ML20248F452
| ML20248F452 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/26/1998 |
| From: | Stewart Bailey NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248E027 | List: |
| References | |
| NUDOCS 9806040270 | |
| Download: ML20248F452 (8) | |
Text
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@ Cth kl UNITED STATES p
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.c. - M
$9 * * * * *,o COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 24,1997, 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; j
l 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; i
D.
The issuance of this emendment 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 end 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 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
i 9806040270 990526 1
PDR ADOCK 05000454 P
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2 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 93 and the Environmental Protection Plan contained in Appendix B, both of which are cttached hereto, are hereby incorporated into this license. The licensee shall operate the facility in acccrdance with the Technical Specifications and the Environmental Protection Plan.
3.
This !icense amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Stawart N. Bailey, P e nager Project Directorate lll-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance:
May 26, 1998 i
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4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3068H001 p%...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 MNDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NFF 77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 24,1997, 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; D.
The issuance of this amendment will not be inimical to the comm'on 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)'of Facility Operating License No. NJF-77 is hereby amended to read as follows:
l
2 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 93 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF 72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
Thh license amendment is effective as of the date if its issuance and shall be implemented within 30 days.
FCG THE NUCLEAR REGULATORY COMMISSION Stewart N. Bailey, P ject M ger Project Directorate ! -
Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance:
May 26, 1998
ATTACHMENT TO LICENSE AMENDMENT NOS. 93 AND 93 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 l
DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
Remove Paaes insert Paaes 3/4 3-65 3/4 3-65 8 3/4 3-6 B 3/4 3-6 B 3/4 3-7 8 3/4 3-7 s
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPLICABILITY:
MODES 1,2, AND 3.
ACTION:
a.
With one throttle valve or one govemor valve per high pressure turbine steam iir.s inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated t
OPERABLE:
a.
During turbine operation at least once per 31 days by direct observation of the movement of the valves below through one complate cycle from the running position:
1.
Gix turbine reheat stop valves, and 2.
Six turbine reheat intercept vcives.
b.
During turbine operation at least once per 92 days by direct observation of the movement of the valves below through one complete cycle from the running position:
1.
Four high pressure turbine throttle valves, and 2.
Four high pressure turbine govemor valves.
c.
Within 7 days prior to entering MODE 3 from MODE 4, by cycling each of the 12 extraction steam nonretum check valves from the closed position, d.
During turbine operation at least once per 31 days by direct observation, of freedom of l
movement of each of the 12 extraction steam non-retum check valve weight arms, e.
At least once per 18 months by performance of CH/.NNEL CALIBRATION on the l
Turbine Overspeed Protection Systems, and f.
At least once per 40 months by disassembling at least one of each of the valves given in Specifications 4.3.4.2a., b. and c. above, and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
BRAIDWOOD-UNITS 1 & 2 3/4 3-65 AMENDMENT NO. 93
INSTRUMENTATION BASES 3/4.3.3.8 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System components. The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors,"
May 1981.
3/4.3.3.9 DELETED 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION The instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.
3/4 3.3.11 HIGH ENERGY LINE BREAK ISOLATION SENSORS The OPERABILITY of the high energy line break isolation sensors ensures that the capability is available to promptly detect and initiate protective act!on in the event of a line break.
This capability is required to prevent the potential for damage to safety-related systems and structures in the auxiliary building.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumen-tation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.
Specification 4.3.4.2a and b (High Pressure Turbine and Reheat Valves)
These valves isolate large quantities of steam with high potential for delivering energy to the rotor system. Tha turbine design recognizes this potential in providing rapid action, dual shut off capability in each path, remote testing capability, and a flow path that reduces the effects of changes in flow distribution, load reductions, and thermal transients during testing. The testing intervals are in accordance with the latest manufacturer's recommendations: " Operation and Maintenance Memo 093," Power Generation Business Unit, Westinghouse.
l BRAIDWOOD - UNITS 1 & 2 B 3/4 3-6 AMENDMENT NO. 93
-a
! INSTRUMENTATION BASES TURBINE OVERSPEED PROTECTION (Continued)
Specification 4.3.4.2c and d (Extraction Steam Non-Retum Check Valves) l These valves are provided to protect the turbine from reflux of steam remaining in the feedwater heater shells and piping following the pressure ieduction caused by the actuation of valves in Specification 4.3.4.2a and b. The quantities of stored steam controlled by these valves l
are smaller and are divided up into separate heater shells. The feedwater heating system design, including these valves, did not intend routine full stroke testing.
The extraction steam check valves are self closing swing disk non-retum valves which shut under the combined effect of gravity and reverse flow of steam. The weight of the disk is partly balanced by a counterweight and lever on the pivot shaft. A spring cylinder acting on the lever assists the start of the automatic closing, but is not intended to close the valve fully against normal steam flow and pressura. In normal operation the spring assist is held clear by air pressure acting on a piston under the spring. The turbine trip system releases the air pressure to assist the closing.
Manual stroking of the extraction steam non-retum valves is possible under shutdown conditions by latching the turbine and applying the air pressure to the spring cylinder, it is possible to hear and feel the disk contact the seat sc! idly. This manual stroking was not provided for h the design but will be done within 7 days prior to entering Mode 3 from Mode 4.
The engineering specifications provided for testing the extraction steam non-retum check valves during operation by equalizing the air pressure across the piston in the spring cylinder, permitting the spring to partially close the disk against the steam flow. The rotation of the shaft accompanying the disk closure can be observed by movement of the weight lever. The amount of movement observed in other stations has depended on the extraction steam conditions and valve size, but has been ample to indicate freedom of movement, and this will be verified during startup testing.
Partial stroking demonstrates that the disk system is free at the beginning of the closing stroke where the steam closing forces are smallest. As the disk enters a reverse steam flow the closing forces build up rapidly with progressive closure.
The design of the feedwater heating system is such that full stroke testing of the extraction steam non-retum valves during turbine operation involves several penalties without significant additional advantages over partial stroke testing. The motor-operated isolating valve must be closed on an individual heater. Heater stages 1,2,3, and 4 are arranged in three parallel strings with cascaded drains in each string and heater stages 5,6 and 7 are similarly arranged in two parallel strings. An entire string is taken out of service, isolated, and bypassed for maintenance.
Isolating the extraction steam to a single intermediate heater involves several complications.
l BRAIDWOOD - UNITS 1 & 2 B 3/4 3-7 AMENDMENT NO. 93