ML18005A918
| ML18005A918 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/22/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18005A919 | List: |
| References | |
| NPF-63-A-011 NUDOCS 8905300194 | |
| Download: ML18005A918 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER 8 LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 11 License No.
NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 8 Light Company (the licensee),
dated February 22, 1989, 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 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 1icense amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-63 is hereby amended to read as follows:
8905300i94 390522 PDR ADOCK 05000400 P
(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.ll
, are hereby incorporated into this license.
Carolina Power 5 Light Company 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.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1989 Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II Office of'uclear Reactor Regulation
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ATTACHMENT TO LICENSE AMENDMENT NO. 11 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es Insert Pa es 3/4 1-4 3/4 1-5 8 3/4 1-2 B 3/4 1-2a 3/4 1-4 3/4 1-5 B 3/4 1-2 B 3/4 1-2a
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
a.
Less positive than
+5 pcm/'F for power levels up to 70X RATED THERMAL POWER and a linear ramp from that point to 0 pcm/'F at 100X RATED THERMAL POWER; and b.
Less negative than -49 pcm/'F for all rods withdrawn, end of cycle life (EOL),
RATED THERMAL POWER condition.
APPLICABILITY: Specification 3.1.1.3a.
MODES 1 and 2"< only""-".
Specification 3.1.1.3b.
MODES 1, 2, and 3 only'"'>>.
ACTION:
a.
With the MTC more positive than the limit of Specification 3 ~ 1 ~ 1.3a.
- above, operation in MODES 1 and 2 may proceed provided:
1 ~
Control rod withdrawal limits are established and maintained sufficient to restore the MTC to within the above limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6
hours'hese withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6; 2.
The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for. the all rods withdrawn condition; and 3.
A Special Report is prepared and submitted to the Commission, pursuant to Specification 6.9.2, within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
b.
With the MTC more negative than the limit of Specification 3 ~ 1 ~ 1.3b.
- above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With keff greater than or equal to 1.
<>See Special Test Exceptions Specification 3.10.3.
SHEARON HARRIS - UNIT 1 3/4 1-4 Amendment No.
REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a ~
The MTC shall be measured and compared to the BOL limit of Specifi-cation 3.1.1.3a.,
above, prior to initial operation above 5X of RATED THERMAL POWER, after each fuel loading; and b.
The MTC shall be measured at any THERMAL POWER and compared to
-41.5 pcm/'F (all rods withdrawn, RATED THERMAL POWER condition) within 7
EFPD after reaching an equilibrium boron concentration of 300 ppm.
In the event this comparison indicates the MTC is more negative than
-41.5 pcm/'F, the MTC shall be remeasured, and compared to the EOL MTC limit of Specification 3.1.1.3b.,
at least once per 14 EFPD during the remainder of the fuel cycle.
SHEARON HARRIS UNIT 1 3/4 1-5 Amendment No. 11
REACTIVITY CONTROL SYSTEMS BASES MODERATOR TEMPERATURE COEFFICIENT (Continued)
The most negative MTC, value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.
These corrections involved:
(1) a conversion of the MDC used in the FSAR safety analyses to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all rods withdrawn, RATED THERMAL POWER conditions, and those most adverse conditions of moderator temperature and pressure, rod insertion, axial power skewing, and xenon concentration that can occur in normal operation and lead to a significantly more negative EOL MTC at RATED THERMAL POWER.
These corrections transformed the MDC value used in the FSAR safety analyses into the limiting MTC value of
-49 pcm/'F.
The MTC value of -41.5 pcm/'F represents a conservative MTC value at a core condition of 300 ppm equilibrium boron concentration, and is obtained by making corrections for burnup and soluble boron to the limiting MTC value of -49 pcm/'F.
The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 551'F.
This limitation is required to ensure:
(1) the moderator temperature coefficient is within its I
analyzed temperature
- range, (2) the trip instrumentation is within its normal operating
- range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RTNDT temperature.
3/4.1 ~ 2 BORATION SYSTEMS The Boron Injection System ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include:
(1) borated water sources, (2) charging/safety injection
- pumps, (3) separate flow paths, (4) boric acid transfer
- pumps, and (5) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 350'F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable.
The boration capa" bility of either flow path is sufficient to provide the required SHUTDOWN MARGIN as defined by Specification 3/4.1.1.2 after xenon decay and cooldown to 200'F.
The maximum expected boration capability requirement occurs at BOL SHEARON HARRIS UNIT 1 B 3/4 1-2 Amendment No. //,
11
REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued) from full power equilibrium xenon conditions and requires 21,400 gallons of 7000 ppm borated water be maintained in the boric acid storage tanks or 436,000 gallons of 2000"2200 ppm borated water be maintained in the refueling water storage tank (RWST).
With the RCS temperature below 350'F, one boron injection flow path is accept-able without single failure consideration on the basis of the stable reactivity SHEARON HARRIS - UNIT 1
B 3/4 1-2a Amendment No. ll