump check, it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Control Room.
in addition, motor current will be compared with an establit,hed reference value to ascertain that no degradation of pump operation has occurred. The inside recirculation spray pumps are removed and inspected periodically to verify the mechanical condition of the pumps.
The. recirculation spray pumps outside the containment have the capability of being dry-run and flow tested.
The test of an outside recirculation spray pump is performed by closing the containment sump suction line valve and the isolation valve between.the pump discharge and the containment penetration.
This allows the pump casing to be filled with water and the pump to recirculate water through a test line from the pump discharge to the pump casing.
With a system flush conducted to remove particulate matter prior to the installation of spray nozzles and with corrosion resistant nozzles and piping, it is not considered credible that a significant number of nozzles would plug during the life of the unit to reduce the effectiveness of the subsystems; therefore provisions to air-test the nozzles every 5 years, coinciding with the closest refueling outage, is sufficient to indicate that plugging of the nozzles has not occurred.
Amendment Nos.132 and 132
e TS 4.5-4 The spray l nozzles in the refueling water storage tank provide means to.
I ensure that there is no particulate matter in the refueling water storage
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tank and the containment spray subsystems which could plug or cause-deterioration - of the spray nozzles.
The nozzles in the tank are identical to those used on the containment spray headers.
The flow test of the containment spray pumps and recirculation to the refueling water storage will indicate any plugging of-the nozzles-by a. eduction of flow through the nozzles.
Performing the containment sump and pump well. inspections will reduce the potential for system degradation due to sump debris associated with refueling activities or major maintenance activities as well as reduce wear on the inside containment recirculation spray pumps during dry testing.
Ensuring proper installation and structural integrity of' the trash racks and sump screens will prevent ingress of debris generated-during the DBA and will allow long term containment cooling and
' recirculation mode cooling of the core.
References FSAR Section 6.3.1, Containment Spray Pumps FSAR Section 6.3.1, Recirculation Spray Pumps I-l l
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Amendment Nos.132 and 132
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.Ti TS 4.11-2 Verifying, by visual inspection, that each low head safety c.
. injection pump suction inlet from the containment sump is free of debris that could' degrade system operation.
Perform each refueling outage and/or after major maintenance activities in the containment.
Basis Complete system tests cannot be performed. when the reactor is operating because a safety injection signal causes containment isolation.- The method of assuring operability of these systems is therefore to combine system ' tests to be performed during refueling shutdowns, with more frequent component
- tests, which can be performed during ' reactor operation.
The. system. tests demonstrate proper automatic operation of. the Safety Injection System.
A test signal is applied to initiate automatic operation action and verification is made that the components receive the safety injection signal in the proper sequence.
The test may be performed with the pumps blocked from. starting.
The test demonstrates the operation of the valves, pump circuit breakers, and automatic circuitry.-
During reactor operation, the instrumentation which is depended on to initiate safety injection is checked periodically, and the initiating circuits are tested in accordanre with Specification 4.1.
In addition, the active components (pumps and valves) are to be periodically tested to l
check the operation of the starting circuits and to verify that the pumps are in satisfactory running order.
The test interval is determined in accordance with ASME Section XI.
The accumulators are a passive safeguard.
In accordance with Specification 4.1, the water volume and pressure in the accumulators are checked periodically.
References FSAR Section 6.2, Safety Injection System i
Amendment Nos. 132 and 132
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