ML17229A837
ML17229A837 | |
Person / Time | |
---|---|
Site: | Saint Lucie ![]() |
Issue date: | 08/18/1998 |
From: | Hebdon F NRC (Affiliation Not Assigned) |
To: | |
Shared Package | |
ML17229A838 | List: |
References | |
NUDOCS 9808210174 | |
Download: ML17229A837 (8) | |
Text
ggS REoy
~o Cy 00 I
0 Cy
+
gO
+**++
UNITED STATES NUCLEAR REGULATORY,COMMISSION WASHINGTON> D.c. 205554001 CITY OF OR D
0 D
0 A
U ICIP GENG 0
- 8 S
UCEPLA I
0 2 DME T 0 FACILI 0
E NG LICENSE Amendment No. 95 License No. NPF-16 The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee), dated March 3, 1998, 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; The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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.
98082iOi74 9808i8 PDR AOQCK 05000389 P
PDR Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:
2.
hi ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 18, 1998
0 C
DE O95 TO C
OCK NO 50-389 Replace the following pages of the Appendix "A"Technical Specifications with the enclosed pages.
The revised pages are identified. by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness'.
emove e
3/4 4-22 5-4 6-12 se a es 3/4 4-22 5-4 6-12
REACTO COOLANTSYS 3/4.4.7 CHEMISTR 3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-2.
APL A>>:
II DES
~CTION:
MODES1,2,3, and 4:
a.
With any one or more chemistry parameter in excess of its Steady State Limitbut within its Transient Limit, restore the parameter to within its Steady State Limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any one or more chemistry parameter in excess of its Transient Limit, be in at least HOT.STANDBYwithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
With the concentration of eithei chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limitfor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its Transient Limit, reduce the pressurizer pressure to less than or equal to 500 psia, ifapplicable, and perform an engineering evaluation to determine the effects of the outwf-limitcondition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operatiorr prior to increasing the pressurizer pressure above 500 psia or prior to proceeding to MODE 4.
4.4.7.
The Reactor Coolant System chemistty shall be determined to be within the limits by analysis of those parameters at the frequencies specified in fable 4.4-3.
ST. LUCIE-UNIT2 3/4 4-22 Amendment No.
95
5.4.2 The total water and steam volume of the reactor coolant system is 10,931+ 275 cubic feet at a nominal T of572'.
5.5.1 5.6 METEOROLOGICALTOWER LOCATION The meteorological tower shall be located as shown on Figure 5.1-1
~
FUEL STOR GE
~CIT T
5.6.1 a.
The spent fuel storage racks are designed and shall be maintained with:
A k~ equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 0.024 dk,(Region I) and 0.01 7 hk, (Region II)for Total Uncertainty.
2.
A nominal 8.96 inch center-to-center distance between fuel assemblies placed in the storage racks.
3.
A boron concentration greater than or equal to 1720 ppm.
Region I can be used to store fuel which has a U-235 enrichment less than or equal to 4.5 weight percent.
Region II can be used to store fuel which has achieved sufficient burnup such that storage in Region I is not required. The initial enrichment vs. bumup requirements of Figure 5.6-1 shall be met prior to storage of fuel assemblies in Region II.
b.
The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal to 4.5 weight percent, while maintaining a k,of less than or equal to 0.98 under the most reactive condition.
~DRAINAG 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining'of the pool below elevation 56 feet.
~GAPA IPT'.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1076 fuel assemblies.
COMPONENT CYCLIC0 T
S ENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
ST. LUCIE-UNIT2 Amendment No. 7,. 9g
~ULS (continued) d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50.
e.
Any other area of unit operation considered appropriate by the CNRB or the President - Nuclear Division.
f.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel.
g.
The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
h.
The radiological environmental monitoring program and the results thereof.
i.
The OFFSITE DOSE CALCULATION MANUALand implementing procedures.
j.
The PROCESS CONTROL PROGRAM and implementing procedures for dewatering of radioactive bead resin.
TECHNICALREVIEW RE PONSIBI ITIES 6.5.2.9 The technical review responsibilities under the cognizance of the CNRB shall encompass:
a.
Plant operating characteristics, NRC issuances, industry advisories, Licens'ee Event Reports and other sources that may indicate areas for improving plant safety:
b.
Plant operations, modifications, maintenance, and surveillance to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical; c.
Internal and external operational experience information that may indicate areas for improving plant safety; and d.
Making detailed recommendations to the Chairman - CNRB and plant management for revising procedures, equipment modifications or other means of improving nuclear safety and plant reliability.
6.5.2.10 The CNRB shall report to and advise the President - Nuclear Division on those areas of responsibility specified in Specifications 6.5.2.7, 6.5.2.8, and 6.5.2.9.
ST. LUCIE - UNIT2 6-12 Amendment No.47,69,89,'5