ML20210K702
| ML20210K702 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/13/1997 |
| From: | Dick G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210K705 | List: |
| References | |
| NUDOCS 9708200044 | |
| Download: ML20210K702 (5) | |
Text
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UNITED STATES
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NUCLEAR REEULATORY COMMISSION WASHINGTON, D.C. 2066H001
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-66 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 by letters dated May 31, June 20, June 24, and July 18, 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 witn 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 lechnical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
P
i, (2)
Inc.hpical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 91 and revised by Attachment 2 to hPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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George F. Dick, Pr ject Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1997 b
ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. NPF-66 DOCKET NO. STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 5-4b 3/4 5-4b B 3/4 5-2a B 3/4 5-2a a
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E EBSENCY CORE COOLING SYSTEMS
-SURVEILLANCE REOUIREMENTS
~4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
- 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 a.
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 Pumps MOV SI8835 SI Pump Discharge Open*
To RCS Cold legs MOV-SI8813 SI Pump Recirculation Open To The RWST MOV SI8809A RHR Pump Discharge to Open*
RCS Cold Legs MOV SI8809B 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 M0V SI8802B SI Pump Discharge to Closad RCS ' Hot Legs b.
At least once per 31 days by:
1)
Venting the ECCS pump casings and discharge piping high point vent valves outside of containment (applicable to idle RH and SI systems only), and 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 (applicable to CV, RH, SI systems)..
3)
Verifying the CV-system is full of water by ultrasonically exa:nining the discharge portion of the idle CV pump up to the discharge check valve, the stagnant portion of the piping upstream of the 25I8801 A and B at the 2SIO45 valve,.and the-piping at the 2CV206 valve if the 2BCV pump is idle (applicable to the CV system only).
By a-visual inspection which verifies that no loose debris (rags.
c.
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 5-4b AMENDMENT NO. 91 4
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 R
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 -urveillance 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 ISIO45. This will
(
provide added assurance that the piping is water solid.
For Unit 2, Surveillance Requirement 4.5.2.b.1 requires that the RH and SI pump casings and discharge piping high point vent valves be vented on a 31 day frequency. This venting surveillance does not apply to subsystems in E
communication with operating systems because the flows in these systems are sufficient to provide confidence that water hammer which could occur from I-~}
voiding would not result in unacceptable dynamic loads.
During shutdown cooling operation, the exclusion would apply to the operating RH pump, in addition to the ECCS piping in communication with the operating pump.
The TS 4.5.2.b.3 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, the stagnant portion of the piping upstream of the 2 SIB 801A/B adjacent to the vent valve 2S1045, and the piping at the 2CV206 valve if the 2B CV pump is idle. This examination will provide added assurance that the pipirg is water solid.
BYRON - UNIIS i & 2 B 3/4 5-2a AMENDMENT N0. 91
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