Text

Amend 73 to License NPF-43,clarifying Accident Monitoring Instrumentation Requirements of TS to Eliminate Confusion W/ Current TS & to Better Reflect Compliance W/Regulatory Requirements
	ML20077N896
Person / Time
Site:	Fermi
Issue date:	08/05/1991
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20077N898	List: ML20077N896; ML20077N900;
References
	NUDOCS 9108150146
	Download: ML20077N896 (10)
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UNITED STATES NUCLEAR REEULATORY COMMISSION nAsHHWGTON, D C 30886

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DETROIT EDISON-COMPANY FERMI-2 DOCKET NO. 50-341 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-43 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (the licensee) dated-November 15, 1988 as supplemented November 16, 1989 and September 11,_1990, 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 conTormity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 compliance with the Comission's regulations; 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 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 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 amerided to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, 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.

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3. -This license amendment-is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY-COMMISSION L. B. Marsh, Director Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear-Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August'5, 1991 l:

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ATTACHMENT TO LICENSE AMENDMENT-NO. 73 FACILITY OPERATING LICENSE NO.- NPF-43' DOCKET NO. 50-341

- Replace the following-pages of-the Appendix "A" Technical Specifications with the-attached'pages. The revised pages are identified.b contain a vertical line indicating the area of. change. y Amendment number and

-The corresponding-overleaf pages are also provided to maintain document completeness.

REMOVE IMEERT-3/4 3-61 3/4 3-61 3/4 6-61a 3/4 3-63 3/4 3 '

3/4 6-63a 3/4 3 77 3/4 3-77

3/4 3-78

3/4 3-78 3/4 3-80 3/4 3-80 L

L

'overleat page provided to maintain document completeness. No changes

. contained-in these pages.

^

TABLE 3.3.7.5-1 m

i ACCIDENT MONITORING INSTRUMENTATION l

5 1

MINIMt#1 APPLICABLE j

3 REQUIRED NUMBER CHANNELS OPERATIONAL m

INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION 1.

Reactor Yessel Pressure 2

1 1, 2 80 1

2.

Reactor Yessel Water Level a.

Fuel Zone 2

1 1, 2 80 l

b.

Wide Range 2

1 2, 2 80 3.

Suppression Cha~ er Water level 2

I, 2 80 4.

Suppression Chamber Wate,' Temperat:re 2

1 1, 2 80

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5.

Suppression Chamber Air Temperature 2

I 1, 2 80 6.

Suppression Chamber Pressure 2

1 1, 2 80 7.

Drywell Pressure, Wide Range 2

I 1, 2 80 k

8.

Drywell Air Temperaturt 2

1 1, 2 80 E

9.

Drywell Oxygen Concentration 2

1 1, 2 80 g

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10. Drywell Hydrogen Concentration 2

I 1, 2 80 P

II. Safety,7elief Yalve Position Indicators 1*/ valve 1*/ valve 1, 2 80

%?

17 Containment High Range Radiation Monitor 2

2 1, 2, 3 81 w?

M.

Pressure switch

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g-TABLE 3.3.7.5-1 (Continued)

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ACCIDENT MONLTORING INSTRUMENTATION i~

EZ MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIOML INSTRUNENT

~

._ OF CHANNELS OPERABLE CONDITIONS ACTION

]

i; 13.. Standby Gas Treatment System Radiation Monitors.

4 t

SGT5 - Noble Gas-(Low-range)'

1/0PERA8tE I/0PERA6LE 1, 2. 3 81

[

a.-

SGTS subsystem SGTS subsystem b..

'SGTS - Noble Gas (Mid-range) 1/0? ERA 8tE

. - 1/0PEM8tE 1, 2, 3 81 SGTS subsystem SGTS subsystem SGIS - AIM-Noble Gas (Mid-ranga) 1/0PERA8tE 1/CPEMBLE 1, 2, 3 81 c.

R SGT5 subsystem SGTS subsystem y

d.-

SGTS - AXM-Neble Gas (High-range)

I/cPERA8tE 1/0PERA8tE 1, 2, 3 81 3

5G15 subsystem SGTS subsysten

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14. Meutron Flux 1

2.

