ML20056E511
| ML20056E511 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/06/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E512 | List: |
| References | |
| NUDOCS 9308240158 | |
| Download: ML20056E511 (9) | |
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UNITED STATES 1
NUCLEAR REGULATORY COMMISSION l
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t wAswinoTon. o c. 20sss-oooi VIRGINIA ELECTRIC AND POWER COMPANY
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DOCKET NO. 50-280 SURRY POWER STATION. UNIT N0. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.181 i
License No. DPR-32 t
1.
The Nuclear Regulatory Commission (the Commission) has found that:
f A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 21, 1993, complies with the standards and requirements of the Atomic Energy-Act of 1954, as i
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; 1
)
C.
There is reasonable assurance (i) that the activities authorized l
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 j
defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Coriaission's regulations and all applicable requirements have been satisfied.
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A J
P
t 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 i.s hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 181, 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 ierbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance: August 6, 1993
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E UNITED STATES l'
NUCLEAR REGULATORY COMMISSION
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usmNGTON, D.C. 2055N VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-281 JURRY POWER STATION. UNIT N0. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 181 License 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 April 21, 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 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.
)
. 2.
Accordingly, the license is amended by changes to the Technical r
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. 181, 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.
l FOR THE NUCLEAR REGULATORY COMMISSION
- L Her ert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 6, 1993 i
I I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 3.7-7 TS 3.7-7 TS 3.7-8 TS 3.7-8 TS 4.1-9c TS 4.1-9c TS 4.1-9d TS 4.1-9d i
l 1
i TS 3.7-7 steam line pressure setting limit is set below the full load operating pressure.
The safety analysis shows that these settings provide protection in the event of a large steam line break.(3)
Accident Monitoring Instrumentation i
The operability of the accident monitoring instrumentation in Table 3.7-6 1
ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. On the j
pressurizer PORVs, the pertinent channels consist of redundant limit switch indication. The pressurizer safety valves utilize an acoustic monitor channel and a downstream high temperature indication channel. This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Ught Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-
]
l 0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations." Potential accident effluent release paths are equipped with radiation monitors to detect and measure concentrations of noble gas fission products in plant gaseous effluents during and following an accident.
The effluent release paths monitored are the process vent stack, ventilation vent stack, main steam safety valve and atmospheric dump valve discharge and the AFW pump turbine exhaust. These monitors meet the requirements of NUREG 0737.
Instrumentation is provided for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the Waste Gas Holdup System. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50.
Containment Hydrogen Analyzers indication of hydrogen concentration in the containment atmosphere can be provided in the control room over the range of zero to ten percent hydrogen concentration under accident conditions.
These redundant, qualified hydrogen analyzers are shared by Units 1 and 2 with instrumentation to indicate and record the hydrogen concentration. Each
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Amendment Nos.181 and 181
TS 3.7-8 hydrogen analyzer is designed with the capability to obtain an accurate sample within 30 minutes after initiation of safety injection.
A transfer switch is provided for Unit 1 to use both analyzers or for Unit 2 to use both analyzers. In addition, each unit's hydrogen analyzer has a transferable emergency power supply from Unit 1 and Unit 2. This will ensure redundancy for each unit.
Indication of Unit 1 and Unit 2 hydrogen concentration is provided on the Unit 1 Post Accident Monitoring panel and the Unit 2 Post Accident Monitoring panel, l
respectively. Hydrogen concentration is also recorded on qualified recorders.
In addition, each hydrogen analyzer is provided with an alarm for trouble /high hydrogen content. These alarms are located in the control room.
The supply lines installed from the containment penetrations to the hydrogen analyzers have Category l Class IE heat tracing applied. The heat tracing system receives the same transferable emergency power as is provided to the containment hydrogen analyzers. The heat trace system is de-energized during normal system operation. Upon receipt of a SIS, after a preset time delay, heat tracing is energized to bring the piping process temperature to 250 i 10'F.
l Each heat trace circuit is equipped with an RTD to provide individual circuit readout, over-temperature alarm, and control the circuit to maintain the process temperatures.
The hydrogen analyzer heat trace system is equipped with high temperature, j
loss of D.C. power, loss of A.C. power, loss of control power, and failure of automatic initiation alarms.
Non-Essential Service Water Isolation System j
The operability of this functional system ensures that adequate intake canal inventory can be maintained by the Emergency Service Water Pumps.
j Adequate intake canal inventory provides design service water flow to the recirculation spray heat exchangers and other essential loads (e.g., control room area chillers, charging pump lube oil coolers) following a design basis loss of coolant accident with a coincident loss of offsite power. This system is common to both units in that each of the two trains will actuate equipment on each unit.
i Amendment Nos.181 and 181
t TABLE 4.12A (CONTINUED)
MHMUM FREQUENCY FOR EQUIPMENT TESTS l
FSAR SECTION DESCRIPTION TEST FREQUENCY REFERENCE 14a. Service Water System Valves in Functional Each Refuehng Shutdown 9.9 l
Line SupplyinD Recwculation Spray Heal Exchangers b. Serwce Water System Valves Functional Each Relueling Shutdown 9.9 isolahn0 Flow to Non-essential loads on intake Canal Low Levelisolation
- 15. Control Room Ventilation System
- Abilty to maintain positive Each Refueling Shutdown 9.13 l
pressure for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using a volume of air equivalent to or less than stored in the bottled air supply l
16.
Reactor Vessel Overpressure Functional & Setpoint Prior to decreasirg RCS 4.3 k
Mitigatino System (except termerature below 350*F backup air supply) and monthly while the RCS s
is < 350*F and the Reactor Vessel Head is bolted g
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- 17. Reactor Vessel Overpressure Setpoint Each Refueling Shutdown 4.3 r
Manganno System Badop Air Supply 3
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