Text

Proposed Defueled Tech Specs & Bases for Big Rock Plant
	ML20154M543
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	10/14/1998
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML20154M541	List: ML20154M538; ML20154M543;
References
	NUDOCS 9810200326
	Download: ML20154M543 (52)
	v • d • e

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BIG ROCK < POINT RESTORATION PROJECT DEFUELED TECHNICAL SPECIFICATIONS i

M "2888R H a8sise W

PDR u

TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS FOR BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE#

LICENSE..........................................................................1 LICENSE.........................................................................2 1.0 D E FINIT IONS.........................................................

1 - 1 1.1 A CTI O N...............................................................

1 - 1 1.2 CERTIFIED FUEL H ANDLER............................................. 1-1 1.3 CH ANN EL CA LIB RATION............................................... 1 - 1 1.4 C H ANN E L C H E C K...................................................... 1 - 1 1.5 CH ANNEL FUNCTION AL TEST........................................... 1 - 1 1.6 CONTAINM ENT C LOSURE............................................. 1 - 1 1.7 D I RE CT PATH S......................................................... 1 -2 1.8 F U E L H AND L ING......................................................

1 -2 1.9 I MM E D I ATE LY......................................................... 1 -2 1.10 M ONITORING STATION................................................. 1 -2 1.11 OFF-SITE DOSE CALCULATION MANUAL (ODCM)......................... 1-2 1.12 OP ERAB L E-OPE RAB ILITY.............................................. 1 -3 1.13 PROCESS CONTROL PROGRAM (PCP)..................................... 1-3 1.14 REPO RTAB LE EVENT................................................... 1 -3 1.15 SHIFT.................................................................1-3

'l.16 S ITE B O UND AR.Y....................................................... 1 -3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEMS SETTINGS.............. 2-1 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE Q. U I REM ENTS......................................................

3/4-1 3/4.0 APPLICAB ILITY......................................................

3/4-1 3/4.1 FU E L STO RA G E....................................................

3 /4-2 3/4.1.1 Spent Fuel Pool Parameters.........................................

3/4-3 3/4.1.2 Spent Fuel Pool Support System Requirements.........................

3/4-4 3/41.3 Fuel Storage General Requirements...................................

3/4-5 3/4.2 F UE L H AN D LIN G................................................

3 /4-6 3/4.2.1 Fuel Handling Support System Requirements.............................

3/4-6 3/4.2.2 Fuel Handling General Requirements................................. 3/4-7 & 8 3/4.3 CONTROL OF HEAVY LOADS...................................... 3/4-9 & 10 3/4.4 SEALED SOURCE CONTAMINATION.....

3/4-11 AS PROPOSED l

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1 b

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TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS i

BIG ROCK POINT PLANT E

l-l l

l SECTION DESCRIPTION PAGE#

5.0 D E S I GN F E ATURES....................................................... 5 - 1 l

5.1 SITE......................................................................5-1 5.1.1 Location and Boundaries................................................ 5-1 5.2 STORAGE AND INSPECTION OF SPENT FUEL.....................

.........5-1 5.2.1 Cri ti c al ity............................................................

5-1 5.2.2 Water Level......................................................... 5 - 1

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5.2.3 Co o l i n g.............................................................. 5 - 1 L

F igu re (Fi gure 5.1 - 1 ).............................................................. 5 -2 5.2.4 C ap a c i ty............................................................ 5 -3 5.3 R E A CT O R.............................................................. 5 -3 5.3.1 S t a t u s............................................................... 5 -3 6.0 ADMINISTRATIVE CONTROLS.............................................. 6 1 6.1 RESPONSIBILITY AND AUTHORITY......................................... 6-1 6.1.1 Senior Nuclear Officer.................................................. 6-1 6.1.2 S ite General M anager................................................... 6-1 6.1.3 S hi f1 S upe rvi sor.......................................................

6-1 6.2 O R G ANIZ ATI ON...........................................................

6-1 6.2.1 Reporting Relationships.................................................

6-1 6.2.2 Facility Organization................................................... 6-2 Table 6.2-1 Minimum Shift Crew Composition during Permanently Defueled Condition... 6-3 6.3 STAFF QUALIFIC ATIONS................................................. 6-4 6.4 T RA INI N G................................................................ 6-4 6.5 RE VIEW AND A UDIT...................................................... 6-4 6.5.1 CPC-2 A Quality Program Description.................................... 6-4 6.6 PROCEDURES AND PROGRAMS............................................

6-4 6.6.1 Proc ed ures........................................................... 6-4 6.6.1.1 S c o p e....................................................... 6 -4 l

6.6.1.2 Review and Approval........................................... 6-5 6.6.1.3 Tempo rary Changes..................................

..... 6-5 6.6.2 P ro gra m s......................................................

6-5 6.6.2.1 Radiation Protection Program...................................... 6-5 6.6.2.2 High Radiation Area............................................ 6-5 6.6.2.3 Process Control Program (PCP)..................................... 6-6 6.6.2.4 Offsite Dose Calculation Manual (ODCM)...........

............. 6-7 6.6.2.5 Radioactive Effluent Controls Program.................

......... 6-7 l

6.6.2.6 Radiological Environmental Monitoring Program................. 6-8 i

6.6.2.7 Fire Protection Program........................................ 6-9 6.6.2.8 Cold Weather Protection Program................................ 6-9 AS PROPOSED l

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TABLE OF CONTENTS 3

DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE#

6.7 REPORTING REQUIREM ENTS............................................... 6-9 6.7.1 Annual Occupational Radiation Exposure Report............................. 6-9 6.7.2 Annual Radiological Environmental Operating Report........................ 6-10 6.73 Annual Radioactive Effluent Release Report............................... 6-10 6.7.4 Special Reports......................................................

6-10 6.8 RE C O RD S................................................................

6-1 0 6.9 RE PORTAB LE EVENTS.................................................... 6-1 1 AS PROPOSED

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 CONSUMERS ENERGY COMPANY DOCKET NO 50-155 BIG ROCK POINT PLANT FACILITY OPERATING LICENSE License No DPR-6 A.

This license applies to the decommissioning of Big Rock Point Plant, (the facility),

owned by Consumers Energy Company (the licensee). The facility is located in Charlevoix County, Michigan, and is described in the licensee's application dated January 14,1960, and the Final Hazards Summary Report; as supplemented, updated, and amended by subsequent filings by the licensee, i

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Energy Company:

(1)

Pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities" to possess the facility at the designated location in Charlevoix County, Michigan, in accordance with the procedures and limitations set forth in this license; (2)

Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material," to possess at any one time up to (a) 2500 kilograms of contained uranium 235 in fuel rods, (b) 10.32 grams of uranium 235 as contained in fissior.

counters, (c) 150 kilograms of plutonium contained in PuO -UO I"'I 2

2 rods, and (d) 5 curies of plutonium encapsulated as a plutomum-beryllium neutron source; (3)

Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to Domestic Licensing of By-product Material," to receive, possess and use at any one time up to 7000 curies of antimony-beryllium in the form of neutron sources,3.7 curies of cobalt-60 as sealed sources,45 curies of cesium-137 as sealed sources,10 microcuries of miscellaneous alpha emitting material as scaled sources, and up to 500 millicuries per nuclide of any byproduct material between atomic numbers 1 and 83, inclusive, without restriction as to chemical and physical form; (4)

Pursuant to the Act and 10 CFR Part 40, " Licensing of Source Material,"

to possess at any one time up to 500 kilograms of depleted uranium dioxide contained in the facility's fuel assemblies; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may have been produced by operation of the facility.

AS PROPOSED

1 2

. C.

' This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

.(1)

' Reactor Ooeration The reactor is not licensed for power operation. Fuel shall not be placed in the reactor vessel.

(2)

Technical Specifications i

The Technical Specifications contained in Appendix A, as revised through Amendment No.

, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

(3)

The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans approved by the Commission and all amendments and

)

revisions to such plans made pursuant to the authority of 10 CFR 50.90

. and 10 CFR 50.54(p). The plans, which contain Safeguards Information l

protected under 10 CFR 73.21, are entitled: " Big Rock Point Plant' i

Security Plan," with revisions submitted through September 29,1988; " Big Rock Point Plant Suitability Training and Qualification Plan," with revisions submitted _through November 30,1988; and " Big Rock Point Plant Safeguards Contingency Plan," with revisions submitted through-September 30,1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance' with the schedule set forth therein.

