ML20059J256

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Amend 56 to License NPF-43,revising List of Required Accident Monitoring Instrumentations to Eliminate Confusion W/Tech Spec & Better Reflect Facility Compliance W/ Regulatory Requirements
ML20059J256
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 09/10/1990
From: Pierson R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059J260 List:
References
NUDOCS 9009190235
Download: ML20059J256 (6)
v • d • e


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UMTED STATES NUCLEAR NEGULATORY COMMISSION-l-

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- WASHINGTON, D. C. 20566 k.....,/

L DETROIT EDISON COMPANY l

_ DOC _KET NO. 50-341 i

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E.ELDt(EjlT,T,0,fACJQT,YJPE, RATING LICENSE PE A Amendnent No. 55 License No. NPF-43 a

1.

The Nuclear ~ Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the. Detroit Edison Company (the licensee) dated November 15, 1988~:as supplemented November.16, 1989, complies with the standards and re Energy Act of 1954, as amended-(the Act)quirements of.the Atomic-

, and. the Comission'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

- Comis sion; 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 corpliance with the Comission'_s regulations; D.

The issuance of this amendment will not beiinimical to the comon-4 defense and security or to the health and safety of the public; and l'

E.

The issuance of this amendment is in accordance with'10 CFR Part 51 of the Cor.. mission's regulations and all applicable requirements have been -

satisfied.

2.

- Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license. amendment and paragraph _

F 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

. Technical Specifications and Environmental Protection Plan l

The Technical Specifications contained in Appendix A as revised.through Amendn;ent No. 56, 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.

L 9009190235 900910 PDR ADOCK 05000341 p

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- 3. - Tt,is licttise anetidsent is effectiveas of its date of issuntice with full I

irpien.entatier, within 30 days of the d6te of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION-w4 (g

gbert C. P rson, Director oject Directorate 111-1 Division of Reactor Projects.- III, ilV, V;& Special Projects-i Office:of Nuclear-Reactor Regulation t

At tochtrert:

Cbtr.ses to the Technical Spcificatic.ns.

Cate of Issuar.ce: September 10, 1990

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E6.CHMENT T,0 LICENSE AMENDMENT NO. '56 FACILITY dPEf?ATING LICENSE NO. NPF-43 DOC,KET NO. 50-341 Replace the following > ages of the Appendix "A" Technical Specifications with the attached pages<

T1e revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

i REMOVE INSERT 3/4 3-61 3/4 3-61 7

3/4 3-62 3/4 3-62 3/4 3-63 3/4 3-63 e

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TABLE 3.3.7.5-1

.Aff.l.0,Ep,1,M,h,( )}@,1,R,t?,Epp))IpN I 5 MikIMLH AFPLICAELE F:EQUIRED t.tCBER CHANNELS '0FEFATIONAL l hS1kttE.h.T --OF CHAN.N.E.L.S.. OPERABLE-CONDITIONS ACTION e = { 1. Reactor V(ssel Pressure 2 1 1, 2

80' ro 2.

Reactor Versel Water Level l a. Fuel Zone 2 1 1, 2 80 b. Wide Range 2 1 1, 2 80 3. Siippression Chanber Water Level 2 1 1, 2 80 4 Suppression Chanber Water Tttperature .2 1-1, 2 80 5. . Suppression Chamber Air Temperature 2 ~ 1 1, 2 80 6. Suppression Chanber Pressure 2 1 1, 2 80 1 7. Drywell Pressure, Wide Range 2 1 1, 2 80 [ 8. Drywell Air Temperature L2 1 1, 2 80

9..

Drywell Oxygen Concentration - 2 1 '1, 2 ~ 80

10. Drywell Hydrogen Concentratier.

'2 1 1,' 2 80

11. Safety / Relief Valve Position Indicators :

1*/ valve 1*/ valve 1, 2 80 -l

12. Containment High Range Radiation Monitor 2

2 1,' 2, 3 81

13. Standby Gas Treatment System Radiation Monitors **

2 2 1, 2, 3 --. 81 14 Neutron Flux

15. Deleted
16. Primary Containment ' Isolation Valve 1/ valve 1/ valve 1

2, 3. 82 3 g Position co. I

  • Pressure switch
    • lligh (accident) range ncble gas aonitors (one channel per flow path)

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I' TABLE 3.3.7.5-1 (Continued); ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 - a. . With the number of OPERABLE accident _ monitoring instrunentation' ) channels less than the Required Number of Channels shown'in Table 3.3.7.5-1. restore the inoperable channel (s) to OPERABLE. status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours. 3 b. With the number of OPERABLE accident monitoring instrumentation: ' channels less than the Minimum Channels OPERABLE requirements. 4 of Table 3.3.7.5-1, restore the inoperable channel (s)'to OPERABLE status within 48 hours or be-in at least HOT SHUTD0VN' within the next 12' hours. ACTION 81 - With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements,linitiate the prep (s)nn la alternate method of= monitoring the appropriate parameter within 72 hours, and: 1) either restore the inoperable channel (s) t'o OPERABLE status within 7-days of, the event, or 2) prepare and submit a Special. Report to the Corrsissicn pursuant to Specification 6.9.2 within 14 days following the-event outlining the action' taken, the cruse'of the _ inoperability and thelplans arid schedule for restoring the system to OPERABLE status. ACTIOP P2 - With the number of.0PERABLE accident monitoring instrumentation channels less than required by the Minimum Channels 0PERABLE' requirements of Table 3.3.7.5-1, within'4B hours either: a. Restoretheinoperablechannel(s)toOPERABLEstatus,- or b. Declare the affected isolation valve inoperable'and take the ACTION specified by. Specifications 3.6.3 ACTION a. .p ? l y FERMI - UNIT 2 3/4 3-62 Amendment No. 28, 56

l: TABLE 4.3.7.5-1 '? ACCIDENT MONITORING INSTRUMENTATION SUP.VEILLANCE REQUIREMENTS mz APPLICABLE CHANNEL CHANNEL OPERATIONAL INSTRUMENT CHECK CALIBRATION CONDITIONS 1. Reactor Vessel Pressure 'M -R 1, 2-2. Reactor Vessel Water Level i 3 a. Fuel Zone M R 1, 2 b. Wide Range .M R 1'2 3. Suppression Chamber Water Level M R 1, 2 4. Suppression Chamber Water Temperature M R. 1, 2 5. Suppression Chamber Air Temperature M .R 1, 2 6. Suppression Chamber Pressure M R 1,'2 i 7. Drywell Pressure, Wide Range M R 1, 2. 8. Drywell. Air Temperature M .R-1, 2 w 9. Drywell Oxygen Concentration _ M 'R' 1, 2 10. Drywell Hydrogen Concentration M -Q' 1, 2 'I I' 11. Safety / Relief Valve. Position Indicators M-R- 1,E2.: m 12. Containment High Range Radiation Monitor M R** 1, 2, 3 { 13. Standby Gas Treatment System Radiation Monitors *** M R 1, 2,'3 14. Neutron Flux 'M R 1, 2~ 15. Deleted l 16. Primary Containment' Isolation Valve Position M> R 1,2,3 E

  • Using sample gas'containing:

il a. One volume percent hydrogen, balance. nitrogen. b. Four volume percent-hydrogen, balance nitrogen. S

    • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not' including the

] detector, for range' decades ~above 10 R/hr.and a one point calibration check of the' detector below = '10'R/hr with an installed or portable gamma source. s 4 m 3.-

      • High (accident) range noble gas monitors.

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