ML20127N337

Application for Amend to License DPR-9,reflecting Extension of Expiration Date for Possession Only License Until Mar 2025.Safety Evaluation & Status Description Encl

ML20127N337
Person / Time
Site:	Fermi
Issue date:	05/15/1985
From:	Jens W DETROIT EDISON CO.
To:
Shared Package
ML20127N333	List: ML20127N330 ML20127N337
References
NUDOCS 8505230495
Download: ML20127N337 (19)

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UNITED STATES'OF AMERICA BEFORE THE NUCLEAR REGULATORY COMMISSION

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.- In the matter of )

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THE DETROIT EDISON COMPANY ~) Docket No. 50-16

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.(Enrico Fermi Atomic Power )

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Plant Unit No. 1) )

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APPLICATION TO EXTEND LICENSE Pursuant to Section 50.90 of the Rules ~and Regulations of the Nuclear Regulatory Commission (" Commission"), the

~ Detroit Edison Company'(" Detroit Edison") requests the NRC to revise Edison's " Possession Only" License (License No.

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DRP-9) for Enrico Fermi l'to reflect an extension beyond the current expiration date.' The current Fermi License expires

. onLJune 30, 1985.-

_ .. Edison requests thatEthe License be extended for 40 years to

- expirelin March'2025,1at.which time it is~ currently intended that all : residual. activity. willi be removed and the License terminated. .The extension will allow Fermi-1 to be maintained in its present safe storage condition.

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~ The extension will not.present a:significant hazards concern .,

as defined-in 10CFR50.92(c). The radiological. state of the

- facility"is becoming more progressively benign due to decay

of residual radioactivity. Furthermore, the current ~

Technical Specifications provide for maintaining the.

4 facility in a manner that assures the health and safety of

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the public will not be endangered. In adJition, no irreversible consequences are anticipated with the-extension. On the contrary, the extension-allows Detroit Edison the. option.to pursue the best available alternatives for the. final decommissioning of the facility. The safety evaluation in support of the application is included in AttachmentJ1.

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T EThe presentEstatus of the-facility including description, .

' current radiation levels, surveillance program,

administration and procedures are-delineated in Attachment 2 c in' support of this application.

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'WHERFFORE, Applicants. request that the Possession Only.

License DRP-9 be extended as requested herein.

IN WITNESS WHEREOF, The-Detroit. Edison Company, has

- caused ~its name to be signed hereunto by its Vice President,

' Wayne H. Jens, this 20d day of May, 1985.

THE DETROIT EDI N COMPANY BY vv

. t: W. H. Jens Vice President Nuclear Operations

Pago 4

-I WAYNE-H. JENS, do hereby affirm that the foregoing 1

statements are based on the-facts and circumstances which-

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are-true and accurate to.the best of my knowledge and' belief.

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dua WAYNE H. JENS Vice President Nuclear Operations On this e2e d day of , 1985, before me personally appeared Wayne H. Jens, being first duly sworn'and says that he executed the foregoing as his free act.and deed.

Notary Public MAftCIA BUCK Notary Public, Washtenaw County, MI My Commission Expires Dec.28,1987 Ar:g~ i W % .7E.

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ATTACHMENT 1 - gAFETY EVALUATION

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~ SAFETY EVALUATION INTRODUCTION Retirement of the Fermi l plant was accomplished through provisions of 10CFR50.59 and through a series of Techni-

cal Specification changes. The original decommission-

ing plan submitted through ERDA document NP-20047, consisted of the following major elements

1. Shipping all fuel and blanket elements offsite.

2. Shipping all bulk radioactive and non-radioactive sodium offsite and passivating-the. residual sodium.

.3. Disposing of all other-contaminated or irradiated materials by shipping offsite or placing in restricted areas whose access is limited only to authorized personnel.

4. Securing some of the Reactor Building electrical, instrumentation, piping, ventilation, personnel'and equipment penetrations.

5. Sealing the primary system, comprised of the reactor vessel, primary sodium piping, primary shield tank, inachinery dome, primary sodium service,'and secondary sodium system out to welded pipe caps, and passivating the residual sodium-therein.