^D.

This license amendment is effective as of the date of its issuance, or at midnight on

, whichever is later.

~

Attachment:

Appendix A Technical Specifications Date ofIssuance:

AS PROPOSED

l BIG ROCK POINT PERMANENTLY DEFUEIRD TECHNICAL SPECIFICATIONS -

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1.0 DEFINITIONS 1.1 ACTION l

ACTION shall be that part of a specification which prescribes remedial measures i

required under designated conditions.

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1.2 CERTIFIED FUEL HANDI.FR l-CERTIFIED FUEL HANDLER, is an individual who is qualified in accordance with i

BRP Program D25.1 " Certified Fuel Handler Initial Certification Program".

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1.3 CHANNEL CAI IBRATION 1

A CHANNEL CALIBRATION is the adjustment as necessary, of the channel output such that the channel responds with the necessary range and accuracy to known values i

of the parameter which the channel monitors. The CHANNEL CALIBRATION shall f

encompasses the entire channel including the sensor and alarm and/or trip functions, and includes the CHANNEL FUNCTIONAL TEST. The CHANNEL l

CALIBRATION may be performed by any series of sequential, overlapping, or total i-channel steps such tha: the entire channel is calibrated.

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1.4 CHANNEL CHECK l

A CHANNEL CHECK is the qualitative assessment of channel behavior during operation by observation. This assessment shall include, where possible comparison of the channel indication and/or status with other indications and/or status derived l

from independent instrumentation channels measuring the same parameter.

1.5-CHANNEL FUNCTIONAL TEST l

A CHANNEL FUNCTIONAL TEST is the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY, including alarm and trip functions.

i 1.6 CONTAINMENT CLOSURE I

L CONTAINMENT CLOSURE is that condition of containment in which there are no direct paths from containment atmosphere to the outside atmosphere, except for the containment ventilation inlet and exhaust valves, which may be open if at least one exhaust fan is in operation. Leak tightness is not required for CONTAINMENT CLOSURE to exist.

1 l

11 AS PROPOSED l'

BIG ROCK POINT PERMANENTL'Y DEFUEIED TECHNICAL SPECIFICATIONS i

1.0 DEFINITIONS 1.7 DIRECT PATH

. A DIRECT PATH is a visually observable opening which permits the free exchange of air between containment and the environs. Equipment configurationc or an engineered feature such as a closed valve, check valve, ivater seal, closed door, membrane layer, or securely fastened plate may be used to preclude direct paths.

Redundancy of engineered features to eliminate direct paths is not required.

1.8 FUEL HANDLING

- FUEL HANDLING means the activities associated with moving spent nuclear fuel, l

including moving the 24 ton fuel transfer cask when it contains spent fuel. When spent naclear fuel is contained in a closed and sealed permanent storage cask or associated transfer device, the activities associated with moving the cask or device when it is outside the Spent Fuel Pool Area are not to be considered FUEL l

HANDLING.

1.9 IMMEDIATELY When "IMMEDIATELY" is used as a completion time for a required ACTION, the ACTION should be pursued without delay and in a controlled manner.

1.10 MONITORING STATION The MONITORING STATION is the facility which has monitoring, alarming, data.

archiving and limited control capabilities for selected system parameters during the deconunissioning process. The Control Room shall remain the MONITORING STATION until such time as a new facility is activated to serve this function.

1.11 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

The OFF-FITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring programs required by Sections 6.6.2.5 and 6.6.2.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.7.2 and 6.7.3.

1-2 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS (continued) 1.12 OPERABLE - OPERABII ITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that is are required for the system, subsystem, train, component or device to perform its safety function (s) are also capable of performing their related support function (s).

1.13 PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM contains the methods and determinations which ensure that the processing and packaging of wet solid radioactive wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61 and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

1.14 REPORTABLE EVENT A REPORTABLE EVENT is any of those conditions specified as reportable in Specification 6.9.

1.15 SHIFT A SHIFT shall be the duration of the normal work period, which will be either 8 or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in length as determined by the Site General Manager. For purposes of determining the maximum allowable time between surveillances, when the specified surveillance interval is "once per SHIFT," the maximum allowable extension not to exceed 25 percent of the specified surveillance interval described in surveillance requirement 4.0.2 shall be based upon the SHIFT duration approved by the Site General Manager at that time.

1.16 SITE BOUNDARY The SITE BOUNDARY is that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

1-3

IllG ROCK POINT PERMANENTLY DEFUEIED TECHNICAL SPECIFICATIONS l

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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS E

There are no safety limits or limiting safety system settings applicable to the permanently defueled condition.

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2-1 AS PROPOSED

_ -.. =

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 Unless otherwise specified, entry into an applicability condition shall not be made unless the conditions of the associated Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements.

SU3VEILLANCE REQUIREMENTS 4.0.1 Unless specified otherwise, Surveillance Requirements shall be applicable during the specified applicable conditions for the associated Limiting Conditions for Operation.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Unless specified otherwise, performance of a Surveillance Requirement within the specified time interval including the maximum allowable extension shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements.

4.0.4 Unless specified otherwise, entry into a specified applicable condition shall not be made unless the Surveillance Requirements associated with the Limiting Condition for Operation have been performed within the stated surveillance interval including the maximum allowable extension.

3/4-1 AS PROPOSED

l BIG ROCK POINT PERMANENTLY DEFUEIID TECHNICAL SPECIFICATIONS l

3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS LIMITING CONDITIONS FOR OPERATION 3.1.1 The following parameters shall be monitored and maintained within the limits indicated:

a.

The water level in the Spent Fuel Pool shall be maintained at or above 630'.

b.

Spent Fuel Pool water temperature shall be maintained greater than 40 F and less than 140 F.

c.

Water chemistry in the Spent Fuel Pool shall be maintained within the following:

pH 5.0 to 9.0 Conductivity less than or equal to 10.0 micromhos per em at 77 degrees F d.

Radiation levels in the area of the Spent Fuel Pool shall be normally monitored by two gamma radiation monitors, each with a locally and remotely audible alarm set at not less than 5 millirems per hour and not more than 20 millirems per hour, except during the movement of spent fuel or radioactive components in or adjacent to' the Spent Fuel Pool, when alarm settings may be raised above 20 mrem /hr provided the overall detection criterion in 10CFR70.24(a)(2) is satisfied. At least one monitor is required to be OPERABLE. The monitors shall have remote indication and the capability of recording data.-

APPLICABILITY:

When spent fuel is in the Spent Fuel Pool.

ACTION:

i.

With the requirements of 3.1.1.a not met, IMMEDIATELY suspend activities having potential to drain the Spent Fuel Pool. Place fuel assemblies and the crane load in a safe condition, suspend further

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movement of fuel assemblies ed crane operations with loads in or over the Spent Fuel Pool, and initiate action to restore Spent Fuel Pool water level. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish CONTAINMENT CLOSURE.

ii.

With the requirements of 3.1.1.b not met, IMMEDIATELY place j

fuel assemblies and the crane load in a safe condition, suspend j

further movement of fuel assemblies and crane operations with loads 3/4-2 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE i

3/4.1.1 SPENT FliEL POOL PARAMETERS LIMITING CONDITIONS FOR OPERATION in or over the Spent Fuel Pool, and initiate ACTION to restore acceptable temperature. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish CONTAINMENT CLOSURE.

iii.

If the water quality specifications of 3.1.1.c are exceeded, initiate corrective measures to meet chemistry requirements within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and sample pool water at least once a day until readings meet the requirements of 3.1.1.c. If water quality cannot be recovered after one week, prepare a special report that identifies the causes and proposed corrective action (s) to ensure future water quality is in compliance and submit to the NRC by 31 days following entry into the LCO.

iv.

With the requirements of 3.1.1.d not met, IMMEDIATELY provide j

an alternate method of monitoring Spent Fuel Pool radiation levels.

