ML20076G934
| ML20076G934 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/07/1994 |
| From: | Carpenter C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076G936 | List: |
| References | |
| NUDOCS 9410200313 | |
| Download: ML20076G934 (2) | |
Text
4 psnou i
UNITED STATES p
s j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665 4 001
+.,
/
TOLED0 EDIS0N COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.192 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated September 3, 1992, as supplemented on August 22, 1994, 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; 8.
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 license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9410200313 941007 PDR ADOCK 05000346 P
ppg
_2_
j (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.192, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance l
with the Technical Specifications.
3.
This license amendment is effective as of its date of
.uance and shall be implemented not later than 90 days after issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION k
pM Cynthia A. Carpenter, Acting Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation j
i
Attachment:
Changes to-the Technical Specifications-i Date of issuance: October 7, 1994
9 ATTACHMENT TO LICENSE AMENDMENT NO.192 FACILITY OPERATING LICENSE NO. NPF-3 l
DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 1-1 3/4 1-1
.3/4 4-6 3/4 4-6 3/4 4-6a 3/4 4-6b B 3/4 4-3 B 3/4 4-3 f
1 j
.P
3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be 11% ok/k.
l APPLICABillTY: MODES 1, 2*,
3**, 4 and 5.
ACTION:
With the SHUTDOWN MARGIN < 1% ok/k, immediately initiate and continue boration at 2 25 gpm of 7875 ppm boron or its equivalent, until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE RE0VIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be 11% ok/k:
Within one hour after detection of an inoperable control rod (s) a.
and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s),
b.
When in MODES 1 or 2#, 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 regulating rod groups withdrawal is within the limits of Specification 3.1.3.6.
When in MODE 2## within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor c.
criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6.
Prior to initial operation above 5% RATED THERMAL POWER after each d.
fuel loading by consideration of the factors of e. below, with the regulating rod groups at the maximum insertion limit of Specification 3.1.3.6.
- With k,, 1 1.0
- Withe
< 1.0
- SeeSpeETalTestException3.10.4
- See LC0 3.4.5, Steam Generators, for additional SHUTDOWN MARGIN requirements.
DAVIS-BESSE, UNIT 1 3/4 1-1 Amendment No. JSJ,192
REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each Steam Generator shall be OPERABLE with a minimum water level of 18 inches and the maximum specified below as applicable:
MODES I and 2:
The acceptable operating region of Figure 3.4-5.
a.
MODE 3*:
b.
50 inches Startup Range with the SFRCS Low Pressure Trip bypassed and one or both Main Feedwater Pump (s) capable of supplying Feedwater to any Steam Generator.
c.
96 percent Operate Range with:
l 1.
The SFRCS Low Pressure Trip active.
Or i
2.
The SFRCS Low Pressure Trip bypassed and both Main Feedwater i
Pumps incapable of supplying Feedwater to the Steam Generators.
MODE 4:
d.
625 inches Full Range Level APPLICABILITY:
MODES 1, 2, 3, and 4, as above.
ACTION:
With one or more steam generators inoperable due to steam a.
generator tube imperfections, restore the inoperable generator (s) to OPERABLE status prior to increasing T,,, above 200*F.
b.
With one or more steam generators inoperable due to the water level being outside the limits, be in at least HOT STANDBY within 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 next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- Establish adequate SHUTDOWN MARGIN to ensure the reactor will stay subtritical during a MODE 3 Main Steam Line Break.
DAVIS-BESSE, UNIT 1 3/4 4-6 Amendment No. 7Y,Y77,192
a Fiaure 3.4-5 Maximum Allowable Steam Generator Level in MODES I and 2 100 -
(43,96)
U
/
T 90 -
t
.a EE 80 -
Unacceptable Operating 3
Region 2
E, 70 -
o
%$ 60 -
5 Acceptable U
Operating 3
Region 3 50 -
m (0,43) 40 -
i i
i i
i f
0 10 20 30 40 50 60 Main Steam Superheat (*F)
DAVIS-BESSE, UNIT 1 3/4 4-6a Amendment No.192
REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE RE0VIREMENTS Each steam generator shall be demonstrated OPERABLE by performance of 4.4.5.0 the following augmented inservice inspection program and the requirements of Specification 4.0.5.
4.4.5.1 Steam Generator Samole Selection and Insoection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4-4.1.
4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
The first sample inspection during each inservice inspection a.
(subsequent to the baseline inspection) of each steam generator shall include:
1.
All tubes or tube sleeves that previously had detectable wall penetrations (> 20%) that have not been plugged or repaired by sleeving in the affected area.
2.
At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems.
J DAVIS-BESSE - UNIT 1 3/4 4-6b Amendment No.192
\\
REACTOR COOLANT SYSTEM BASES (Continued)
Operating plants have demonstrated operation and by postulated accidents.
that primary-to-secondary leakage of 1 GPM can be detected by monitoring the secondary coolant.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired by sleeving in the affected areas.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during !.cheduled inservice steam generator tube examinations.
As described in Topical Report BAW-2120P, degradation as small as 20% through wall can be detected in all areas of a tube sleeve except for the roll expanded areas and the sleeve end, where the limit of detectability is 40%
Tubes with imperfections exceeding the repair limit of 40% of through wall.
the nominal wall thickness will be plugged or repaired by sleeving the affected areas. Davis-Besse will evaluate, and as appropriate implement, better testing methods which are developed and validated for commercial use so as to enable detection of degradation as small as 20% through wall without Until such time as 20% penetration can be detected in the roll exception.
expanded areas and the sleeve end, inspection results will be compared to those obtained during the baseline sleeved tube inspection.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results shall be reported to the Commission prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
The steam generator water level limits are consistent with the initial While in MODE 3, examples of Main feedwater Pumps assumptions in the USAR.
that are incapable of supplying feedwater to the Steam Generators are tripped pumps or a manual valve closed in the discharge flowpath.
The reactivity requirements to ensure adequate SHUTDOWN MARGIN are provided in plant operating procedures.
DAVIS-BESSE, UNIT 1 B 3/4 4-3 Amendment No. 17J, W, 192