~6. Revising the site boundary to a very_ limited area to include.only those areas containing radioactivity.

7. Implementing a post-retirement surveillance plan.

All_ elements of the plan have been implemented with the shipment of primary sodium to the Argonne National Laboratory-West between October 29 and November 12, 1984.

The facility is currently in-a safe-storage condition.

Detroit Edison is proposing to continue maintaining the facility in its present condition until the_ year 2025 at which time all residual-radioactivity is currently intended to be removed and the License terminated. ,

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EVALUATION The radiological status of the facility is progressively becoming more benign due to the decay of residual radioactivity. In June 1973 the main source of

-radioactivity in the facility was estimated to be 1550 Curies, of which slightly more than 1500 Curies was due to Cobalt 60. The Cobalt 60 presently is calculated to have decayed to approximately 320 Curies, and by the year 2025, will have decayed to approximately lif Curies. Other contributors _ originally present such as Co-58, Fe-59 and Cr-51 are now essentially absent. The safe storage condition of the facility has been and will continue to be maintained on the basis of the Technical Specifications. This will assure that the barriers toresidual radioactivity will retain their physical integrity until such radioactivity is removed.

CONCLUSIONS Based on the above, the maintenance of the Fermi l facility in a safe storage condition until the year 2025 presents no increased risk to the-health and safety of the employees or the public, and is within the scope of current regulation. In addition, continued existence of the facility in the safe storage condition in accordance with the proposed amendment would not:

(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

In addition, the proposed amendment creates no irrever-sible conditions. Options for final decommissioning of the facility remain open and flexible as the residual activity decreases.

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ATTACHMENT 2 - FERMI 1 STATUS DESCRIPTION L'

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, TABLE OF CONTENTS

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1.0 INTRODUCTION

2.0 FACILITY DESCRIPTION 3.0 ADMINISTRATION a

4.0 ACCESS CONTROL 5.0 MONITORING AND ALARMS 6.0 SURVEYS, INSPECTIONS, AND TESTING 7.0 PROCEDURES 4

Table 1 Environmental Survey Regimes Figure 1 Facility Plan LBP/100/LIC-29/7.0

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1.0 INTRODUCTION

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The: retirement plan for: the Enrico Fermi 1 Power Plant .-was previously

' presented to lthe 'At'omic Energy Commission via a September 24, 1973 letter

from'the Power Reactor Development Company. The following discussion is

an J update ' ofithat information which reflects the' current status of Fermi 1.

As reflected in the September 24, 1973 submittal, the core fuel sections of all-214' Core A fuel' subassemblies ccaposed of'25.6 '/o enriched uranium

, - molybdenum alloy ~ were shipped to' the Savannah' River Plant facility for reprocessing.

The comp 1.ete inventory 'of approximately 70,000 gallons of primary sodium was stored. frozen in 1344, 50-gallon drums stored in .the reactor

' containment dome and..just. prior.to shipment, in the cask car trestleway.-

- This sodium was shipped to Argonne National Laboratory-West. between October

29.and November 12,1984. .Though virtually. all sodium has been. removed

'from the systems within Fermi 1, a ' residual heel of sodium (approximately 450 gallons estimated) is retained in vessels and piping formerly used for s odium.-

.The main source of activity in the facility, concentrated in the lower.

elevation' of the reactor building, was estimated in June 1973 to be 1550 -

curies, fof which slightly more than'1500 curies was due to cobalt 60.

present in the reactor support plates, holddown mechanism, and shield bars.

At the present time 'the Cobalt 60 is calculated to have decayed to approximately 320 curies, and in 2025, the time that " safe store" condition

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Intended to. bef terminated, it will have decayed to approximately 1.6 curies. .0ther contributors present in 1973 (Co-58, Fe-59, and Cr-51) are -

!now essentially absent. Typical radiation levels'in the high radioactivity regions within the Protected Area presently average between-1.0 and 15 mres/hr. Areas outside the . protected area are at less than 5 microren/hr above natural background. . ,

The safe storage condition of the facility is maintained aon the basis of the Technical Specifications and the Administrative and Surveillance

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Procedures which prescribe the' administration, access control, monitoring, periodic . environmental ~ and radiological surveys, long term maintenance

- provisions, and-record keeping requirements.