If the alternate instrumentation does not have an audible alarm, locally and in the MONITORING STATION, radiation levels shall j

be continuously monitored by personnel in communication with the 1

MONITORING STATION, when personnel are in the vicinity of the Spent Fuel Pool.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.1.a Twice per SHIFT, the water level in the Spent Fuel Pool shall be determined to be at or above the elevation of 630'.

4.1.1.b Twice per SHIFT, Spent Fuel Pool water temperature shall be determined to meet the requirements of Specification 3.1.1.b.

4.1.1.c Once per 31 days, Spent Fuel Pool water chemistry shall be determined to meet the requirements of Specification 3.1.1.c i

4.1.1.d The Spent Fuel Pool radiation monitor required by this specification shall be demonstrated operable:

i.

Daily by performing a CHANNEL CHECK.

ii.

Once per 31 days by performing a CHANNEL CALIBRATION.

l 3/4-3 AS PROPOSED l

l BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS L_IMITING CONDITIONS FOR OPERATION l

3.1.2 The capability to supply makeup to the Spent Fuel Pool shall be maintained as follows:

A diesel generator capable of providing power within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to operate a.

an on site electric motor-driven pump shall be available DR.

One off-site source of ac power capable of providing power to operate an on site electric motor-driven pump shall be available, DE, An on site pump not requiring electrical power shall be capable of providing makeup water to the Spent Fuel Pool within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

The pump designated to satisfy the requirements of Specification 3.1.2.a shall be capable of supplying at least 28 gpm of water within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a temperature equal to or less than 100 F to the Spent Fuel Pool. The capability to manually initiate at least 28 gpm flow to the Spent Fuel Pool shall be maintained.

APPLICABILITY:

When spent fuel is in the Spent Fuel Pool.

ACTION:

With the requirements of specifications 3.1.2.a or 3.1.2.b not met, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish an alternate source of water capable of delivering at least 28 gpm of water at a temperature equal to or less than 100 F to the Spent Fuel Pool.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.2.a i.

Daily, verify the presence of potential on the offsite power line, ii.

Once per 31 days, manually start the diesel generator and run loaded for 30 minutes using an electric motor-driven pump as a load.

4.1.2.b i.

Once per 12 months, verify that the pumps satisfying the requirements of this specification are capable of supplying water within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and will deliver at least 28 gpm of water.

l ii.

Once per 12 months, Spent Fuel Pool makeup shall be determined to be j

OPERABLE by verifying its flow capacity to be at least 28 gpm.

3/4-4 AS PROPOSED

. -. _ - =. -

BIG ROCK POINT PERMANENTLY DEFUEI FD TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE l

L 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS l

LIMITING CONDITIONS FOR OPERATION i

3.1.3 The following limitations shall apply to the storage of spent fuel in the Spent Fuel l

Pool, a.

Spent fuel assemblies shall be stored in fuel storage racks located in the Spent Fuel Pool.

b.

The storage of materials in the area directly between rack B and the east wall of the Spent Fuel Pool is prohibited.

c.

Only spent fuel with a decay time of greater than one year will be stored in the outer three rows of the fuel rack adjacent to the south wall of the fuel pool.

APPLICABILITY:

When spent fuel is in the Spent Fuel Pool.

ACTION:

With the requirements of specifications 3.1.3.a. 3.1.3.b, or 3.1.3.c not met, suspend Spent Fuel Pool work activities other than required surveillance activities and perform a prompt investigation to determine the cause and initiate appropriate corrective actions.

SURVEILLANCE REQUIREMENTS 4.1.3 a.

At least semi-annually and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completion of any activity involving movement of spent fuel in the Spent Fuel Pool, verify that the requiremeras of Specification 3.1.3.a have been met.

b.

At least semi-annually and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completion of any activity involving movement of components in the Spent Fuel Pool, verify that the requirements of Specification 3.1.3.b have been met, c.

At least quarterly and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completion of any FUEL HANDLING activity which involves movement of fuel into the fuel rack adjacent to the south wall of the Spent Fuel Pool, verify that the

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storage configuration satisfies the requirements of Specification 3.1.3.c. Performance of this surveillance is not required after August 29,1998.

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3/4-5 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS LIMITING CONDITIONS FOR O.PERATION 3.2.1 The following conditions apply when handling fuel inside containment.

a.

For containment penetrations or openings, CONTAINMENT CLOSURE shall exist and containment ventilation valves shall be closed or capable of being closed.

b.

Radiation levels shall be maintained below the alarm setting requirements of specification 3.1.1.d.

APPLICABILITY:

When handling fuel inside containment.

ACTION:

i.

With the requirements of specification 3.2.1.a not met, place fuel assemblies in a safe condition, and suspend FUEL HANDLING activities insid:: containment.

ii.

With the requirements of specification 3.2.1.b not met, initiate closure of containment ventilation inlet and exhaust valves and initiate corrective actions to reduce the radiation levels to acceptable values.

SURVEILLANCE REQUIREMENTS

.4.2.1 a.

Prior to commencement of FUEL HANDLING activities, perform verification of CONTAINMENT CLOSURE for all containment penetrations or openings and verify OPERABILITY of containment ventilation valves (CV-4094, CV-4095, CV-4096, CV-4097),

b.

Verify that the radiation levels on the Spent Fuel Pool area radiation monitor are less than the alarm setting requirements of specification 3.1.1.d at least twice per SHIFT.

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3/4-6 AS PROPOSED 1

l' BIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l ~

3/4.2 FUEL HANDLING 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS l

LIMITING CONDITIONS FOR OPERATION 3.2.2 FUEL HANDLING operations shall conform to the following requirements:

1 a.

Movement of spent fuel into and out of the storage racks or inspection j

stations shall be restricted to one assembly at a time.

b.

Radiation levels at the south wall of the Spent Fuel Pool, elevation 600'6",

shall be maintained at less than 50 mrem /hr above the background level l

during FUEL HANDLING operations, c.

FUEL HANDLING shall be accomplished by manual guidance and visual i

observation of all FUEL HANDLING operations.

d.

Water shall be used as the basic shielding except when transferring spent fuel from the Spent Fuel Pool using the 24 ton fuel transfer cask.

APPLICABILITY:

When handling fuel in the Spent Fuel Pool.

ACTION:

i.

With the requirements of Specification 3.2.2.a not met, suspend FUEL HANDLING operations and place irradiated fuel assemblies

in a safe condition. Conduct a prompt investigation to determine the cause and initiate appropriate corrective actions.

ii.

With the requirements of Specification 3.2.2.b not met, IMMEDIATELY suspend FUEL HANDLING operations, initiate action to restore radiation levels to less than 50 mrem /hr above background levels and conduct a prompt investigation to determine the cause of increased radiation levels. FUEL HANDLING may resume if it is determined that increased radiation levels have not been caused by the handling of fuel in the Spent Fuel Pool and radiation levels are verified to be within the required range.

iii.

With the requirements of Specification 3.2.2.c not met, suspend FUEL HANDLING operations. FUEL HANDLING may resume once the requirements of 3.2.2.c have been re-established.

I iv.

With the requirements of Specification 3.2.2.d not met, suspend FUEL HANDLING operations. FUEL HANDLING may resume

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once the requirements of 3.2.2.d have been re-established.

I 3/4-7 AS PROPOSED

l BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

3/4.2 FUEL HANDLING l

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3/4.2.2 FUEL HANDLING GEN'ii! AL REQUIREMENTS l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.2.2 a.

None, b.

Prior to commencing, once per SHIFT during and IMMEDIATELY upon completion of FUEL HANDLING operations, monitor the radiation levels at the south wall of the Spent Fuel Pool, elevation 600'6", to verify that the requirements of Specification 3.2.2.b are met.

c.

None.

d.

None.

l l

3/4-8 AS PROPOSED 1

l BIG ROCK POINT PERMANENTLY DEFUEI FD TECHNICAL SPECIFICATIONS r

3/4.3 CONTROL OF HEAVY LOADS LIMITING CONDITIONS FOR OPERATION 3.3.1 IIandling of heavy loads over or in the Spent Fuel Pool shall conform to the following requirements:

Use of the reactor building gantry crane over the Spent Fuel Pool for loads a.

exceeding 24 tons is prohibited, i

b.

