ML20059K197
| ML20059K197 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 09/11/1990 |
| From: | Mathews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059K200 | List: |
| References | |
| NUDOCS 9009210212 | |
| Download: ML20059K197 (6) | |
Text
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'o, UNITED STATES
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WASHINGTON, D. C. 20555 -
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DUKE POWER COMPANY
. DOCKER NO.'50-369-
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o MCGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO' FACILITY OPERATING LICENSE l
Amendment No.1121 License No. NPF-91 The Nuclear Regulat' ry Commission (the' Commission)- has found that:
1.
o A.- The app (lication for amendment to the McGuire Nuclear Sta' tion :
Unit 1 the facility) Facility Operating License No. NPF-9 filed >
by the Duke Power Company (the'11censee) dated July 13,1990,1 complies.
with the standards and requirements of.the. Atomic Energy Act'of 1954, as amended (the Act) and the Commission.'s rules and regulations as; set i
forth in 10 CFR Chapter I;-
B.
The facility will operate in conformity with the application, ar.
amended, thel provisions-of the Act,7 and the rules andiregulatir,ns.of the Commission; C.
Thereisreasonableassurance.(1)that.the.activitiesauthorized'by.
this amendment can be. conducted without endangering the health and '
safety of the public, and.(11) that such activities will,be conducted-in cospliance with the Commission's regulations set forth in 10 CFR t
Chapter I; 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'amendsent is in accordance w'ith 10 CFR Part 51 of the Consission's regulations and alliapplicable requirements have been satisfied.
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Accordingly, the license'is hereby amended by page chenpes to the Technical i
Specifications as~ indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of the Facility _ Operating License No. NPF-9 is hereby -
pended to read as follows.-
Technical Specifications The Technical Specifications' contained in Appendix'A,-as revised:through Amendment No.112, are hereby incorporated. into' t.he license. The. licensee shall operate the facility in accordance with.the' Technical Specifications and the Environmental Protection Plan.-
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3.
This'11 cense amendment is effective asfof.its date-offissuance.
FOR_THE. NUCLEAR REGULATORY' COMMISSION-l 4
Da d B..Matthews,._ Director Project Directorate 11-3 Division of Reactor.' Projects-1/II Office of Nuclear Reactor Regulation:
Attachment:
Technical Specification
-Changes Date of Issuance:
September 11, 1990 1
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1 1-DUKE POWER COMPANY DOCKET NO. 50-370 N
MCGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 7
i Amendment No.:94 j
License No. NPF-17 11 The Nuclear' Regulatory Cosmission (the Commission) has found that:
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TheLapp(lication'for amendment to the McGuire Nuclear Station,-the facility) F "i
A.
Unit-2 13, 1990,-
by<the Duke Power Contpany (the licensee) dated July o
1 Act of'1954, as' amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Commission's rules and -
4 -
regulations as set forth in 10 CFR Chapter I; j
B.
The. facility will operate in conformity with the application', as amended, the; provisions of the Act, and the rules and regulations f
of the Commission-g C.
There is' reasonable assurance (1)L hat the activities authorized by-t this amendment:can be conducted without endargering the health and, m
s' -
safety of,the public, and.(11)=that such activities will be conducted:
1 in compliance with the Commission's' regulations set forth in 10 CFR -
Chapter.1;-
E D.
The issuance of this. amendment will not be inimical to the common w
defense and security or to the health and safety of the pub'lic; and:
q E.
The issuance of ~this amendment 1s in accordance with 10 CFR Part 51 of
~
the Commission's regulations and all applicable requirements have been p
' satisfied..
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Accordingly. the license is hereby amended by page changes to the. Technical i
' Specifications 'as indicated in the attachment to this license amendsent, and Paragraph 2.C.(2) of Facility Operating License No. MPF-17 is hereby.
amended. to read'as follows:
~
Technica1' Specifications.
The Technical Specifications containedlin Appendix A, as revised through' 1
Amendment No.94
'are hereby incorporated into the license. ;The 11cer.see -
shall operate.the facility in accordance with the.Technica1' Specifications-
'and the Environmental Protection Plan..
.3.
This license amendment is effective as of'its date of; issuance.-
i FORip)E NUCLEAR-REGULATORY-COM f
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' Davi B. M tthews, Director Project Directorate II-3:
Division of: Reactor. Projects'I/II-Office.of Nuclear Reactor Regulation j
i Attachmenti Technical ~ Specification 1
Changes b
Date of. Issuance:
September. 11, 19901 o
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ATTACHMENT TO LICENSE AMENDMENT NO.112' FACILITY OPERATING LICENSE NO. NPF-9 1
DOCKET.-NO. 50-369:
AND
-TO LICENSE AMENDMENT NO. 94 _
FACILITY OPERATING LICENSE NO. NPF-17 DOCKET N0;-50-370 Replace-the following page of the Appendixi"A" Technical Specifications with s
the enclosed page. 'The revised page is identified by Amendment number and
.i contains_a vertical line' indicating the area of change._
1 Remove Page Insert Page i
3/4 5-6 3/4[5-6 3
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- SURVE'ILLANCE REQUIREMENTS E.5.2 ;Each ECCSisubsystem shall be demonstrated OPERABLE:
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l-a.
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 the following valves a
L are in the indicated' positions with power to the valve operators j
l removed:
.i l
Valve Number-Valve Function Valve Position NI162A Cold Leg Recire.
' Open*
p NI121A Hot Leg Rectre.
Closed 3
NI1528 Hot Leg Recire.
Closed NI1838-Hot L3g Recirc.
Closed NI173A RH5t Pump Discharge Open*
l NI1788-RHR Pump Discharge
' Open*
1 l
nil 008--
FW27A-RHR/RWST Suction Open*
l N1147A St Pump Mini' flow
. Open
'b.
At least;once per 31 days by:
1)
Verifying that the ECCS piping is full of water by venting the J
ECCS pump casings and accessible discharge piping high points,
.q Lunless the pumps and associated piping are in service or have-been in service within 31' days, and l
l 2)
Verifying that-each. valve-(manual, power operated or automatic) in the flow path that-is not locked, sealed, or otherwise=
secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags,-
trash, clothing, etc.) 1s present in'the containment which could be transported-to the containment. sump and cause restriction of the 1
l pump suctions during LOCA conditions.
This visual' inspection shall-
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p be performed:-
1)
For all-accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and i
2)
. 0f the. areas affected within containment at the completion-of each containment entry when CONTAINMENT INTEGRITY is established.
d.
- At least once.per 18 months' by:
j 1)
Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that.with a simulated or actual Reactor Coolant' System pressure signal greater than
.or equal to 425 psig the interlocks prevent the valves ~from being' opened.
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"Valves may be realigned to place RHR System in service and for testing pursuant to Specification 4.4.6'.2.2.
- McGUIRE - UNITS 1 and 2 3/4 5-6 Amendment No.112(Unit 1)
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Amendment No. 94(Unit 2)
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