- 2.0 FACILITY DESCRIPTION'

.The Fermi 1 facility is located within the owner controlled area and outside' the protected area of. the nearby Fermi 2 Unit. Figure 1 presents -

- the' current facility plan. - ' As shown in the figure, the following buildings are-identified:  ;

o Reactor Building

' The Reactor (or containment) Building contains, below floor, the empty

-radioactive reactor vessel (which itself is contained in the Primary Shield y Tank), . heat exchangers, primary sodium pumps, and the primary sodium i

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4 ' y oveEflow tank' (which has been passified and is open to the atmosphere). A moisture detector'is located in the area sump that alarms -in -the manned

' control station. Operators enter this area twice a year to check

.the moisture detector operation in accordance with the Technical S pec ifications. No moisture has been detected in this' area since the retirement. of the facility.

. Above ? floor level, the Reactor Building contains the machinery done, containment crane,-and other machinery. The primary system has' been capped

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(with carbon dioxide- at 'approximately two inches water pressure. -Though virtually all sodium has been removed from~ the system an estimated 450

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gallons of residual heel of sodium remains in the vessels or pipes formerly -

used for sodium. This residual- sodium contains an estimated 1.7 mci of Cs-137 and 0.34 aci of Sr-90.

The Reactor. Building outer' air lock door is kept' locked, except when occupied, to provide additional security. The interlock on the-emergency exit has been removed and the outer door can be operated from the inside in Lcase of'an emergency. -i o Fuel and Repair Building (FARB) -

This building houses 1 the fuel storage pool and fuel ' cut up pool which were

-drained out, cleaned and painted with strippable paint. In addition, above

' floor, .there is ' the sealed containment steam cleaning chamber and below.

. floor,Lthe sealed transfer. tank room, mechanical equipment room, liquid radioactive waste tank rooms , and the " hot" drains sump. . The transfer tank room houses a drained and sealed transfer tank containing a heel of passivated residual sodium.- The radioactive liquid waste tanks were originally drained. The " hot" sump has been left active. A moisture detector--in the sump alarms at the manual control station when water gets to the applicable level.- . The sump ' pumps presently pump into the liquid waste tanks, MK 7, 8, 9, or-15. In the last 10~ years, during which Fermi 1 has' been~ in a safe. storage condition, approximately 15,000 gallons of water have been discharged to the' tanks. The' quantity of liquid in the tanks is ,

. monitored from level indicators located in the upper floor of the Fuel and ,

Repair Building. - The total capacity of the tanks is 37,500. gallons..- - Much - l of.this water came from water in-leakage-from pipe penetrations to the

- Health Physics Building. The situation causing the in leakage has been corrected.

Radiation indications within the general area of the ground level floor of the Fuel and Repair' Building are below delectable levels. Slight contam-ination has been found in the fuel and cut-up pools and the " hot" sump.

As' of May '1985 the activity at the bottom of the sump pump was 100,000

- d pa/100cm2 and at the shaft of the pump was 20,000 dpm/100cm 2 . One corner of the bottom of the sump measured 15 mres/hr.

o Sodium Storage Building

~ The primary Sodium Storage Building contains three 15,000 gallon tanks.

The sodium in these tanks was removed and placed in 55 gallon drums. These

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. drums were shipped to Argonne National Laboratory-West in Idaho. The three primary sodium storage tanks have been passivated with a carbon dioxide cover gas which is maintained on the' tanks.

- Entrance to- the sodium tank room' is- through a steel door. in the north wall of the. building which has been locked.

- The Sodium-Storage Tank room was surveyed for radiation levels on April 15,

- 1985. The radiation-levels-between' tanks range between 0.5-1.0 arem/hr.

o Waste Gas Building

This - building- contains . two deactivated waste gas tanks and is nonradio-active.

o- Waste Gas Tunnel ,

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' The tunnel runs. east to west from the Reactor Building along-side the south

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wall of the Waste Gas. Building. The tunnel steps down as it approaches;the

- Waste Gas Building and becomes too congested and small for access along its .

whole length. AccessLis via a. steel cover southeast of the Waste Gas g_ Building.