With the exception of the properly rigged 24 ton fuel transfer cask, or other cask specifically approved by NRC for use in or over the Spent Fuel Pool:

i.

No cask shall be moved over spent fuel stored in the Spent Fuel Pool.

li.

Cask handling operations shall be limited to the southwest erner of the Spent Fuel Pool.

iii.

No fuel shall be stored in the fuel storage racks adjacent to the cask handling area in the southwest corner of the Spent Fuel Pool during cask handling operations.

c.

The trip mechanism of the 24 ton fuel transfer cask safety catch device shall be operable prior to handling of the cask over or in the Spent Fuel

Pool, d.

For Containment penetrations or openings, CONTAINMENT CLOSURE' t

shall exist.

' APPLICABILITY:

When spent fuel is in the Spent Fuel Pool.

ACTION:

With the requirements of specifications 3.3.1.a,3.3.1.b,3.3.1.c, or 3.3.1.d not met, IMMEDIATELY place the crane load in a safe condition, and suspend further load handling activities with the reactor building gantry crane Load handling shall not resume until permission has been obtained from the Site General Manager.

SURVEILLANCE REQUIREMENTS I

4.3.1 a.

Prior to moving a load over the SFP, verify that the load does not exceed 24 tons.

I b.

Prior to moving a cask over the SFP, verify that the cask is the properly L

rigged 24 ton fuel transfer cask, or another cask specifically approved by 3/4-9 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS SURVEILLANCE REQUIREMENTS NRC for use in or over the Spent Fuel Pool, Prior to handling of the 24 ton fuel transfer cask over or in the Spent Fuel c.

Pool, the trip mechanism of the cask safety catch device shall be functionally tested.

d.

Prior to moving a heavy load over or in the Spent Fuel Pool, verify that CONTAINMENT CLOSURE exists.

I i.

l l

3/4-10 AS PROPOSED l

=

i l

BIG ROCK POINT PERMANENTLY DEFUELED TECIINICAL SPECIFICATIONS l

3/4.4 SEALED SOURCE CONTAMINATION LIMITING CONDITIONS FOR OPERATION 3.4.1 Each sealed source containing more than 100 microcuries of beta and/or gamma l

emitting material, or more than 5 microcuries of alpha emitting material shall not have removable contamination which equals or exceeds 0.005 microcuries.

APPLICABILITY:

At all times.

I l

ACTION:

1.

Each sealed source with removable contamination in excess of the l

above limits shall be IMMEDIATELY withdrawn from use and either decontaminated and repaired, or disposed of in accordance with NRC regulations.

a.

A special report shall be submitted to the NRC as indicated by Specification 6.7.4 b.

l SURVEILLANCE REQUIREMENTS 4.4.1 Except for: 1) sealed sources which are stored and not in use, and 2) start up sources l

and fission detectors previously subjected to core neutron flux, sealed sources l

containing radioactive materials in any form other than gas and with a half-life greater than 30 days (excluding ill') shall be tested for contamination and/or leakage at least l

once per six months by the licensee or other person specifically authorized by the NRC or an Agreement State to perform such services. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample. The test sample l

shall be taken from the sealed source or from the surfaces of the device in which the sealed source is permanently mounted or stored, on which one might expect contamination to accumulate. Records ofleak test results shall be kept in units of l

microcuries and maintained for inspection by the NRC.

l a.

Sealed sources requiring testing by this section, but exempted on the basis of not being in use, shall have been tested within 6 months prior to being transferred or put into use.

l 4

l l

l 3/4-11 AS PROPOSED l

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES 5.1.

SIIE 5.1.1 LOCATION AND BOUNDARIES The plant site, consisting of approximately 600 acres, is located in Charlevoix County, Michigan, about 4 miles northeast of Charlevoix, Michigan, and about 11 miles west of Petoskey, Michigan. The nearest landside property line is about 2680 feet and the nearest shoreline property line is about 200 feet from the containment sphere (Reference Figure 5.1-1).

5.2 STORAGE AND INSPECTION OF SPENT FUEL 5.2.1 CRITICALITY Spent fuel is stored in spent fuel storage racks which are designed and shall be maintained with sufficient center-to-center distance between stored fuel assemblies to ensure a k,y less than or equal to 0.95 when the racks are flooded with unborated water.

The fuel loading per axial centimeter of any assembly placed in the Spent Fuel Pool 235 shall be less than or equal to a maximum of 28.3 grams of U or equivalent.

Fuel inspection stations, if installed, shall be designed and maintained with sufficient center-to< enter distance between fuel assemblies placed in the inspection stations to ensure a k,y less than or equal to 0.95 when flooded with unborated water.

5.2.2 WATER LEVEL The Spent Fuel Pool is designed to maintain a normal water level between 630' and 632' 6".

5.2.3 COOLING The configuration of storage racks placed in the Spent Fuel Pool allows for adequate circulation of water to prevent localized pool boiling, i

i 5-1 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECIINICAL SPECIFICATIONS 5.0 DESIGN FEATURES (Figure 5.1-1) l-2 c.

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5-2 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

5.0 DESIGN FEATURES i

j 5.2.4 CAPACITY Subject to the limits listed below, the fuel pool is designed for and shall be maintained with a storage capacity of no more than 441 fuel assemblies. In i

l addition, fuel pins which have been removed from fuel assemblies shall be stored in the Spent Fuel Pool and shall be in a geometry which ensures suberiticality.

The following limits apply to the amount of special nuclear material which may be stored in the Spent Fuel Pool:

2500 kilograms of contained uranium 235.

10.32 grams of uranium 235 as contained in fission counters.

150 kilograms of plutonium contained in PuO -UO fuel rods.

i 2

2

5 curies of plutonium encapsulated as a plutonium-beryllium source.

5.3 REACTOR 5.3.1 STATUS The reactor is not licensed for power operation. Fuel shall not be placed in the reactor vessel.

l I

L 5-3 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY AND AUTHORITY 6.1.1 SENIOR NUCLEAR OFFICER The Senior Nuclear Officer shall be the Senior Vice President-Nuclear, Fossil, and Hydro Operations and shall be responsible for the overall operation, maintenance and decommissioning of the Big Rock Point nuclear power plant.

6.1.2 SITE GENERAL MANAGER The Site General Manager shall be responsible for overall facility operation, maintenance and decommisssioning and for periods of absence shall delegate m writing the succession to this responsibility. Unless otherwise specified, the Site General Manager's delegate has authority to perform all actions and grant approvals assigned by these specifications to the Site General Manager. The Site General Manager may delegate specific tasks to other individuals who may perform those tasks whether the Site General Manager is absent or present at the site.

6.1.3 SIIIFT SUPERVISOR The Shift Supervisor shall be responsible for the shift command function. This position will be filled by a Certified Fuel Handler.

6.2 ORGANIZATION 6.2.1 REPORTING RELATIONSHIPS On-site organization and corporate reporting relationship shall be established for activities affecting safety of the facility.

a.

Lines of authority, responsibility and communication shall be established and documented in facility administrative procedures.

b.

The Site General Manager shall be responsible for safe operation of the facility and shall have control over those on-site activities necessary for safe operation and maintenance of the facility. The i

individual filling this position shall report directly to the Senior Nuclear Officer, c.

The individuals who perform audits, surveillances and independent safety reviews report to the Manager, Nuclear Performance Assessment Department.

6-1 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) d.

The individuals who train the Certified Fuel Handlers and those who carry out radiation protection functions report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY ORGANIZATION j

The facility organization shall be subject to the following:

a.

Each on-duty shift shall be comprised of at least the minimum shift crew composition shown in Table 6.21.

b.

At least one individual, who shall be qualified to stand watch in the MONITORING STATION, shall be in the MONITORING STATION when irradiated fuel is in the Spent Fuel Pool.

c.

During operations without FUEL HANDLING either the SHIFT Supervisor or the Non-Certified Operator shall be qualified in radiation protection procedures; or a Radiation Protection Technician shall be on site. During FUEL HANDLING operations a qualified Radiation Protection Technician shall be on site.

d.

