ML20011E530

Amend 46 to License NPF-43,revising Tech Specs to Reflect Deletion of Special Test Exceptions - Oxygen Concentration

ML20011E530
Person / Time
Site:	Fermi  (NPF-43-A-046, NPF-43-A-46)
Issue date:	11/28/1989
From:	Thoma J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20011E531	List: ML20011E530 ML20011E532
References
NUDOCS 9002160016
Download: ML20011E530 (13)

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UNITED STATES 7

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NUCLE AR CECULATORY COMMISSION WASHINGTON, D. C. 706M e...+

DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED f

DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 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, 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 conformity 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 Commission's regulations; i

D.

The issuance of this amendment will not be inimical to the common i

defense and security or 6 the health and safety of the public; and E.

The issuance of this em adment 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 amended to read as follows:

l Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised throu$

Amendment No. 46, 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.

9002160016 891128 PDR ADOCK 05000341 P

PDC

2-J 3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W

John 0. Thoma, Acting Director i

Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 28, 1989 h

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ATTACHMENT TO LICENSE AMENDMENT NO. 46 i

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 by Amendment number and contain a vertical line indicating the area of change.

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

REMOVE INSERT

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1 ix*

ix*

l x

x j

l xvi xvi l

3/4 3-61 3/4 3-61 3/4 3-62*

3/4 3-62*

i 3/4 6-57*

3/4 6-57*

3/4 6-58 3/4 6-58 3/4 10-5 3/4 10-5 3/4 10-6*

3/4 10-6*

B 3/4 10-1 B 3/4 10-1

" Overleaf page provided to maintain document completeness.

No changes contained in these pages.

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE i

3/4.8 ELECTRICAL POWER SYSTEMS l

3/4.8.1 A.C. SOURCES j

i A.C. Sources - Operating.............................

3/4 8-1 A.C. Sources - Shutdown..............................

3/4 8-9 3/4.8.2 D.C. SOURCES I

D.C. Sources - Operating.............................

3/4 8-10 i

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0. C. Source s - Shutdown..............................

3/4 8-13 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution -

Operating.............................

3/4 8-14 Distribution -

Shutdown..............................

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES A. C. Circuits Inside Primary Containment.............

3/4 8-16

)

l Primary Containment Penetration Conductor overcurrent i

Protective 0evicas.................

3/4 8-17 Motor-Operated Valves Thermal Overload Protection....

3/4 8-20 Reactor Protection System Electrical Power l

Mo n i to ri ng.........................................

3/4 8-2 5 i

Standby Liquid Control System Associated Isolation Devices...........................................

3/4 8-26 3/4.9 REFUELING OPERATIONS i

3/4.9.1 REACTOR MODE SWITCH..................................

3/4 9-1

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3/4.9.2 INSTRUMENTATION......................................

3/4 9-3 3/4.9.3 CONTROL ROD P051T10N.................................

3/4 9-5 3/4.9.4 DECAY TIME...........................................

3/4 9-6 3/4.9.5 COMMUNICATIONS.......................................

3/4 9-7 3/4.9.6 REFUELING PLATF0RM...................................

3/4 9-8 FERMI - UNIT 2 ix e

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

_PAGE

_ REFUELING OPERATIONS (Continued) 1 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L...............

3/4 9-9 3/4.9.8 WATER LEVEL - REACTOR VESSEL.........................

3/4 9-10 3/4.9.9 WATER LEVEL - SPENT FUEL STORAGE P00L................

3/4 9-11 l

3/4.9.10 CONTROL ROD REMOVAL i

Sfngle Control Rod Remova1...........................

3/4 9-12 Multiple Control Rod Remova1.........................

3/4 9-14 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1.....................................

3/4 9-16 Low Water Leve1......................................

3/4 9-17 3/4.10 SPECIAL'fEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................

3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM..........................

3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.......................

3/4 10-3 3/4.10.4 RECIRCULATION L00PS..................................

3/4 10-4 3/4.10.5 D E L E T E D.............................................

3 /4 10 - 5 l

3/4.10.6 TRAINING STARTUPS....................................

3/4 10-6 l

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i FERMI - UNIT 2 x

Amendment No. 46

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BASES SECTION i

PAGE i

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY...................

B 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM.....................

B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS..................

B 3/4 10-1 i

3/4.10.4 RECIRCULATION L00PS.............................

B 3/4 10-1 3/4.10.5 DELETED........................................

B 3/4 10-1 3/4.10.6 TRAINING STARTUPS..............................,

8 3/4 10 1 h

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FERMI - UNIT 2-xvi Amendment No. 46

.e TABLE 3.3.7.5-1 ACCIOENT 9mNITORING INSTMNGITATION 98f9519808 Af9LICABLE g

REQUIREDlil#WER CNAIMELS OPERATICIIRL q

INSTRupENT OF CNMOIELS OPENABLE CONDITIONS ACTICII 1.

Reacter vessel Pressere 2

1 1, 2 80 2.

Reactor Vessel tester Level, Fuel Zone 2

1 1, 2 80 3.

Suppression Chamber ideter Level 2

1 1, 2 80 4.

Suppression Chaser 18 ster Teaperature 2

1 1, 2 90 5.

Suppression Chamber Air Temperature 2

1 1, 2 80 g

6.

Suppression Chamber Pressere 2

1 1, 2 90 y

7.

Drywell pressure Wide Range 2

1 1, 2 30 O.

