ML20059F171
| ML20059F171 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/30/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F174 | List: |
| References | |
| NUDOCS 9009110121 | |
| Download: ML20059F171 (6) | |
Text
{{#Wiki_filter:E 2 3 + 7s, y. U i N[:[,qne;' -. + UNITED STATES -
- c' 8.
NUCLEAR REGULATORY COMMISSION : i n-j ?1 -{ . WASHINGTON, D. C. 20555 * .j DETROIT EDISON COMPANY' j DOCKET NO. 50-341 g FERMI-2 j -AMENDMENT TO FACILITY OPERATING LICENSE q Amendment No. 55' license Not NPF-43 u 7 1. The Nuclear Regulatory Comission (the Comission) has found that:L A. The application for amendment by the Detroit Edison Company (the i licensee)datedSeptember 21, 1988,. complies with the'-standards and a requirements of the Atomic ~ Energy Act of 1954, as amended (the Act).. l and the Comission's: rules and regulations set forth in.10 CFR f Chapter'I; b 'B. The-facility will operate in conformity with the application,-the - j provisions of the Act. and the rules and regulations of the-l Comhsion; j C. There-is reasonable assurance (1) that'the activities authorized-by this amendrent can be conducted without endangering the health and safety of the public, and.(11) that such activities will be conducted in compliance with the Comission's regulations; e c D.- The' issuance of-this amendment will not be inimical' to the comon~. defense and security or to-the health and safety of the public; and. 7 'E. The issuance of this amendment is in accordance with 10 CFR Part 51 of h the Commission's regulations and'all applicable re_quirements have been 7, satisfied. ~ j r 2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to ~ read as fo11cws: Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 55, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, t 900911012. 900830 PDR ADOCK 05000341 -4 P PDC . _,. ~ -. _ _ _. -
a,.. D,:' ' l 7, i m. i
- i) 7
- i[.,- $..^
, el ~, n r. e.-!;q { \\ <, f[ Ecv 3; This literis'e ' amendment is effective as of the~ date of its issuance.? t ,, o 2-FOR THE NUCLEAR REGULATORY COMMISSION- .u. (,, w J ^ r:- Robert C. Pierson,' Director . Project Directorate.III-1: 7 Division of Reactor Projects - III.- IV, V & Special Projects ',V:; 20ffice of-Nuclear Reactor Regulation a-e- t
Attachment:
Che.ris,es, to' the ' 'echnical Specifications Dat'e'of Issuerce: August 30, 1990 l 4 j t 6
- Y tr, I.'
e 1, j -:\\ _ 1 + l g a 4 ,f. n
,l :
- n
!![- i 'll i i
- i y *k _ -
.. ~ <n. ATTACHMEllT 10 LICENSE AMENDMENT NO. sn - y;+ I 2 ' FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace-the followingD>aget, of the Appendix "A". Technical Specifications with .the attached pages.> Tie revised pages are identified by Amendment number and Leontain a vertical line indicatum the-area of change. _The corresponding overleaf pages are also providec to maintain document completeness.- ' REMOVE INSERT '3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33
- 3/4 3-34
- 3/4 3-34 o
i 4 }'
- 0verliiT~pahiprovidedtomaintaindocumentcompleteness.
No changes contained in these pages.
m; i. y.1 y _T_H_S_T_RUMElsT ATION 3/4.3.4-ATWS, RECIRCULATION,PlHP TRIP SYSTEM _ INSTRUMENTATION .l.)!!.TJ!i,G,,Cp!:JDITION_ F0,R,,0P,E, RATIO!!,, _ ) T 3.3.4 The anticipated transient without scram. recirculation pump trip (ATWS-RPT): system instrumentation channels shown in Table 3.3.4-1 shall be OPERABLE with-their trip setpoints. set consistent with the values shown in the Trip Setpoint.
- column'of Table 3.3.4-2.
' APPLICABILITY: OPEPliTIONAL CONDITION 1. N ' ACTION: a.- With an ATWS-RPT system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Yalues column of. Table 3.3.4-2, declare the channel inoperable until the channel is. restored,to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value, b. With the number of OPERABLE channels.one less than required by.the-I Pinimum OPERABLE Channels per Trip System requirement for one or imth trip systen.s, place the inoperable channel (s) in the tripped condition within 1 hour. c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip Systen, requirement for one trip system and: 1. If the inoperable channels consist of one reactor vessel water i level channel and cne reactor vessel pressure channel, place both inoperable channels in the tripped condition v' thin 1 hour, cr, if this acticr, will initiate a pump trip, declare the trip system inoperable. i 2. If the. inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperabic. d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours or be in at-1 cast STARTUP within the next 6 hours. e.- With both trip systems inoperable, restore at least one trip system to OPERABLE status within 1 hour or be in at least STARTUP within the next 6 hours. S l!P.Y EJ,L,L,A!;,C E,,R,E,Q U I R EM E HT S 4.3.a.1 Each ATHS-RPT systern instrumentation channel shall be derronstrated OPERAELE by the perforrrance of the CHAllHEL CHECK, CHAllHEL FUNCTIONAL TEST ar.d CHANNEL CALIBRATION operations at the ftequencies shewn in Table 4.3.4-1. 4.3.4.2 LOCIC SYSTER FUNCTIONAL TESTS and simulated automatic operatfon of all channels shall be performed at least once per 10 months. FLRMI - UNIT 2 3/4 3-32 Amendn'ent No. 3E, 55
7 ~ ~ = y .:n. x.=.: g :. q7.=. y:. ..: - j ~ L. ~-. .( p '~ ~ .p .n.; lT N Ib m - Q ~ TABLE 3.3.4 '~ . z.. .. ' G a; e t-li
- ATWS RECIRCULATION PLEP TRIP SYSTEN INSTRUMENTATION-
.z: C$ iMINIMUM OPERABLE ~ CHANNELS PER. TRIP FUNCTION: . TR.IP SYS.T.E.M_*- l 1.. Reactor Yessel' Low Water Level - 2 E Level 2-i l 2. ' Reactor' Vessel Pressure-High 2 w1 4' ww u .e h* - 3
- 0ne channel may be placed in an. inoperable' status' for up to 2 hours for. required surveillance provided
.E the other channel-of the same trip lfurction.is OPERABLE ~ f ^ ~ ? ~. .--m .#.m.,. ....rm. m.. ,.y-% .m._. ^ '-
- ~_
.__,.im....L .m.-. .lM
~ qqjQ, >.
- ~
j J4: g a . TABLE'3.3.4-2 ~
- o
.ATWS RECIRCULATION' PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS z' TRIP-ALLOWABLE ec - E TRIP FUNCTION' SETPOINT VALUE' w m 1. Reactor Vessel Low Water Level - 1 110.8 inches
- 1 103.8 inches.
Level 2 2.. -Reactor Vessel Pressure-High 5 1133 psig. 5115's psig -+ V w N ^ w k
- See Bases Figure B3/4 3-1.
l _a..._.._ ., ~..,,. _ _ , _ _a ....}}