When spent fuel is stored in the Spent Fuel Pool or during FUEL HANDLING operations, administrative procedures shall be implemented to limit the worF., hours of the facility staff wha perform safety related functions, and activities important to the safe storage of spent fuel and the monitoring and control of radiological hazards. These individuals include the minimum SHIFT crew required by Table 6.2-1, key maintenance personnel and Radiation Protection Technicians.

Adequate SHIFT coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

(1)

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding SHIFT turnover time.

(2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding l

SHIFT turnover time.

(3)

A break, including SHIFT turnover time, of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should 6-2 AS PROPOSED

2

+.-

A L--

A.

BIG ROCK POINT PERMANENTLY DEFUELED TECIINICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) be allowed after continuous work periods of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months duration.

Any deviation from the above guidelines shall be authorized by the Site General Manager or designated alternates in accordance with established administrative procedures and with documentation of the basis for granting the deviation.

Administrative procedures shall include a requirement for the Site General Manager or designated alternates to review individual overtime on a monthly basis in order to verify that excessive hours have not been assigned. Routine deviations from the above guidelines are not authorized.

TABLE 6.2-1: MINIMUM SHIFT CREW COMPOSITION DURING PERMANENTLY DEFUELED CONDITION STAFFING FOR STAFFING POSITION OPERATIONS DURING FUEL WITHOUT HANDLING FUEL HANDLING OPERATIONS SHIFT Supervisor (CERTIFIED FUEL HANDLER) 1 1

Non-Certified Operator 1

1 CERTIFIED FUE' MNDLER 1

Radiation Protection aechnician 1*

1 1f Shift Supervisor or Non-Certified operator are not certified in Radiation Pmtection Procedures e.

FUEL HANDLING operations shall be directly supervised by a CERTIFIED FUEL HANDLER who shall have no other concurrent responsibilities during this operation. CERTIFIED FUEL HANDLERS shall meet qualifications set forth in the CERTIFIED FUEL HANDLER Training Program.

f.

The SHIFT Supervisor shall be a CERTIFIED FUEL HANDLER.

g.

The SHIFT Supervisor shall report to an individual who is a CERTIFIED FUEL HANDLER.

h.

Personnel requirements of(a) and (c) above may be less than the minimum specified for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty personnel provided 6-3 AS PROPOSED

RIG ROCK POINT PERMANENTLY DEFUELED TECIINICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) immediate ACTION is taken to restore the minimum requirements specified. This provision only applies to on-SlilFT personnel and does not permit any SIIIFT crew position to be unmanned upon SIIIFT change due to oncoming SlilFT crew member being late or absent.

6.3 STAFF OUALIFICATIONS Each member of the facility management and supervisory staff shall meet the minimum requirements of ANSI N18.1-1971 for comparable positions. The individual responsible for radiation protection functions shall meet the minimum requirements of Regulatory Guide 1.8, September,1975.'

6.4 TRAINING A training program for the facility's CERTIFIED FUEL HANDLERS shall meet the requirements and recommendations of Section 5.5 of ANSI N18.1-1971. The Site General Manager has overall responsibility for implementation and maintenance of the training program.

6.5 REVIEW AND AUDIT 6.5.1 Requirements for on-site and off-site reviews and audits are described in CPC-2A, Quality Program Description.

6.6 PROCEDURES AND PJELGRAMS 6.6.1 PROCEDURES 6.6.1.1 Scope Written procedures shall be established, implemented and maintained for safety related structures, systems components and safety actions defined in the Big Rock Point Decommissioning Quality List and those structures, systems, components and activities important to the safe storage of spent fuel (ISSSF) and monitoring and control of radiological hazards (IMCRH). These procedures shall meet or exceed the requirements of ANS! N18.7-1976, as endorsed by the Quality Program Description (CPC-2A).

1 As applied to this specification," equivalent", as used in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) formal training in science engineering, or (b) operational or technical experience and training in nuclear power.

6-4 AS PROPOSED

I BIG ROCK POINT PERMANENTLY DEFUELED TECilNICAL SPECIFICATIONS l

l 6.0 ADMINISTRATIVE CONTROLS (continued) l Written procedures shall also be established, implemented, and maintained L

covering the following activities:

a.

Site security plan; b.

Site emergency plan; and, c.

All programs listed in Specification 6.6.2.

6.6.1.2 Review and Acproval Requirements for review and approval of procedures (and revisions thereto) required by this section are described in CPC-2A, Quality Program Description.

6.6.1.3 Temporary Changes Requirements for making temporary changes to procedures which fall within the scope of this section are described in CPC-2A, Quality Program Description.

6.6.2 PROGRAMS The following programs shall be established, implemented and maintained in accordance with written procedures meeting the requirements contained in specification 6.6.1:

6.6.2.1 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.6.2.2 High Radiation &ga 6.6.2.2.1 Dose Rates less than 1000 Millirem per Hour In lieu of the " control device" or " alarm signal" required by Paragraph 20.1601(a) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation I

penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by the use of a Radiation Work Permit (RWP). Radiation protection qualified personnel or personnel continuously escorted by radiation protection qualified personnel may be exempt from 6-5 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUEISD TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) working under an RWP during the performance of their assigned radiation protection duties in high radiation areas with exposure rates of less than or equal to 1000 mrem /hr, provided they are otherwise following facility radiation 1

protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area, or b.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them, or i

c.

A radiation protection qualified individual (e.g., Radiation Protection Technician) with a radiation dose rate monitoring device, responsible for providing positive control over the activities within the area.

6.6.2.2.2 Dose Rates equal to or greater than 1000 Millirem per Hour In addition to the requirements of 6.6.2.2.1, areas accessible to personnel with radiation levels greater than or equal to 1000 mrem!hr at 30 cm (12 inches) but l

less than 500 rad /hr at 1 meter from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under administrative controls specified in the facility administrative procedures. Doors shall remain locked except during periods of access by personnel under an approved RWP.

The dose rate levels in the immediate work areas and the maximum allowable l-stay time for individuals in that area shall be communicated to the individuals.

In lieu of a stay time specification, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the K

activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels L

greater than 1000 mrem /hr that are located within large areas where no l

enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a l

warning device.

l 1

l l

6-6 AS PROPOSED L

BIG ROCK PO, INT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) j 6.6.2.3 Process Control Program (PCP) l 6.6.2.3.1 Changes to the PCP l

l Changes to the PCP shall become effective after approval by the Site General Manager.

6.6.2.3.2 Reports Changes to the PCP shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the changes were made effective. This submittal shall contain sufficiently detailed information to support the rationale for each change and a determination that the change did l

not reduce the overall conformance of the solidified waste product to existing l

criteria for solid wastes.

l 6.6.2.4 Offsite Dme Calculation Manual (ODCM) 6.6.2.4.1 Changes to the ODCM Changes to the ODCM shall become effective after approval by the Site General Manager.

6.6.2.4.2 Reports Changes to the ODCM shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the changes were made effective. This submittal shall contain sufficiently detailed information to support the rationale for each change and a determination that the change did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

6.6.2.5 Radioactive Effluent Controls Program A program, conforming with 10 CFR 50.36a, for the control of radioactive effluents and for maintaining doses from radioactive effluents to members of the public as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by facility procedures, and (3) shall include remedial actions to be taken whenever program limits are exceeded.

l The program shall include the following elements:

i I

a.

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 6-7 AS PROPOSED

l BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

l 6.0 ADMINISTRATIVE CONTROLS (continued) b.

Limitations conforming to 10 times the concentration values specified in Appendix B, Table II, Column 2 to 10 CFR 20.1001-20.2402 for radioactive material released in liquid effluents to unrestricted areas; l

c.

Monitoring, sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; d.

Limitations conforming to Appendix I to 10 CFR Part 50 on the annual and quarterly doses or dose commitment tc a member of the public from radioactive materials in liquid effluents released from the facility to unrestricted areas; e.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days; f.

Lim.itations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.

g.

Limitations conforming to the doses associated with 10 CFR Part 50 on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY; h.

Limitations conforming to Appendix I to 10 CFR Part 50 on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the facility to areas beyond the SITE BOUNDARY; and i.