Inert Cas Buildins

, .o The south end of this building contains a 500 -cubic foot vacuum tank, a 200

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cubic foot vapor trap, and a 500 cubic foot hold-up tank. The north room contains'three inert gas. compressors. Both rooms are nonradioactive.

o' NaK Room The room houses the NaK equipment (used in conjunction with the sodium cold trap) which has been disconnected. The sodium drumming facility is 'also -

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- located in this room. Radiation surveys indicate only trace amounts of-radioactive material present in equ{pment and structures in this room.

o' Cold-Trap' Room

- This room contains sodium piping needed formerly for sodium drumming, .and

\, the piping and valves to and from the primary sodium tunnel. Some of the latter has been cut'and capped. Others have had ' the- valves closed and the

. - handwheels disconnected. Some misc _ellaneous radioactive materials are

'being stored in the' room.

i. Not shown in Figure l'is a second story above the Cold Trap Room, Nak Room, and part of the Inert -Gas . Building. This second story contains 'the hand-wheels to the sodium valves' at the ' north end of the room (some

' disconnected) and the electrical feeds for sodium heating.

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'o ' ~ Vent Buildina.

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This building has' been ' emptied of a111 equipment and the fence -has been modified toLbe continuous past the east doors of the building.

o Primary Sodium Tunnel' This tunnel is steel-lined and runs fram-the northwest corner of the Reactor Building to the Cold' Trap Room. The piping in this_ tunnel has been-

. drained and capped at the; Reactor' Building, and either capped or isolated

with closed disconnect valves in the Cold Trap Room. Access to this tunnel is via a manhole near the transfer corridor.

o' Fission Product Detector' Building This is a small building, partly below ground level, to the. east of the LL Reactor Building._ It contains some slightly radioactive piping.

o Sodium Piping Galleries'

'There~are'two bAlow ground' piping galleries that were used to house (secondary sodium piping.

'The west' gallery consists of two chambers (i.e., north.and south chambers) which hold the __ secondary sodium lines that supplied: the No.- 3 steam generator. The-sodium lines have been capped where they exit and enter the

, Reactor: Building.

The ground level entry to the north chamber was sealed off as part of the decommissioning program. Entry is now made via a short 30" diameter tunnel

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which runs between the biological shield wall space and the north chamber.

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' Access to ~ the south chamber islvia's steel door just 'above ground level at the north wall of the Steam Generator building.

The east gallery consists of three separate chambers and contains the secondary; sodium pipe . lines that supplied the Nos. 1 and 2 steam generators.

.These lines.have'been capped as in the. west gallery.'

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. Access to the' three ~ chambers ;is by means of steel doors just above ground level outside the' southeast quadrant of the Reactor Building.

Jo Biological Shield Wall Area

' _ This ~is approximately a three foot wide annulus that surrounds the building below floor level to about three feet below the concrete pedestal on which the' steel Resctor Building stands. Various service piping systems'are

. located in the annulus.- It 'is entered via a bolted-in-place cover at the west asinuth outside of the containment shell. An access ladder has been-le f t in place. In addition, at 'about 30*; north of -the entrance, at just below floor level, there is an access port to the northwest secondary sodium pipe. gallery chamber. .

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p The annulus has four floor drains that drain into a collection tank and l' '

- sump pump system located'in the basement of the Stema Generator Building.

. In addition, there is'a moisture detector that alarms at the manned control i station. -The water drained into the. tank is nonradioactive.

