ML20076K721
| ML20076K721 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/27/1994 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076K724 | List: |
| References | |
| NUDOCS 9411020030 | |
| Download: ML20076K721 (8) | |
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i UNITED STATES j
j NUCLEAR REGULATORY COMMISSION r
WASHINGTON, D.C. 20666-0001 h
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ylRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.193 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated October 19, 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 1
l 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.
9411020030 941027 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. 193, 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 Mohan C. Thadani, Acting Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Isstlance: October 27, 1994 1
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UNITED STATES g
S NUCLEAR REGULATORY COMMISSION E
If WASHINGTON, D.C, 20665-0001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 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 October 19, 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'heaith 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 Commiscion'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 paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Techni.1 Specifications contained in Appendix A, as revised through Amendment No.193, 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 C
Mohan C. Thadani, Acting Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 27, 1994
l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 193 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 193 TO FACILITY OPERATING LICENSE NO. DPR-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 3.7-29 TS 3.7-29 TS 4.1-9a TS 4.1-9a
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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) j Accident Monitoring instrumentation The operability of the accident monitoring instrumentation in Table 3.7-6 ensures that sufficient information is available on selected plant parameters to monitor and assess 1
these variables during and following an accident. On the pressurizer PORVs, the _
pertinent channels consist of redundant limit switch indication. The pressurizer safety J
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 Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term
(
Recommendations." Potential gaseous effluent release paths are equipped with radiation monitors to detect and measure concentrations of noble gas fission products j
in plant gaseous effluents during and following an accident. The gaseous 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. The potential liquid effluent re ease paths via the service water discharge from the recirculation spray heat exchangers are equipped with radiation monitors to detect leakage of recirculated containment sump fluid. These radiation monitors and the associated sample pumps are required to operate during the recirculation heat removal phase following a loss of coolant accident in order to detect a passive failure of a recirculation spray heat exchanger tube. 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 analyzers are shared by Units 1 and 2 with instrumentation to indicate and record the hydrogen concentration. Each Amendment Nos.193 and 193
TABLE 3.7-6 ACCIDENT MONITORING INSTRUMENTATION in ts rumert Total No. Of Channels Minimum OPERABLE Channels 1.
Auxiliary Feedwater Flow Rate 1 per S/G 1 per S/G 2.
Inadequate Core Cooling Montor a.
Reactor Vessel Coolant Level Monitor 2
1
- b. Reactor Coolant System Subcooling Margin Monitor 2
1
- c. Core Exit Thermocouples 2 (Note 2) 1 (Note 2)
~
3.
PORV Position Indicator 2Nalve 1 Naive 4.
PORV Block Valve Position Indicator 1 Naive 1 Naive 5.
Safety Valve Position Iruncator (Primary Detector) 1 Naive 1Nalve I
6.
Safety Valve Postion Indicator (Backup Detector) 1Nalve 0
7.
Containment Pressure 2
1 8.
Containment Water Level (Narrow Range) 2 1
1 9.
Containment Water Level (Wide Range) 2 1
- 10. Containment High Range Radiation Morntor 2
1 (Note 1,b and c only) y 3g
- 11. Process Vent High Range Effluent Monitor 2
2 (Note 1, a, b, and c) o.3
- 12. Ventilation Vent High Range Effluent Monitor 2
2 (Note 1, a, b, and c)
- 13. Main Steam High Range Radiation Monitors (Units 1 and 2) 3 3 (Note 1, a, b, and c) h
- 14. Aux. Feed Pump Steam Turbine Exhaust Radiation Monitor 1
1 (Note 1, a, b, and c) i
- 15. Recirculation Spray Heat Exchanger Service Water Outlet Radiation Monitors 1 per RSHX 1 per RSHX (Note 1, a, b, and c) l E
Note 1: With the number of operable channels less than required by the Mirumum OPERABLE Channels requirements
- a. Initiate the preplanned attemate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> y
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- b. Either restore the inoperable channel to operable status wthin 7 days of the event, or
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c.
Prepare and sutmt a Special Report to the commesion pursuant to specification 6.2 within 30 days following the event 9
outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable y
Note 2: A mirumum of 2 core exit thermocouples per quadrant are required for the channel to be operable.
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9 TARLE 41-2 AOCIDELLT_MQNITORINQltiSJTJMMEtlTATION SURVFJLLANCE REQUIREMENTb CHANNEL CHANNEL FUNCTIONAL CHANNEL JMSTRUMENT
_ CHECK TEST CAllBRATlON 1.
Auxiliary Feedwater Flow Rate P
R 2.
Inadequate Core Cooling Monitor M
R 3.
PORV Position Indicator (Primary Detector)
M R
4 PORV Position Indicator (Backup Detector)
M R
5.
PORV Block Valve Position Indicator M
R G.
Safety Valve Position Indicator M
R 7.
Safety Valve Position Indicator (Backup Detector)
M R
8.
Containment Pressure M
R 9.
Containment Water Level (Narrow Range)
M R
10.
Containment Water Level (Wide Range)
M R
11.
Containment High Range Radiation Monitor M
O R
3 m
12.
Process Vent High Range Effluent Monitor M
Q R
13.
Ventilation Vent High Range Effluent Monitor M
O R
- 3 14 Main Steam High Range Radiation Monitor M
O R
g 15.
Auxiliary Feedwater Pump Turbine Exhaust Radiation Mortitor M
O R
16.
Recirculation Spray Heat Exchanger Service Water Outlet M
O(1)
R Radiation Mraitors w
{
(1) Channel Functional testing shall include the associated sample pump.
g M - Monthly M
P - Prior to each startup if not done within the previous week w
O - Quarterly
-3 m
R - Refueling 6
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