ML20248A895

Amend 34 to License NPF-43,revising Tech Specs to Reflect Design Mod to Reactor Bldg Railroad Bay Airlock Doors

ML20248A895
Person / Time
Site:	Fermi
Issue date:	05/31/1989
From:	De Agazio A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248A900	List: ML20248A895 ML20248A903
References
NUDOCS 8906080222
Download: ML20248A895 (8)

Text

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UNITED STATES l

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g NUCLEAR REGULATORY COMMISSION

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j WASHINGTON, D. C. 20555 i

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DETROIT EDISON COMPANY

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i WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED l

DOCKET NO. 50-341 4

FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3a 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 April 21, 1989, 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 CF.R' Chapter I; B.

The facility will operate in conformity with the aphiication, the provisions of the Act, and the rules and regulations of the Commission; t

C.

There is reasonable assurance (1) 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; 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 amendment is in accordance with 10 CFR Part 51 of i

the Commission's regulations and all applicable required;ents have been I

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:

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l Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, 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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This license amendment is effective as of the date of its issuance.

The Technical Specifications are to become effective within 10 days of receipt

of.this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION l!

Albert, eAgazio, Actin Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation i

Attachment:

f Changes to,the Technical Specifiedtio.ns D. ate of Issuente: May 31, 1989 I

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ATTACHMENT TO LICENSE #4ENDMENT NO. 34 FACILITY OPERATING LICENSE N0. NPF-43

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DOCKET NO. 50-341 l

Replace the following pages

' the Appendix "A" Technical Specifientions 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.

l PEMOVE INTERT i

1-5*

1-5*

1-6 1-6 3/4 6-51 3/4 6-51 i/4 6-51a 3/4 6-52*

34 6-52*

a-t l

• 0verleaf page provided to maintain documer,t completeness.

l No changes on this page.

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. DEFINITIONS.

2.

Closed by at least one manual valve, blank flange, or deactivated automatic valve secured in its closed position, except as provided in Table-3.6.3-1 of Specification 3.6.3.

, b.

All primary containment equipment hatches are closed and sealed.

c.

Each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.

d.

The primary containment leakage rates are within the limits of Specification 3.6.1.2.

e.

The suppression chamber is in compliance with the requirement of.-

Specification 3.6.2.1.

f.

The' sealing mechanism associated with each primary containment penetration, e.g., welds, bellows, or 0-rings, is OPERABLE.

~

g.

'The_ suppression chamber to reactor building vacuum breakers are in compliance with Specification 3.6.4.2.

.THE PROCESS CONTROL PROGRAM 1.30 The PROCESS CONTROL PROGRAM (PCP) shall contain the provisions'to assure that the SOLIDIFICATION of wet radioactive wastes results in a waste form with properties that meet the requirements of 10 CFR Part 61.and of low-level radio-active waste disposal sites.

The PCP shall identify process parameters influencing SOLIDIFICATION, such as pH, oil content, H 0 content, solids content, p

ratio of solidification agent to waste and/or necessary additives for each type-V of anticipated waste, and the acceptable boundary conditions for the process parameters shall be identified for each waste type, based en laboratory scale and full scale testing or experience.

The PCP shall also include an identi-fication of conditions that must be satisfied, based on full scale testing, to assure that dewatering of bend resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10 CFR Part'61 and of low-level radioactive waste disposal sites.

PURGE - PURGING 1.31 PURGE or PURGING is the controlled process cf discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER

'1.32 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3292 MW.

FERMI - UNIT 2 1-5

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DEFINITIONS REACTOR PROTECTION SYSTEM RESPONSE TIME t

1.33 REAC10R PROTECTION SYSTEM RESPONSE TIME shall be the time interval from l

when the monitored parameter exceeds its trip setpoint at the channel sensor l

until de energization of the scram pilot valve solenoids.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

REPORTABLE EVENT 1.34 A REPORIABLE EVENT shall be any of those conditions specified in Section i

50.73 to 10 CFR Part 50.

R00 DENSITY 1.35 R0D DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches.

All rods fully inserted is equivalent to 100% R0D DENSITY.

SECONDARY CONTAINMENT INTEGRITY 1.36 SECONDARY CONTAINMENT INTEGRITY shall exist when:

A11 secondary containment penetrations required to be closed' during i

a.

accident conditions are either:

1.

