ML20058L620
| ML20058L620 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/31/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L622 | List: |
| References | |
| NUDOCS 9008070364 | |
| Download: ML20058L620 (9) | |
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'A NUCLEAR REGULATORY COMMISSION
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 i
SE0VOYAH N,UCLEAR, PLANT,_ UNIT,1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143 License No. DPR-77 1.
The Nuclear Regulatory Conniission (the Conmission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licenste) dated February 14,1990, complies with the undards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Consnission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 Conmission'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 amendnent is in accordance with 10 CFR Part 51 of the Consnission's regulations and all applicable requirements have been satisfied.
9006070364 900731 P11R ADOCK 05000327 P
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2-2.
Accordingly, the license is arrended by changes to the Technical Specifications as indicated in the attacho>ent to this license arendo:ent and paragraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby arended to read as follcws:
(2) Technir Alj,e,c,1,fications The Technical Specificatieris contained in Appendices A art B, as rtvised thrcugh Aniendnent No.143, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license aniendn.ent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0! PISS 10N h, >.W,f N. !h E ~
FrederickJ.Heb) don, Director Project Directorate !!-4 Divisien of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachtrent:
Charises to the Technical Specifications Date of Issuar:ce: July 31, 1990 l
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FfCILITY OPERAT1hG LICENSE NO. DPR-77 DOCKETNO,.,)p,,327 Etvise the Apper, dix A Technical Specifications by renoving the pages identified Lelow and inserting the enclosed pages. The revised pages L
are identified by the captioned antndrent number and contain margir.a1 lines indicating the area of change, REMOVE INSERT.
3/4 7-37 3/4 7-37 3/4-7-39 3/4 7-39 g
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i PLANT. SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.
APPLICABILITY:
Whenever equipment in the steas protected by the fire hose stations is required to be OPERABLE.
ACTION:
a.
With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.3.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the station to OPERABLE status, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
S.URVEILLANCE REQUIREMENTS i
4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:
a.
At least once per 31 days by visual inspection of the stations accessible during plant operations to assure all required equipment is at the station, b.
At least once per 18 months by:
1.
Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, l
2.
Removing the hose for inspection and re-racking, and 3.
Inspecting all gaskets and r d acing any degraded gaskets in the couplings, c.
At least once per 3 years by:
1.
Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
2.
Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
SEQUOYAH - UNIT 1 3/4 7-37 Amendment No. 36, 114, 143
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- TABLE 3.7-5 (Continued)
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
Control Building 685 0-26-1188 Control Building 685 0-26-1193 Control Building 669 0-26-1189 Control Building 669 0-26-1194 i
d.
Diesel Generator Building Corridor 722 0-26-1077 Corridor 740.5 0-26-1080 Air Exhaurt Rs.
740.5 0-26-1082 Lube Oil Storage Room 722,0-2 722 0-26-2337 l
e.
Additional Equipment Building - Unit 1 South Wall 740.5 1-26-687 South Wall 706 1-26-686 f.
Auxiliary Building 759 1-26-669 749 2-26-664 749 1-26-664 734 2-26-670 734 0-26-684 734 1-26-670 734 0-26-602 734 1-26-671 Siamese Outlet 734 1-26-672 734 1-26-665 714 0-26-660 714 1-26-666 714 0-26-677 706 0-26-658 690 0-26-690 690 0-26-661 fffSiameseOutlet fff'fff 690 1-26-667 669 1-26-668 669 0-26-662 0
669 0-26-680 653 0-26-663 653 0-26-691 l
l SEQUOYAH - UNIT 1 3/4 7-39 Amendment No. 13, 143 l
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%,..... p TENNESSEE VALLEY AUTHORITY DOCKET N_0.,50-328 SEgyOf All,., NUCLE AR,,P,L,A,N,T,,, UNIT 2 AMENDttENT TO FACILITY OPERATING LICENSE 4
Amendment No.124 License No. DPR-79 1.
The Nucleat Regulatory Conmission (the Consission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) datec' february 14, 1990, con. plies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Consission'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.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 Cormission's regulations; D.
The issuance of this aniendnent will r.ct be inimical to the conmon 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 Consission's regulations and all applicable requiren:ents have been satisfied, t
1
, 2.
Accordingly, the license is atended by changer to the Technical Specifications as indicated in the attachnent to this license an.endment l
arid paragraph 2.C.(2) of facility Operating License No. DFR-79 is hereby arrended to read as follows:
(2) I.65h h.if.0.l..SP.ef.i.f i _c a t i o n s The Technical Specifications f.ontained in Appendices A 2nd B, as rtvised through Amendnent No.124. are hereby incorporated in the r
license. The licensee shall operate the facility in accordance with the Technical Specific 6tions.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a ') h
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Frederick J. Heb on, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attach:4nt:
Chenges to the Technical Specifications Date of Issuance: July 31, 1990
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.1-ATTACHMENT TO LICENSE AMENDMENT NO.124
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FACILITY OPERATihG LICENSE NO. DPR-79 5
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DOCKET 140,.,,5,0-3f 8 Perfs9 the Apptodix A Technical Specifications bf renoving the pages i'sentified below and inserting the enclosed pages. The. revised pages-
'are identified by the captioned an.endnent nuciber and contain narginal
-lines indicating the area of-change.
REMOVE INSERT 3/4 7-50 3/4.7-50 i
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t Table 3.7-5 (Continued) f]_RE HOSE STATIONS R
LOCATION ELEVATION HOSE RACK #
Control Building 685 0-26-1188 Control Building 685 0-26-1193 Control Building 669 0-26-1189 Control Building 669 0-26-1194 d.
Diesel Generator Building Corridor 722 0-26-1077 Corridor 740.5 0-26-1080 Air Exhaust Rm.
740.5 0-26-1082 Lube Oil Storage Room 722.0-2 722 0-26-2337 l
e.
Additional Equipment Building - Unit 2 North Wall 740.5 2-26-687 North Wall 706 2-26-686 f.
Auxiliary Building 759 2-26-669 749 2-26-664 749 1-26-664 734 2-26-670 734 0-26-684 734 1-26-670 734 0-26-682 734 Siamese Outlet 2-26-671 734 2-26-672 734 2-26-665 714 0-26-660 714 2-26-666 l
i' 714 0-26-677 706 0-26-658 l
690 0-26-690 l
690 0-26-661 690 Siamese Outlet 2-26-674 690 2-26-675 669 2-26-667 669 2-26-668 669 0-26-662 669 0-26-680 653 0-26-663 653 0-26-691 l
SEQUOYAH - UNIT 2-3/4 7-50 Amendment No. 104, 124
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