ML20148F666
| ML20148F666 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/01/1997 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148F671 | List: |
| References | |
| NUDOCS 9706040305 | |
| Download: ML20148F666 (8) | |
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4 UNITED STATES NUCLEAR REGULATORY COMMISSION N
f WASHINoTON, D.C. 20666-0001
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 24, 1997, as supplemented on May 31, 1997, 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; 1
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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
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9706040305 970601 PDR ADOCK 05000454 1
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Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 90 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and i
the Environmental Protection Plan.
1 3.
This license amendment is effective as of the date of its issuance and l
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shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION kNO0W Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 1, 1997
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 90 FACILITY OPERATIfG LICENSE NO. NPF-37 DOCKET NO. STN 50-414 j
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paoes 3/4 5-4 3/4 5-4 3/4 5-4a 3/4 5-4b B 3/4 5-2 B 3/4 5-2 3 3/4 5-2a i
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' EMERGENCY CORE COOLING SYSTEMS 2
- SURVEILLANCE REQUIREMENTS
[ INTENTIONALLY LEFT BLANK]
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BYRON - UNITS 1 & 2 3/4 5-4 AMENDMENT NO. 90
EMERGENCY CORE COOLING SYSTEMS
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SVRVEILLANCE RE0VIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position MOV SI8806 Suction to the SI Open i
Pumps MOV SI8835 SI Pump Discharge Open*
To RCS Cold Legs H0V SI8813 SI Pump Recirculation Open To The RWST MOV SI8809A RHR Pump Discharge to Open*
RCS Cold Legs MOV SI88098 RHR Pump Discharge to Open*
RCS Cold Legs MOV SI8840 RHR Pump Discharge to Closed RCS Hot Legs MOV SI8802A SI Pump Discharge to Closed RCS Hot Legs MOV SI8802B SI Pump Discharge to Closed RCS Hot Legs b.
For Unit 1, through Cycle 8, at least once per 31 days by:
l 1)
Venting the pump casings and discharge piping high point vent valves outside of contair. ment (applicable to idle Rh and SI systems only), and E)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position (applicable to CV, RH, SI systems).
l 3)
Verifying the CV system is full of water by ultrasonically examining the discharge portion of the idle CV pump up to the discharge check valve and the stagnant portion of the piping upstream of the ISI8801A and B of the 151045 valve (applicable to CV system only).
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall i
~be performed:
- Valves may be realigned for testing pursuant to Specification 4.4.6.2.2.
BYRON - UNIT 1 3/4 5-4a AMENDMENT N0.90
EMERGENCY CORE COOLING SYSTEPi1
' SURVEILLANCE RE0VIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators
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removed:
Valve Number Valve Function Valve Position MOV SI8806 Suction to the SI Open Pumps MOV SI8835 SI Pump Discharge Open*
To RCS Cold Legs MOV SI8813 SI Pump Recirculation Open To The RWST M0V SI8809A RHR Pump Discharge to Open*
RCS Cold Legs MOV SI8809B RHR Pump Discharge to Open*
RCS Cold Legs M0V SI8840 RHR Pump Discharge to Closed RCS Hot Legs MOV SI8802A SI Pump Discharge to Closed RCS Hot Legs MOV S18802B SI Pump Discharge to Closed RCS Hot Legs i
b.
At least once per 31 days by:
1)
Venting the ECCS pump casings and discharge piping high points outside of containment., and i
2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
- Valves may be realigned for testing pursuant to Specification 4.4.6.2.2.
BYRON - UNIT 2 3/4 5-4 b AMENDMENT N0.90
EMERGENCY CORE COOLING SYSTEMS
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BASES ECCS SUBSYSTEMS (Continued) i i
i The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE Charging pump to be inoperable in MODE 4 with one or j'
more of the RCS cold legs less than or equal to 330*F, MODE 5, and MODE 6 with the reactor vessel head on, provides assurance.that a mass addition pressure l
transient'can be relieved by the operation of a single PORV or RHR suction relief valve. Similarly, the requirement to verify all Safety Injection pumps are inoperable in MODE 4 with the temperature of one or more of the RCS Cold Legs less than or equal to 330*F, in MODE 5 with pressurizer level greater than 5 percent (Level 409.5') and in MODE 6 with pressurizer level greater than 1
5 percent and the reactor vessel head resting on the reactor vessel flange, provides assurance that a mass addition pressure transient can be relieved by a single PORV or RHR suction relief valve.
In MODE 5 and MODE 6 with pressurizer level less than or equal to 5 percent, at least one. Safety Injection pump or gravity feed from the RWST must be available to mitigate the effects of a loss of decay heat removal during partially drained conditions.
Surveillance requirements assure availability, but prevent inadvertent actuation during these modes. The desired flow path for the SI pump or gravity feed varies with RCS configuration and is, therefore, procedurally addressed.
The Surveillance Requirements define what constitutes an adequate bot side vent for various plant conditions.
It was determined that removing the' reactor vessel head was an adequate vent under all conditions. Other venting alterna-tives have restrictions based on time from shutdown and RCS temperature. The values in the surveillance were taken from the graph on page B 3/4 5-3.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
Surveillance Requirements for throttle valve position stops and flow balance-testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.
Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance i
configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. The Surveillance Requirements i
for leakage testing of ECCS check valves ensures that a failure of one valve will not cause an intersystem LOCA.
In Mode 3, with pressurizer pressure below 1000 psig, the accumulators will be available with their isolation valves either closed but energized, or open, whenever a $18809 valve is closed to perform check valve leakage testing.-
For Unit 1, Surveillance Requirement 4.5.2.b.1 requires that the ECCS pump casings and discharge piping high points equipped with vent valves be vented on a 31 day frequency. This venting surveillance does not apply to subsystems in communication with operating systems because the flows and/or pressures prevalent in these systems are sufficient to provide confidence that water hammer which occurs from voiding would not result in unacceptable dynamic BYRON - UNITS 1 & 2 B 3/4 5-2 AMENDMENT NO. 90
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued) loads.
During normal operation, this exclusion would apply to the High Head Safety Injection subsystem.
During shutdown cooling operation, the exclusion would apply to the single required centrifugal charging pump and operating RH pump, in addition to the ECCS piping in communication with the operating pumps.
Because the centrifugal charging pumps are not equipped with pump casing vent valves, and the pump design and system piping configuration allow the pumps to be maintained under positive pressure when in standby, manual venting of these pumps is not required.
The surveillance requirement to ultrasonically examine selected portions of piping involves the idle CV pump discharge piping up to the first check valve on the pump discharge and miniflow lines, and the stagnant portion of the piping upstream of the ISI8801A/B adjacent to the vent valve 1S1045.
This will provide added assurance that the piping is water solid.
BYRON - UNITS 1 & 2 B 3/4 5-2a AMENDMENT NO. 90