Drywell Air Temperature 2

1 1, 2 80 9.

Drywell Daygen Concentration 2

1 1, 2 90

10. Drywell flydrogen Concentration 2

1 1, 2 90

11. Safety / Relief Valve Positten Indica *ws 1*/ valve 1*/ valve 1, 2 08

12. Containment Nigh Range Radiation Ob..ter 2

2 1,2,3 81 l

g

13. Standby Gas Treetsent System Radiation leonit. ors **

2 2

1,2,3 81 E

14. flestron Flest 2

1 1, 2 S8 85

15. Drywell Samp Level 2

1 1, 2 80 16.

Primary Contaissent Isolatten Valve Position 1/ valve 1/ valve 1, 2, 3 80 5

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• Pressure switch

• • High (accident) range noble gas monitors (One chonnel per flew path) l

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-l TABLE 3.3.7.5-1 (Continued) f

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ACCIDENT K.dTORING INSTRUMENTATION I

ACTION $TATEMENTS i

ACTION 80 -

With the number of OPERABLE accident monitoring instrumntation a.

channels less than the Required Number of Channels sht.wa 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements i

of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN i

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 81 -

With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for eestoring the system to OPERABLE status.

4 FERMI - UNIT 2 3/4 3-62 Amendment No. 28

CONTAINMENT SYSTEMS i

'3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL DRYWELL AND SUPPRESSION CHAMBER HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.3 Two independent drywell and suppression chamber hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION: With one drywell and/or suppression chamber hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.6.1 Each drywell and suppression chamber hydrogen recombiner system shall be demonstrated OPERABLE:

At least once per 6 months by verifying during a recombiner system a.

functional test that the heater outlet gas temperature increases to greater than or egaal to 1150'F within 75 minutes and is main-tained for at least I hour.

i b.

At least once per 18 months by:

1.

Performing a CHANNEL CALIBRATION of all recombiner operating instrumentation and control circuits.

2.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test within 60 minutes following the above required functional test.

The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

3.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e, loose wiring or structural connections, deposits of foreign materials, etc.

c.

By measuring the system leakage rate as a part of the overall inte-grated leakage rate test required by Specification 3.6.1.2.

FERMI - UNIT 2 3/4 6-57

CONTAINMENT SYSTEMS D_R_YWELL AND SUPPRESSION CHAMBER OXYGEN CONCENTRATION LIMITING CONDITION FOR OPERATION 3.6.6.2 The drywell and suppression chamber atmosphere oxygen concentration shall be less than 4% by volume.

APPLICABILITY:

OPERATIO,NAL CONDITION 1, during the time period:

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is greater than 15% of RATED a.

THERMAL POWER, following startup, to b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing THERMAL POWER to less than 15% of RATED THERMAL POWER, preliminary to a reactor shutdown.

ACTION:

With the drywell and/or suppression chamber oxygen concentration exceeding the limit, restore the oxygen concentration to within the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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SURVEILLANCE REQUIREMENTS 4.6.6.2 The drywell and suppression chamber oxygen concentration shall be verified to be within the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is greater than 15% of RATED THERMAL POWER and at least once per 7 days thereafter, l

FERMI - UNIT 2 3/4 6-58 Amendment No. 46 we;.;

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4 THIS PAGE INTENTIONALLY DELETED.

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FERMI'- UNIT 2 3/4 10-5 Amendment No. 3,46

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l SPECIAL TEST EXCEPTIONS 3/4.10.6 TRAIN 1HG STARTUP_5 l

L LIMITING CONDITION FOR OPERATION L

3.10.6 - The provisions of Specification 3.5.1 may be suspended to permit one L.

RHR. subsystem to be aligned in the shutdown cooling mode durig training L

startups provided that the reactor vessel is not pressurized THERMAL POWER l-is less than or equal to 1% of RATED THERMAL POWER and reactor coolant temperature is less than 200'F.

f APPLICABILITY: OPERATIONAL CONDITION 2, during training startups.

i ACTION:

With the requirements of the above specification not satisfied, immediately place the rearter mode switch in the Shutdown position.

l SURVEILLANCE REQUIREMENTS 4.10.6 The reactor vessel shall be verified to be unpressurized and the THERMAL POWER and reactor coolant temperature shall be verified to be within the limits at least once per hour during training startups.

FERMI - UNIT 2 3/4 10-6 T-

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'3/4.10 SPECIAL TEST EXCEPTIONS BASES l

3 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY The requirement for PRIMARY CONTAINMENT INTEGRITY is not applicable during the period when open vessel tests are being performed during the low power PHYSICS TESTS.

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM In order to perform the tests required in the technical specifications it is necessary to bypass the sequence restraints on control rod movement.

The

. additional surveillance requirements ensure that the specifications on heat generation rates and shutdown margir requirements are not exceeded during the period when these tests are being performed and that individual rod worths do not exceed the values assumed in the safety analysis.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality is properly monitored and controlled.

These additional restrictions are specified in this LCO.

3/4.10.4 RECIRCULATION LOOPS' i

This special test exception permits reactor criticality under no flow conditions and is-required to perform certain startup and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.6 TRAINING STARTUPS This special test exception permits training startups to be performed with the reactor vessel depressurized at low THERMAL POWER and temperature while controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode in order to minimize contaminated water discharge to the radioactive waste disposal system.

2 FERMI - UNIT 2 B 3/4 10-1 Amendment No. 46 i

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