ML18016A232
| ML18016A232 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/25/1997 |
| From: | Lyons J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18016A233 | List: |
| References | |
| NUDOCS 9712030189 | |
| Download: ML18016A232 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMIVIISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER
& LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 MENDMEN TO FACILITY OPERATING LICENSE Amendment No.
75 License No.
NPF-63 2.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 8 Light Company, (the licensee),
dated February 18,
- 1997, complies w'ith 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.
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-63 is hereby amended to read as follows:
9712030i89 97ii25 PDR ADOCK 05000400 P
POR
3..
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 75, are hereby incorporated into this license.
Carolina Power
& Light Company shall~ operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
This.license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications arne E. Lyons, ir'ector o't Directorate II-I Div sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
NoVember 25, 1997
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
NPF-63 DOCKET NO.. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages'he revised areas are indicated by margin lines.
~RP 3/4 7-2 B 3/4 7-1 Insert Pa e
3/4 7-2 B 3/4 7-1 B 3/4 7-la
TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING 3 LOOP OPERATION MAXIMUM NUMBER OF INOPERABLE MAXIMUMALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR PERCENT OF RATED THERMAL'OWER 53 35 17
~SHEARON HARRIS --UNIT 1 3/4 7-2 Amendment No.
75
I 3/4.7 PLANT SYSTEM BASES I
3/4.7. 1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the Secondary System pressure will be limited to within llOX (1305 psig) of its design pressure of 1185 psig during the most severe anticipated system opera-tional transient.
The maximum relieving capacity is associated with.a Turbine
'rip from 100K RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e.,
no steam bypass to the condenser).
The specified valve liftsettings and relieving capacities are in accordance with.the requirements of Section III of the ASME Boiler and Pressure Code,'971 Edition., The total relieving capacity for all valves on all of the steam lines is 1.36 x 10'bs/h which is 111K of'he total secondary steam flow of, 12.2 x 10'bs/h at 100K RATED THERMAL POWER..
A minimum of two OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.
. STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels.
The Reactor Trip Setpoint reductions are derived on the following bases:
'or 3 loop operation (w, hN)
Hie = (100/Q)
K' Where..
Hie =
Safety Analysis power range high neutron flux setpoint, percent Q
=
Nominal NSSS power rating of the plant (including reactor coolant pump heat),
Mwt K
=
Conversion factor, 947.82 ~8tulsec Mwt w,
Minimum total steam flow rate capability of the operable MSSVs on any one steam generator at the highest MSSV opening pressure including tolerance and accumulation, as appropriate, in lb/sec.
=
Heat of. vaporization 'for steam at the highest MSSV opening ressure including tolerance and accumulation, as appropriate.
tu/ibm N
Number of loops in plant The values from this algorithm must then be adjusted lower to account for instrument and channel uncertainties.
This adjustment will be 9X power.
SHEARON HARRIS - UNIT 1 B 3/4 7-1 Amendment No. /5
~.
'. '/4.7 PLANT SYSTEH
~
BASES 3/4.7.1.2 AUXILIARYFEEDMATER SYSTEM The OPERABlLITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions so that the Residual Heat Removal System may be placed into SHEARON HARRIS - UNIT l B 3/4 7-la Amendment No. 75