-o Fuel Transfer Corridor ,

This is a covered way covering the tracks of the former fuel handling cask car. The end adjacent:to the Reactor Building was. modified after 1966 to provide's covered access to the Reactor Building air lock. The area is free of contamination.-

,4 o  ; Health Physics Building This' building has been removed.. Only the foundation slab remains.- There are potentially radioactive drains'and lines-to-the hot' sump,in the FARB which have been permanently plugged and marked. Due to some problems with E  ; rain water in-leakage via these-drains and.where they penetrate the FARB, 1 'the entire area between the foundation slab and the FARB has been covered l by a concrete slab. Since this has been done, there has been no consequential inleakage. -Radiation levels above the slab are in the same

[ . range as those of natural concrete.

o Primary System Cover Gas The' primary system is defined as the reactor vessel and all connecting volumes.' These include the three primary loops, the machinery done, and-

-the primary sodium service, and secondary sodium systems 'out to the welded -

l fittings.' The primary system is connected to reserve and backup supplies

!! of carbon dioxide to passivate the residual sodium and is kept at approximately two inches water pressure with 'a relief valve set for approximately 5 psig. The relief valve is checked annually for proper h ' operation.

, The cover gas is' instrumented to alarm in the manned control station-at low.

p~ (1/2-in ' water gauge) and high (2 psig increasing pressure) pressure.

Primary cover gas alarm tests are performed every six months.

o. Liquid Waste Discharge System All potentially contaminated drains and sumps collect in the hot sump in the Fuel and Repair Building. The liquid waste collected in the hot sump

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is discharged to the liquid waste tanks, (ak 7, 8, 9, 15). Liquid quantities in these tanks are monitored and recorded. If there is a need to discharge the liquid from the tanks, the water will be processed via a portable liquid radwaste processing system such as is typically used at many power reactor facilities until it is acceptable for discharge in accordance with the Technical Specifications.

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- 0 Liquid waste collected in non-contaminated . sump systems are'not part of the Liquid Waste Discharge System. .Non-contaminated sumps collect underground

water or rain water intruding in non-contaminated areas. These sumpt 4

Edischarge ~ to the plant drain system which drains to Lake Erie.

o Other "The remaining Fermi 1 buildings (e.g., the -steam generator, control, and office buildings) were not exposed to the radioactivity resulting from the.

operation of Fermi 1. Due to this , they have been used ' for various ,

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activities affiliated with~the operation of the oil peaker unit (now

^ decommissioned) and Fermi 2.

' 3.0 ADMINISTRATION.

The Detroit Edison Company has the responsibility for maintaining a continuing administrative and surveillance program in compliance with current Nuclear Regulatory Commission requirements to ensure that the health and safety of>the public and. employees are not threatened or injured.

The Vice President, Nuclear Operations, who reports to the President has overall responsibility for the Enrico Fermi Unit i reactor facility.

Reporting 'to the Vice President, Nuclear Operations, is the Manager and the

- Assistant Manager, Nuclear Operations.

, Responsibility for the decommissioned Enrico Fermi Unit I reactor facility is delegated through the line' organization of the Vice President, Nuclear

. Operations,.'down through the Manager, Nuclear Operations', to a qualified custodian selected from the -staff of the adjacent Fermi 2 Atomic Power Plant. The Custodian is assisted in his duties by Custodial Delegates and Custodial Agents.

~ In addition, the facility administrative. and surveillance program is-audited by means of a Review committee which will also review and approve all matters of safety associated with.any maintenance activities in'the facility. .

! Written procedures delineate the qualification, selection and responsibilities of the Custodian, Custodial Delegates and Ag'ents, and members of the Review-Committee.

4.0 ACCESS CONTROL t

The area encompassed by physical barriers and to which access is controlled is th'e Protected Area. The Protected Area, is enclosed by either a chain link fence or building walls which provide equivalent degree of resistance-

-to penetration. The fence. is topped by three or more strands of barbed

-wire ~or brackets angled outward with an overall height of no less than seven feet. Normal entry to 'the Protected Area is through a normally locked gate in the fence adjacent to the Sodium Building. Other doors in walls' which~ act a part of the Protected Area boundary are locked or

-permanently sealed.

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. Access to the ' Protected ' Area is controlled, limited .and recorded. _The i access key;is in_the manned control statien. A second key is' held in safe l keeping- by.'the Custodian for use only in extenuating circumstances.