Limitations conforming to 40 CFR Part 190 on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources.

6.6.2.6 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the facility. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and 6-8 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECIINICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued)

(2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a.

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; b.

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, or alternatively, that critical receptors are assumed to exist at the SITE BOUNDARY or offsite location of highest dose consequence; and c.

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.6.2.7 Eim Protection Program A fire protection program meeting the requirements of 10 CFR 50.48(f) shall be established, implemented, and maintained.

6.6.2.8 Cold Weather Protection Program This program provides administrative controls to ensure that appropriate measures are implemented and maintained during cold weather to protect the facility against cold temperatures which could impact the safe storage of irradiated fuel or result in unplanned or unmonitored radioactive material release.

6.6.2.9 Scent End Ecol Water Chemistry Program This program uses procedures to provide controls for monitoring Spent Fuel Pool water chemistry.

6.6.2.10 Inservice Inspection and Testing Program a.

Applicability 6-9 AS PROPOSED

I BJG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) i Applies to Inservice Inspection and Testing of ASME Code Class 1, Class 2 and Class 3 piping systems and components.

b.

Objective To insure integrity of the Class 1, Class 2 and Class 3 piping systems and components.

c.

Specifications 1.

Inservice Inspection of ASME Code Class 1,2 and 3 components and Inservice Testing of ASME Code Class 1,2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Sectior 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(I), and where provisions of sections 11.4.1.4, 4.1.5 and 11.4.3.4 take precedence.

2.

Sufficient records of each inspection shall be kept to allow comparison and evaluation of future tests.

3.

The Inservice Inspection program shall be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven practical, and the conclusions of the evaluation shall be used as appropriate to update the inspection program.

6.7 REPORTING REOUIREMENTS The reports identified in this section shall be submitted in accordance with 10 CFR 50.4.

6.7.1 ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT An annual report of radiation exposures received during the previous calendar year shall be submitted prior to March 1 of each year. This report shall tabulate the numbers of facility, utility and other personnel (including contractors) receiving exposures greater than 100 millirem during the year, along with their associated dose according to work and job functions, for example, operations and. surveillance, routine maintenance, special maintenance (identify), and waste processing. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD or film badge measurements. Small exposures totaling less than 20 6-10 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

6.7.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An annual radiological environmental operating report covering operation of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpretations, and statistical evaluation of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCM and Sections IV.B.2, IV.B.3 an s iV.C of Appendix I to 10 CFR 50.

6.7.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT An annual radioactive effluent release report covering operation of the facility during the previous calendar year shall be submitted prior to May 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the ODCM and the PROCESS CONTROL PROGRAM, and shall comply with the requirements of 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

6.7.4 SPECIAL REPORTS The following special reports shall be submitted to the NRC as indicated.

a.

If the water quality specifications of 3.1.1.c are exceeded, and the water quality cannot be recovered after one week, prepare a special report that identifies the causes and proposed corrective action (s) to ensure future water quality is in compliance and submit to the NRC by 31 days following entry into the LCO.

b.

If the sealed source contamination limits of specification 3.4.1 are exceeded, a special report shall be submitted to the NRC within 30 days of idertification of the %tence of the excessive contamination. The report shall describe the equipment involved, the test results and corrective actions taken.

l c.

Inservice Inspection reports required by 10 CFR 50.55(a) and Section XI of the l

Code.

6-11 AS PROPOSED i

~

l BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

6.0 ADMINISTRATIVE CONTROLS (continued) 6.8 RECORQS Record retention requirements are described in CPC-2A, Quality Program Description.

i 6.9 REPORTABLE EVENTS A reportable event is any event or condition that must be reported to the NRC in J

accordance with 10CFR50.72,10CFR50.73, or 10CFR50.9(b).

t e

l l

l 6-12 AS PROPOSED

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-w m4 A&aMJ J AA, BIG ROCK POINT RESTORATION PROJECT DEFUELED TECHNICAL SPECIFICATIONS.

BASES s

TABLE OF CONTENTS l

l BASES FOR LIMITING CONDITIONS FOR OPERATION l

AND SURVEILLANCE REQUIREMENTS FOR BIG ROCK POINT PLANT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS SECTION DESCRIPTION PAGE #

3/4.0 APPLICABILITY..........

.... B3/4-l& 2 3/4.1 F U E L STO RAG E.................................................... B3/4-3 3/4.1.1 Spent Fuel Pool Parameters.................................... B3/4-3, 4 & 5 3/4.1.2 Spent Fuel Pool Emergency Support System Requirements................ B3/4-6 & 7 3/4.1.3 Fuel Storage General Requirements.............

B3/4-8 3/4.2.1 Fuel Handling Support System Requirements............................ B 3/4-9 3/4.2.2 Fuel I tandling General Requirenients................................. B3/4-10 3/4.3 CONTROL OF HEAVY LOADS..................................... B3/4-11 & 12 3/4.4 SEALED SOURCE CONTAMDiATION.................................. B3/4-13 i

l l

AS PROPOSED

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BASES FOR LIMITING CONDITIONS FOR OPERATION

'AND SURVEILLANCE REQUIREMENTS FOR THE BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS NOTE The bases contained in this section summarize the reasons for the Specifications in Section 3/4, but in accordance with 10 CFR 50.36, are not part of these Technical Specifications.

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AS PROPOSED

l RIG ROCK POINT PERMANENTLY DEFUFLFD TECHNICAL SPECIFICATIONS 3/4.0 APPLICABILITY BASES 3.0.1 This specification defines specifically when the other specifications in Section 3/4 are applicable.

3.0.2 This specification defines those conditions which must be met in order to comply with the terms of a Limiting Condition of Operation and its associated ACTION requirement.

3.0.3 This specification provides that entry into a specified Applicability condition may be made only when (a) the full complement of required systems, equipment and components are OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation are met without regard to allowable deviations and out of service provisions contained in the Action statements.

The intent of this provision is to ensure that activities are not initiated with required equipment inoperable or other specified limits being exceeded.

4.0.1 This specification establishes that, unless otherwise specified, surveillances must be performed during the specified applicable conditions for which the requirements of the Limiting Conditions for Operation apply. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a specified Applicability condition. The specification also establishes that surveillance requirements do not need to be performed when the facility is in a condition for which the requirements of the associated Limiting Conditions for Operation do not apply.

4.0.2 This specification establishes how long the specified time interval for a surveillance requirements may be extended. The intent of providing this allowance is to facilitate surveillance scheduling to account for conditions that may not be suitable for conducting the surveillance. It is not intended that this provision be used repeatedly as a convenience to extend the surveillance intervals beyond those specified.

l The allowable extension provided by Specification 4.0.2 is based on

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engineering judgement and the recognition that the most probable result of any particular surveillance is conformance with the surveillance requirement.

These provisions are sufficient to ensure that the reliability demonstrated through surveillance activities is not significantly degraded as a result of an extended interval.

l B3/4-1 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.0 APPLICABILITY BASES (continued) 4.0.3 The provisions of this specification set forth the criteria for detcrmining compliance with the OPERABILITY requirements of Limiting Conditions for Operation. Under these criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been j

satisfactorily performed within the specified time interval, including the maximum allowable extension. Nothing in this provision is to be construed as defining items OPERABLE when they are known to be inoperable even if they meet their associated surveillance requirements.

4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval, including the maximum allowable extension, prior to entry into specified applicability conditions. The intent of this provision is to ensure that i

surveillance activities have been satisfactorily demonstrated on a current basis j

as required to meet the OPERABII.ITY requirements of the Limiting Condition for Operation.

Unless a specification states otherwise, applicable surveillance activities must be performed within the stated surveillance interval prior to placing the associated item in an OPERABLE status.

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B3/4-2 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I

3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS BASES 3.1.1.a Spent Fuel Pool water level is normally maintained at the elevation of the discharge overflow weir, which is at elevation 630' 6" per drawing 0740G40153. However, the range for control is from 630' (siphon breaker-level) to 632' 6" (reactor deck). Maintaining water level at or above 630' l

ensures that 22' of water is maintained above the active fuel contained in the stored fuel assemblies in the spent fuel pool, which is the assumption used in the analysis of heavy load drop event in section 15.10.2.2 of the UFHSR.

