ML20203F824
| ML20203F824 | |
| Person / Time | |
|---|---|
| Site: | Perry |
| Issue date: | 02/08/1999 |
| From: | Pickett D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203F829 | List: |
| References | |
| NUDOCS 9902180322 | |
| Download: ML20203F824 (6) | |
Text
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 300eH001
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FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-440 EE.R_ RY NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-58 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
' se application for amendment by the FirstEnergy Nuclear Operating Company (the licensee, formerly The Cleveland Electric illuminating Company, Centerior Servico Company, Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc.,
Pennsylvania Power Company, and Toledo Edison Company) dated June 30,1998, as supplemented on December 9,1998, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Core:nission; C.
There is raasonable assurance (i) that the activities authorized by this amendment can be condt;cted 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 dufense 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-58 is hereby amended to read as follows:
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9902180322 990208 PDR ADOCK 05000440 P
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(2) TechnicalSpecifications
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The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 97 are hereby incorporated into this license. The FirstEnergy Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days afterissuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q v PM Douglas V. Picken, Senior Project Manager Project Directorate lil-2 Division of Reactor Projects lil/IV i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications I
Date of issuance: February 8, 1999 l
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ATTACHMENTTO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. NPF-58 DdCKET NO. 50-440 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 Insert 3.1-21 3.1-21 3.1-22 3.1-22 3.1-23 3.1-23 i
SLC Systen 3.1.7
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i SlRVFilI ANT RFrillRFKNTS SlRVEILIANCE FREQUENCY l
SR 3.1.7.1 Verify available volme of borax-boric acid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> solution is within the limits of Figure 3.1.7-1.
l SR 3.1.7.2 Verify tarperature of borax-boric acid solution is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a 70 F.
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l SR 3.1.7.3 Verify tarperature of pmp suction piping is 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 70F.
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l SR 3.1.7.4 Verify contiruity of eglosive change.
31 days l
SR 3.1.7.5 Verify the concentration of boron in solution is 31 days within the limits of Figure 3.1.7-1.
01ce within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or bomn is added to solution 01ce within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution tarperature is restored to 2 70 F l-i
-(continued)
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PERRY - LNIT 1 3.1-21 Arendient No. 97 d
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SLC Systen L-3.1.7 I
l SLRVEILIANCE RE0JIREENTS (continued) f SLRVEILLANCE FREQUENCY l
SR 3.1.7.6 Verify each SLC stbsysten manual, pmer operated.
31 days and autoratic valve in the fim path that is not locked, sealed, or otherwise secumd in position.
is in the cormct position, or can be aligned to i
the cormct position.
i SR 3.1.7.7.
Verify each ptmp develops a fim rate 2 32.4 gpm at In accordance with l
a discharge pressum 21220 psig.
the Inservice Testirg Pmgram l
t SR 3.1.7.8 Verify fim thmugh one SLC stbsysten fran ptmp 18 months on a i
into reactor pressure vessel.
STAG ERED H ST EMSIS j
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SR 3.1.7.9 Verify all heat traced pipirg between storage tank 18 rronths and ptmp suction is unblocked.
htD Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ptmp suction i'
pipirg tarperature is restored to 2 70 F i
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PERRY - WIT 1 3.1-22 Aiudud. No. 97
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BORON SOLUTION CONCENTRATION AND VOLUME REQUIREMENTS 3
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LOWLEVEL HIGH LEVEL ALARWI ALARtl TANK SETPOINT SETPOINT NN 2E f
1-g, r,jM,.,..~d. hl{' m.,gypy{,4, 2'
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2.s*
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2 REGION OF APPROVED
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, { 2.as VOLUME AND w
g 2.s conc.
%jyip f 17"'
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CONCENTRATION t
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.:=
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!E 2.8%
5 8"
2.75 s
2 2.7 t
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2.65 tn 4s44 3
47:2 m4 g
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4300 4400 4500 4600 4700 4800 4900 5000 V. INDICATED NET TANK VOLURIE (GALLONS)
Figure 3.1.7-1 Baron Solution ConcentrationNolume R%.:........"a