. Capable of being closed by an OPERABLE secondary containment automatic isolation system, or 2.

Closed by at least ane manual velve, blind flange, or deactivated automatic damper secured in-its cloged position, except as providad in Table 3.6.5.2-1 of Specification 3.6.5.2.

b.

All secondary containment hatches and blowout panels are closed and sealed.

t c.

The standby gas treatment system is in compliance with the requirements of Specification 3.6.5.3.

d.

At least one door in each access to the secondary containment is r

closed (except as noted in item g below).

l The sealing mechanism associated with each seconaary containment e.

penetration, e.g., welds, bellows or 0 rings, is OPERABLE.

f.

The pressure within the secondary containment is less than or equal to the value required by Specification 4.6.5.1.a.

g.

Both railroad bay access doors are OPERABLE and closed except for ingress and egress or testing as specified by Specification 3.6.5.1.

SHUTDOWN MARGIN 1.37 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subcritical or would be subtritical assuming all control rods are fully inserted except for the single control rod of highest reactovity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e., 68 F; and xenon free.

SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise contrclied, by the licensee.

FERMI - UNIT 2 1-6 Amenament No. 34

CONTAINMENT SYSTEMS 3/4.63 ' SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY # shall be maintained.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION:

Without SECONDARY CONTAINMENT INTEGRITY (for reasons other than one

[

a.

railroad bay access door inoperable or open greater than. allowed by #):

1.

In OPERATIONAL CONDITION 1.-2, or 3, restore SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

-2.

10 Operational Condition

, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Speci.fication 3.0.3 are not applicable.

b.

Without SECONDARY CONTAINMENT INTEGRITY because of one railroad bay access door inoperable or open for greater than allowed by #:

1.

In OPERATIONAL CONDITION 1, 2, or 3, restore SECQNDARY CONTAINMENT INTEGRITY by restoring both railroad bay access doors to OPERABLE and closed 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

In OPERATIONAL CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

"When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

1. 0ne railroad bay access door may be open for up to four hours at a time for ingress and egress or testing, or up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for new fuel receipt activities, provided the other door is OPERABLE and closed.

i FERMI - UNIT 2 3/4 6-51 Amendment No. 34

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.5.1 SECONDARY CONTAINMENT IRTEGRITY shall be demonstrated by:

Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the vacuum within the secondary a.

containment is greater than or equal to 0.125 inch of~ vacuum water gauge.

b.

Verifying at least once per 31 days that:

1.

All secondary containment equipment hatches and pressure relief doors are closed and sealed, and both railroad bay access doors are closed and sealed.

2.

At least one door in each access to the secondary containment is closed.

3e All secondary containment penetrations not capable of being tlosed by OPERABLE secondary containment automatic isolation dampers / valves and required to be closed during accident ronditions are closed by valves, blenk flanges, or deactivated automatic dampers / valves secured in the closed position:

At least once per 18 months:

c.

l 1.

Verifying that one standby gas treatment-subsystem will draw down the secondary containment to greater than or equal to 0.25 inch of vacuum water gauge in less than or equal to 567 seconds at a flow rate not exceeding 3800 cfm, and 2.

Operating one standby gas treatment subsystem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and main-taining greater than or equal to 0.25 inch of vacuum water gauge in the secondary containment at a flow rate not exceeding 3000 cfm.

FERMI - UNIT 2 3/4 6-51a Amendment No. 34

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CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.2-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *.

ACTION:

With one or more of the secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 inoperable, maintain at least one isolation damper OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:

a.

Restore the inoperable damper (s) to OPERABLE status, or b.

Isola'te each affected penetration by use of at least one deactivated damper secured in the isolation position, or Is$lateeachaffectedpenetrationbyuseofatleastoneclosed

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c.

manual valve or blank flange.

Otherwise, in OPERATIONAL CONDITION 1, 2, or 3, be in at feast 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

,0therwise, in Operational Condition

, suspend handling of irradiated

~ fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.5.2 Each secondary containment ventilation system automatic isolation damper shown in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

a.

Prior to returning the damper to service after maintenance, repair, or replacement work is performed on the damper or its associated actuator, control or power circuit by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation time.

b.

During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation damper actuates to its isolation position.

c.

By verifying the isolation time to be within its limit when tested pursuant to Specification 4.0.5.

• When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

FERMI - UNIT 2 3/4 6-52

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