Emergency cooling of the pool water is accomplished by a " feed and bleed" method that adds cooler inventory to the pool and removes the hotter inventory at the discharge weir. The minimum level required by this j

specification will ensure that the initial mass of the water in the pool is consistent with the Spent Fuel Pool thermal analysis which concludes that feed and bleed is a viable cooling method for the Spent Fuel Pool. This level allows operational flexibility by allowing interruption of Spent Fuel Pool cooling when dictated by operational needs.

The ACTION statement of this specification requires IMMEDIATE j

suspension of activities that can result in draining the pool to minimize the loss of inventory and IMMEDIATE initiation of the restoration of the water level.

The fuel assemblies and crane loads must be placed in a safe configuration; and further fuel movement suspended until level is restored. This action will minimize the probability of a FUEL HANDLING event before the water level i

is restored. However, CONTAINMENT CLOSURE is required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to minimize a release if an event were to occur and the water level is not I

available to support the thermal analysis or the radiological mitigating effects of scrubbing or shielding.

l Since installation of the stainless steel liner no liquid attributable to leakage of 4.1.1.a the Spent Fuel Pool has been observed. Based on empirical data, the rate of water loss from normal evaporation in the Spent Fuel Pool is not expected to exceed.0.1 gallons per minute (corresponding to less than a half inch loss in i

water level per day). As a result, the specified frequency for monitoring Spent Fuel Pool water level provides for early detection of decreasing water level and provides assurance that water level will not drop to a level significantly less than the specified level during the interval between readings.

L The level specified may be verified by visual inspection of the Spent Fuel Pool level or level instrumentation.

4 B3/4-3 AS PROPOSED i

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BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIO/

3/4.1 FUEL STORAGE l

3/4.1.1 SPENT FUEL POOL PARAMETERS BASES The maximum allowable Spent Fuel Pool temperatures is based upon the 3.1.1.b structural analysis of the concrete pool performed for the Spent Fuel Pool l

capacity expansion and is based on the concrete properties used in the l

analysis. Above 150 F concrete strength properties may begin to be reduced.

i Structural integrity is maintained for temperatures up to 150 F. Specifying 140 F as the upper temperature limit provides assurance that the pool remains at a temperature below the temperature at which concrete strength properties may begin to be reduced.

As documented in the UFHSR, a loss of Spent Fuel Pool Cooling event and its potential to result in approaching or exceeding the Spent Fuel Pool water temperature upper limit has been evaluated. At the time of permanent plant shutdown, an analysis was performed to determine the Spent Fuel Pool heatup rate, based upon the operating history of each assembly in the pool. On September 20,1997, the last fuel assembly was removed from the reactor vessel and placed in the Spent Fuel Pool. The results of the heat-up analysis show that the fuel had decayed sufficiently by December 5,1997, to allow pool cooling to be removed for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months without temperature exceeding 150 F (from an initial temperature of 80 F).

The criticality analysis performed for the Spent Fuel Pool expansion determined that K (neutron multiplication factor) is less than 0.95 at the most reactive temperature, which is greater than the minimum specified temperature F. The criticality parametric study conducted over the temperature of 40 range of 40 F to 212*F concluded that 40 F is the least reactive condition and 212 F is the most reactive condition. The specified minimum temperature ensures that freezing of the Spent Fuel Pool will not occur.

Based upon the UFHSR, achieving the minimum Spent Fuel Pool temperature of 40 F (or below) is considered unlikely. Initiators oflow temperature conditions would include loss of offsite power, boiler problems or ventilation system failures. Such a pool temperature would not only require a sustained loss of both offsite and onsite AC power during extremely cold weather conditions, but would presume that decay heat production from the spent fuel is negligible.

The ACTION requirements of this specification leads to restoration of i

acceptable temperatures in the Spent Fuel Pool. The manner of temperature l

restoration is not specified; the support systems required by Specification 3.1.2 provide assurance that Spent Fuel Pool cooling can be restored.

AS PROPOSED B3/4-4

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS BASES I

Spent Fuel Pool water temperature is verified twice per shift in order to permit 4.1.1.b early detection of abnormal Spent Fuel Pool cooling. This ensures that

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corrective action can be promptly taken.

f Maintaining Spent Fuel Pool water chemistry as specified ensures the Spent 3.1.1.c Fuel Pool water is suitable for long term storage of spent fuel. The specifications provided are consistent with the practices at facilities that provide long term storage of fuel. The conductivity limitation will maintain chlorides at less than 3 parts per million.

The ACTION requirements of this specification lead to restoration of acceptable water chemistry conditions.

I The surveillance requirements of this specification provide assurance that the 4.1.14 chemistry criteria are being met.

Maintaining at least one of the two Spent Fuel Pool area radiation monitors 3.1.1.d operable as specified in this section permits meeting the criticality accident monitoring requirements of 10 CFR 70.24(a)(2). The gamma radiation monitors provide an indication of Spent Fuel Pool criticality and elevated radiation levels that may be indicative of a release. Raising alarm settings beyond 20 mrem /hr may be necessary during the movement of spent fuel or radioactive component in or adjacent to the Spent Fuel Pool. When the option j

j to raise the alarm setpoint is exercised, the revised alarm setpoint must continue to meet the criticality detection criteria of 10 CFR 70.24(a)(2).

The ACTION requirements associated with this specification will provide the equivalent monitoring capability at a level required by 10CFR70.24(a)(2).

The surveillance requirements provide confidence in instrument performance.

4.1.1.d AS PROPOSED B3/4-5

i BIG ROCK POINT PERM ANENTLY DEFUELED TECIINICAL SPECIFICATIONS i

3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL EMERGENCY SUPPORT SYSTEM l

REQUIREMENTS BASES 3.1.2.a Maintaining a diesel generator as an alternate source of AC electrical power provides redundancy in the power supply to an electrically-driven water source. The identification of the diesel generator is not specified, however, the most likely alternates are the units previously identified as the Emergency Diesel Generator or Standby Diesel Generator. This redundancy in power supplies to an electric-motor driven pump ensures that a loss of off-site power will not result in a loss of emergency makeup cooling to the Spent Fuel Pool.

In the event no ac power source is available, a pump not requiring ac electrical power will provide emergency makeup cooling to the Spent Fuel Pool.

Requiring the availability of a diesel generator or pump not requiring ac electrical power within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is consistent with the slow rate of heat up of i

the Spent Fuel Pool (calculated to be approximately less than 1 F per hour after December 5,1997), the historical lack of Spent Fuel Pool leakage and the low rate of Spent Fuel Pool water inventory loss due to evaporation (discussed in the BASES for surveillance requirement 4.1.1.a).

3.1.2.b The pump performance requirements are to supply at least 28 gpm of water, at less than 100 F, to the Spent Fuel Pool. These parameters satisfy the design requirement to maintain the Spent Fuel Pool temperature less than 150 F.

Sources and required inventories of water to be used as the makeup supply are not specified. Normal Spent Fuel Pool makeup is supphed from treated radwaste or the demineralized water system. The pump design capacities associated with these sources are 100 gpm and 50 gpm respectively. Normal cooling is provided by a pool cooling system capable of removing the decay heat. As a backup, in the event that the normal makeup sources are unavailable, Lake Michigan water can be provided by the fire protection system.

The ACTION requirements of this specification ensures at an analyzed Spent Fuel Pool cooling source (28 gpm of water at a temperate lot greater than 100 F) will be available. Allowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to establish tnis alternate source is consistent with the slow rate of heatup of the Spent Fuel Pool (calculated to be less than 1 F per hour after December 5,1997), the historical lack of Spent Fuel Pool leakage and the low rate of Spent Fuel Pool water inventory loss due to evaporation (discussed in the BASES for surveillance requirement 4.1.1.a).

l B3/4-6 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TFCHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL EMERGENCY SUPPORT SYSTEM REQUIREMENTS BASES 4.1.2.a.i This surveillance requirement provides assurance of the availability of offsite AC power.

4.1.2.a.ii This surveillance requirement provides assurance of the availability of onsite AC power.