I 1, 2 80

15. Deleted 4

N i

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16. Primary Centainment Isolation Valve Position 1/ valve 1/ valve 1, 2, 3 82 t

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' TABLE 4.3.7.5-1 1-i 3!

ACCIDENT MONITORING iMSTRtMENTATION SURVEILLANCE REQUIREMENTS APPLICABLE CHANNEL CHANNEL OFERATIONAL E

INSTRUMENT

_ CHECK CALIBRATION CONDITIONS a

~

1.

Reactor Yessel Pressure M

R 1, 2 2.

Reactor "essel Water level a.

Fuel Zone M

R 1, 2 b.

Wide Range M

R I, 2 -

l 3.

Suppression Chamber Water level M

R 1, 2 4.

Suppression Chamber Water Temperature M

R 1, 2 i

5.

Suppression Chamber Air Temperature M

R 1, 2 1

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Suppression r.hamber Pressure M

R 1, 2 4

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7.

Drywell Press;re, Wide Range M

R 1, 2 8.

Drywell Air Temperature M

R 1, 2 9.

Drywell Oxygen Concentration M

R 1, 2

10. Drywell Hydrogen Concentration M

Q*

1, 2

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11. Safety / Relief Valve Position Indicators M

R 1, 2 4

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12. Containment High Range Radiation Monitor M

R**

1, 2, 3 o

A e+

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Using sample gas containing:-

One volume percent hydrogen, balance nitrogen.

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b.

Four volume percent hydrogen. balance nitrogen.

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- CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the j

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.

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TABLE 3.3.7.12-1 E

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RADI0 ACTIVE GASEOUS EFFLUENT MONITORIE INSTRUMENTATION c

5 4

w MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION m

i t

1.

REACTOR BUILDIE EXHAUST PLENUM 1..

EFFLUENT MONITORIE SYSTEM a.

Noble Gas Activity Monitor -

i Providing Alarm 1

121 b.

Iodine. Sampler 1

122 >

c.

Particulate Saapier I

122 w1 d.

Sampler Flow Rate Monitor I

123 i

w 4

2.

OFFGAS MONITORI E SYSTEM (At the 2.2 minute delay piping) 4 a.

Hydrogen Monitor 1

124 b.

Noble Gas Activity Monitor I

126 4

3.

STAMOBY GAS TREATMENT SYSTEM i

F a.

Noble Gas Activity Monitor 88 -

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Providing Alaru I

f 125 2

b.

Iodine Sampler 1

122 y

c.

Particulate Sampler 1

122 y

d.

Sampler Flow Rete Monitor 1

123 0

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' TABLE 3.3.7.12-1 (Continued) m 3E j

7 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION-E U'

MINIMUM CHANNELS

-INSTRUMENT' OPERABLE APPLICA8ILITY ACTION i

'4.

TURBINE BLOG. VENTILATION MONITORING SYSTEM 121' a.

Noble Gas Activity Monitor I

b.

Iodine Sampler 1

122 j

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Particulate Sampler 1'

122-i i

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Sampler Flow Rate Monitor i

123 i

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5.

SERVICE BUILDING VENTILATION MONITORING g

SYSTEM

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a.

Noble Gas Acttv1ty Monttor 1

121 i

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122 c.'

Particulate Sampler 1

122 d.'

Sampler Flow Rate Monitor I

123 f

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1/.01E 3.3.7.12 1 (continued) l 1&E( NOTAT10M

At all times.

- During main condenser offgas treatment system operation.

"During operation of the main condenser air ejector.

8 During operation of the standby gas treatment system.

88 Also included in Table 3.3.7.5-1, item 13.a.

l ACTION STATEMENTS ACTION 121 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 122 With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABl.E requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2 1.

ACTION 123 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 124 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Otherwise, f,uspend release of radioactive effluents via this pathway.

ACTION 125 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, suspend relcase of radioactive effluents via this pathway.

ACTION 126 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via this pathway to the environment may continue for up to 7 days provided that:

a.

The offgas system is not bypassed, and b.

The reactor building exhaust plenum noble gas effluent (downstream) monitor is OPERABLE; Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

FERMI - UNIT 2 3/4 3 80 Amendment No. //,73 1

_.

ML20077N896

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