Writteniprocedures delineate the requirements associated with entry into the- Protected Area and specific areas within the Protected Area to prevent

' unauthorized entries and to - protect the safety -and -health of authorized personnel.-

5'.0_. MONITORING AND ALARMS' Monitoring- detectors for water. intrusion are located in three areas: (1) the Fuel and Repair, Building basement hot sump, (2) the' Lower reactor Building overflow tank pit, and (3)- the Biological _ Shield Wall Area.

tAccumulation of water'in these areas activates an. alarm in the mannM control station.

The primary system cover gas pressure i's also monitored with high and low alarms. The monitors and the alarm circuitry are periodically checked and

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. -calibrated in accordance with the Technical Specifications and written procedures._ -

6.0L SURVEYS, INSPECTIONS, AND' TESTING Two types 'of surveys _ are identified; environmental and radiological, in

' addition ' to periodic facility inspections and instrumentation testing.

For the environmental surveys, a number of stations have been established where it is estimated that maximum concentrations of: radioactive material di,scharged from the facility' may ' occur. Two different regimes of sampling and' analysis are utilized. A summary of these regimes is given in Table 1.

1. Regime I is followed if activity is released.

2. Regime II is followed if no activity has been released during the-previous 90 days.

Periodic Radiation _ surveys are performed to check for the presence of gamma radiation'and transferrable contamination at the frequency specified in the .i

. Technical Specifications. _ Gamma radiation measurements using portable survey instruments and contamination checks using smears are made of the following areas:

Reactor Building - Operating floor, doors and seals around machinery dome, breather pipe', sump pump serving Reactor Building annulus.

Fuel and Repair B'uilding - Pool area, operating floor access points to

. contamination areas, Steam cleaning Room access plug.

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Environmental and radiological surveys are performed by or under supervision of qualified personnel having parallel duties and responsibilities at Fermi 2.

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A monthly visual . inspection of the Protected Area is performed by Custodial

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- ' Agents. The inspection consists of a visual inspection ~ of the fence, gates and all; exterior doors ~ at . the . Protected Area, a' check and recording of the level of liquid in the liquid water tanks, a check on the ' condition of the

.strippable paint .on ,the decay and cut-up pools in the Fuel and Repair Building, and ' verifications of f the operation of- the susp pumps which serve the Protected Area. .All abnormal conditions observed are reported to the.

Fermi 2 Nuclear . Shift Supervisor so that. corrective' measures may be taken.

The Custodian is also notified of all abnormal conditions. immediately, and -

of theJcorrective action taken.

Testing'and calibration of the~ water intrusion monitors, and testing the primary cover' gas pressure alarus, is performed every six months. Testing of the carbon dioxide pressure relief valve is performed snnually. all testing :is ' performed in accordance with written and approved procedures.

7.0 5 PROCEDURES Procedures ensure that the requirements of the Technical Specifications are carried out in a proper and timely'manne~r. They also serve as training and reference units for future Custodians, Custodial Delegates and Custodial

' Agents. Administrative -procedures include Custodial qualifications, responsibilities and authority, Procedure Manual control, Custodial .

Delegate and Custodial Agent s' election and. function, reporting procedures, ,

. Review Committee-functions and financial accounting procedures. In 7 addition, .- th'ere are - appropriate procedures for' details of inspections,-

surveillances' and operation.

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TABLE 1 .!

Environmental Survey Regimes Number of Stations Regime

Sample Media Indicator Background I II Water-4: South Lagoon' 1 0. G26b G26b River Water-. 1. 1 G1b C26b Lake Water 1 0 Gib G26b Raw City Water

• 0 -3 G4b G26b Sediment South Lagoon Sediment 1 0 G26g G26g River Sediment 1 1 G26g G26g Symbols:

G -' Grab Sample Frequency of Sampling:

1 - one week-interval 4_ . ~ four week interval 26 Lt wenty-six week interval Type of Analysis:

b - be t a -

g gamma

-Example : Gib - Sample is collected at one week intervals and analyzed for beta radioactivity

• List of Cities.

Detroit.

Monroe

, Fermi Plant

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FIGURE 1 I FACILITY PLAN l u