4.1.2.b.i This surveillance requirement provides assurance that the makeup pumps are available within the prescribed time and will perform as required.

4.1.2.b.ii This surveillance requirement provides assurance of the availability and flow capacity of SFP makeup.

B3/4-7 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS BASES 3.1.3.a The placement of material in the Spent Fuel Pool is restricted to ensure that the flow paths required to supply cooling to the spent fuel assemblies stored in the racks are clear. Natural circulation will develop across the spent fuel assemblies as buoyancy changes in the water due to heat transfer results in the l

warmer water rising to the top of the pool.

3.1.3.b Storage of material between the east wall and Rack B can result in disrupting the natural circulation patterns required for heat transfer in the pool and adversely affect the cooling flow to various spent fuel assemblies. (This storage restriction applies only to the space directly between Rack B and the east wall of the Spent Fuel Pool.)

3.1.3.c The south wall provides the least amount of shielding with respect to the thickness of the other Spent Fuel Pool walls. The activity level of the spent fuel stored closest to the south wall is restricted to minimize the radiological field through the wall.

The ACTION to suspend FUEL HANDLING operations and perform corrective actions will ensure that the coolable geometry and ALARA considerations of the Spent Fuel Pool are established before fuel movement resumes.

4J l The surveillances required by this specification provide assurance that the Spent Fuel Pool storage configuration continues to be satisfactory after fuel or other components have been handled in the Spent Fuel Pool. Performance of Surveillance 4.1.3.c is not required after August 29,1998 because after that date all fuel in the Spent Fuel Pool will have decayed by at least one year.

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B3/4-8 AS PROPOSED i

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i BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS j

3/4.2 FUEL HANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS BASES 3.2.1.a This specification assures that releases to the site boundary resulting from FUEL HANDLING events will be reduced by the containment shell during the decommissioning process. CONTAINMENT CLOSURE, as opposed to leak-tightness, is specified, since there is no propelling force associated with analyzed FUEL HANDLING accidents.

The ACTION associated with this specification is required to preclude FUEL HANDLING when CONTAINMENT CLOSURE does not exist or when containment ventilation valves are inoperable.

4.2.1.a The surveillance required by this r;,ecification provides assurance that CONTAINMENT CLOSURE exists and that the containment ventilation valves are OPERABLE prior to handling fuel inside containment.

3.2.1 b This specification has the same radiation level alarm setting requirements as 3.1.1.d. The gamma radiation monitors are to provide an indication of Spent Fuel Pool criticality and elevated radiation levels that may be indicative of a release. Raising alarm settings beyond 20 mrem /hr may be necessary during movement of spent fuel or radioactive components in or adjacent to the Spent Fuel Pool. When the option to raise the alarm setpoint is exercised, the revised alarm setpoint must continue to meet the criticality detection criteria of i

10 CFR 70.24(a)(2).

The ACTION associated with this specification is required to mitigate a radioactive release which may be indicated by the radiation alarm and to provide for the reduction of radiation levels to acceptable values.

4.2.1.b The surveillances required by this specification provide assurance that the SFP radiation monitor is OPERABLE to provide indication and alarm functions.

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l B3/4-9 AS PROPOSED

1 BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

L 3/4.2' FUEL HANDLING 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS

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BASES i

3.2.2.a The movement of spent fuel is restricted to one assembly at a time to minimize the consequences of a FUEL HANDLING accident to those analyzed for the drop of a single assembly.

1 The ACTION associated with this specification is required to place fuel 1

assemblies in a safe condition.

3.2.2.b The specified radiation level within the area of the south wall of the Spent j

Fuel Pool, elevation 600' 6" assures that if fuel movement has caused greater than expected radiation levels, the movement of fuel will be suspended and an investigation conducted.

The ACTION associated with this specification is required to permit determining the cause of the increased radiation levels, and specifically to determine if stored fuel is the cause of the increased levels.

4.2.2.b The frequency of performing the required radiation monitoring will provide I

assurance that increased radiation levels near the south wall of the Spent Fuel Pool caused by movement of fuel in the Spent Fuel Pool will not be undetected. The radiation readings should be taken at a distance from the wall which satisfies ALARA considerations and satisfies the geometric requirements to consider the Spent Fuel Pool wall as a plane source. This distance (or location) will be governed by applicable radiation monitoring procedures.

3.2.2.c Manual guidance and. visual observation of FUEL HANDLING operations will provide assurance that fuel movement is carefully conducted and monitored.

The ACTION associated with this specification is required to prevent FUEL HANDLING operations in the absence of adequate provisions for manual guidance and observation of the activity.

3.2.2.d Spent Fuel Pool water provides necessary shielding for the fuel handlers to minhnize occupational dose during normal SFP activities. Transfer of fuel from the pool requires the use of the 24 ton fuel transfer cask.

The ACTION associated with this specification is required to prevent fuel movement without using SFP water as shielding or the using the 24 ton fuel transfer cask.

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B3/4-10 AS PROPOSED l'

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS BASES 111 A heavy load is defined as 500 pounds (the weight of a fuel assembly and the handling equipment).

3.3.1.a This specification reflects a license condition resulting from the Spent Fuel Pool expansion and is reported in the May 15,1981 Safety Evaluation. It is expected that the largest load that would be required to be moved over the Spent Fuel Pool is the 24 ton fuel transfer cask and therefore no other load has been fully evaluated by the NRC.

The ACTION associated with this specification is required to place the crane load in a safe condition and prohibit resumption ofload handling activities until approved by the Site General Manager.

4.3.1.a This surveillance requirement provides assurance that the load will not exceed the 24 ton load limit.

l 3.3.1.b This specification reflects a requirement stated in NRC SER dated May 15, 1981, related to the expansion of the Spent Fuel Pool storage capacity. It is expected thr.t the only casks required to be moved over the Spent Fuel Pool are the 24 ton fuel transfer cask and possibly a cask required for permanently removing fuel from the Spent Fuel Pool. Use of the cask for permanent removal of the fuel from the Spent Fuel Pool (if not the current 24 ton fuel transfer cask) would require NRC approval because this situation has not been fully evaluated.

The ACTION associated with this specification is required to place the crane load in a safe condition and prohibit resumption of load handling activities o

until approved by the Site General Manager.

4.3.1.b This surveillance requirement provides assurance that the 24 ton fuel transfer cask is properly rigged and that only an NRC approved cask is used.

The ACTION associated with this specification is required to place the crane load in a safe condition and prohibit resumption of load handling activities-until approved by the Site General Manager.

3.3.1.c This specification reflects a requirement stated in May 15,1981 Safety Evaluation Relating to the Modincation of the Spent Fuel Storage Pool and

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requires operability of the 24 ton fuel cask safety catch device so that this backup feature is available prior to handling the cask over the SFP.

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l B3/4-11 AS PROPOSED l

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BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIOES l

3/4.3 CONTROL OF HEAVY LOADS BASES The ACTION associated with this specification is required to place the crane load in a safe condition and prohibit resumption of load handling activities until approved by the Site General Manager.

l 4.3.1.c This surveillance provides assurance that the trip mechanism is OPERABLE.

11Ld This specification assures that releases to the SITE BOUNDARY resulting l

from heavy loads events will be reduced by the containment shell.-

CONTAINMENT CLOSURE, as opposed to leak-tightness, is specified, since there is no propelling force associated with analyzed heavy loads accidents.

4.3.1.d The surveillance required by this specification provides assurance that CONTAINMENT CLOSURE exists.

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B3/4-12 AS PROPOSED

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.4 SEALED SOURCE CONTAMINATION BASES 3.4.1 The limitation'on removable contamination for sources requiring leak testing meets the limits of 10 CFR 70.39 for sources containing plutonium. The limitation provides assurance that leakage from sealed sources covered by the specification will not exceed allowable intake values.

1 The ACTION ensures that sources exhibiting leakage are controlled in accordance with NRC regulations.

4.4.1 For purposes of testing, the specification categorizes sealed sources into two groups (in use, or stored and not in use), with surveillance requirements commensurate with the probability of damage to a source in that group, i

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l B3/4-13 AS PROPOSED

ML20154M543

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