Text

Amend 120 to License DPR-6,changing License DPR-6 & App a, TS to Reflect Permanetly Shutdown & Defueled Status of Plant
	ML20198K658
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/24/1998
From:	Weiss S; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20198K657	List: ML20198K655; ML20198K658; ML20198K661;
References
	NUDOCS 9812310123
	Download: ML20198K658 (40)
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2 .E UNITED STATES NUCLEAR REGULATORY COMMISSION j- k 'E WASHINGTON. D.C. 2056H001 1

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CONSUMERS ENERGY COMPANY '

l DOCKET NO. 50-155 BIG ROCK POINT PLANT i

AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.120 License No. DPR-6

1. The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for amendment filed by the Consumers Energy Company (the licensee) dated September 19,1997, as supplemented October 10 and November 12,1997 and June 5, July 21 and 27, October 14, November 25, l

December 21,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the rules and regulations of the Commission and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to License No. DPR-6 and the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.A., 2.B.(1), 2.B.(2), 2.B.(2)(a) through (g), 2.B.(4), 2.C.(1) through (4),

and 2.C.(6) and (7) are hereby amended to read as follows:

A. This license applies to the 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 Sumrnary Report, as supplemented, updated, and amended by subsequent filings by the licensee.

9812310123 981224 ADOCh 05000155

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B.(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, " Domestic 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; B.(2) Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of 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 fission counters, (c) 150 kilograms of plutonium contained in PuO2 -UO fuel r ds, and (d) 5 curies of plutonium encapsulated as a plutonium 2 beryllium neutron source; (a) Deleted (b) Deleted (c) Deleted (d) Deleted (e) Deleted (f) Deleted ;

(g) Deleted '

i B.(4) Pursuant to the Act and 10 CFR Part 40, " Domestic 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; I 1

C.(1) Reactor Operation The reactor is not licensed for power operation. Fuel shall not be placed in the {

reactor vessel.

I C.(2) Technical Soecifications !

The Technical Specifications contained in Appendix A, as revised through Amendment No.120, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

C.(3) Physical Protection I

The licensee shall fully implement and maintain in effect all provisions of the <

physical security, guard training and qualification, and safeguards contingency I 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 protected under 10 CFR 73.21, entitled: " Big Rock Point Plant Security Plan," with revisions submitted through September 29,1988; Big Rock Point 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.

C.(4) Deleted C.(5) Deleted C.(6) Deleted I

C.(7) Deleted i D. This license amendment is effective as of the date of its issuance and shall be j implemented no later that 45 days from the date of issuance.' 1

, FOR THE NUCLEAR REGULATORY COMMISSION i

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La Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management l Office of Nuclear Reactor Regulation i

Attachment:

Changes to Technical Specifications Date of Issuance: December 24, 1998 l l

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ATTACHMENT TO LICENSE AMENDMENT NO.120 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 License No. DPR-6 and its Appendix A, Technical Specifications, have been arnended to reflect the permanently shutdown and defueled condition of the Big Rock Point Plant. The previous Technical Specification in its entirety shall be removed and replaced by the enclosed pages.

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l BIG ROCK POINT RESTORATION PROJECT 1

DEFUELED TECHNICAL SPECIFICATIONS l

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AMENDMENT NO. 120

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L TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS FOR BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 1.0 DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . ................. 1-1 1.1 Ac t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1-1 1.2 Certified Fuel Handler . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.3 Channel Calibration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.4 Channel Check .................................... 1-1 1.5 Channel Functional Test .............. ............... 1-1 1.6 Containment Closure '. . . . . . . . . . . . . . . . ... ............. 1-1 1.7 D irect Path . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.8 - Fuel Handling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 1-2 1.9 Immed iately . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 1-2 1.10 Monitoring Station . . . . . . . . . . ........................ 1-2 1.11 Offsite Dose Calculation Manual (ODCM) . . . . . . . . . . . . . . ..... 1-2 1.12 Operable - Operability .............. . .............. 1-3 1.13 Process Control Program (PCP) . . . . . . . . . . . . . . . . . . . . ...... 1-3 1.14 Reportable Event . . . . . . . . . . . . . . . . ................... 1-3 1.15 - Shift ................................ ........... 1-3 1.16 Site Bou ndary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEMS SETTINGS . . . . . 2-1 3/4 LIMITING CONDITIONS FOR OPERATION & SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . ........... 3/4-1 3/4.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... . 3/4-1 3/4.1 FUEL STORAGE . . . . . . . . . . . . . . . . . . . . . . . . . ...... 3/4-2 3/4.1.1 Spent Fuel Pool Parameters . . . . . . . . ....... . . . . 3/4 4 3/4.1.2 Spent Fuel Pool Support System Requirements .... . . . 3/4-5 & 6 3/4.1.3 Fuel Storage General Requirements . . . . . . . . . . . . . ... . 3/4-7 3/4.2 FUEL HANDLING . . . . . . . . . . . . . . . . . . . . . . . ... ... 3/4-8 3/4.2.1 Fuel Handling Support System Requirements . . . . . . ..... 3/4-8 3/4.2.2 Fuel Handling General Requirements . . . . . . . . . . . . . . 3/4-9 & 10 3/4.3 CONTROL OF HEAVY LOADS . . . . . . . . . . . . . . . . . . 3/4-11 & 12 3/4.4 SEALED SOURCE CONTAMINATION . . . . . . . . . ...... 3/4-13 11 AMENDMENT NO. 120

TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE l 5.0 DESIGN FEATURES .................................... 5-1

! 5.1 SITE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.1 Location and Boundaries . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 FIGURE 5.1-1, BRP Site Map ...................... 5-2 L 5.2 STORAGE AND INSPECTION OF SPENT FUEL , . . . . . . . . . . . . 5-1 l 5.2.1 Criticality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 1

5.2.2 Water Level . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 1 5.2.3 Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 1 l

5.2.4 Capacity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3

.5.3 REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -3

~5.3.1 Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.3 6.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . . . . . . . . f-1 6.1 RESPONSIBILITY AND AUTHORITY . . . . . . . . . . . . . . . . . . . . 6-1 6.1.1 Senior Nuclear Officer . . . . . . , . . . . . . . . . . . . . . . . . . . . . . 6-1

'6.1.2 Site Genera 1 Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 l 6.1.3 Shift Supervisor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 - ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6- 1

, 6.2.1 Reporting Relationships . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 I 6.2.2 Facility Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-2 TABLE 6.2-1, Minimum Shift Crew Composition . . . . . . . . . . 6-3 6.3 - STAFF QUALIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6.5 REVIEW AND AUDIT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6.5.1 CPC-2A Quality Program Description . . . . . . . . . . . . . . . . . . 6-4 l

6.6 PROCEDURES AND PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.6.1 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.6.1.1 Scope ................................... 6-5 6.6.1.2 Review and Approval . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.6.1.3 Temporary Changes . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.6.2 Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.6.2.1 Radiation Protection Program . . . . . . . . . . . . . . . . . . . . 6-6 6.6.2.2 High Radiation Area . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.6.2.3 Process Control Program (PCP) ..................6-7 6.6.2.4 Offsite Dose Calculation Manual (ODCM) . . . . . . . . . .. 6-8 g AMENDMENT NO. 120 i

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TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 6.6.2.5 Radioactive Effluent Controls Program . . . . . . . . . ... 6-8 6.6.2.6 Radiological Environmental Monitoring Program . . . . . . . 6-10 6.6.2.7 Fire Protection Program ....................... 6-10 6.6.2.8 Cold Weather Protection Program . . . . . . . . . . . . . . . 6- 10 6.6.2.9 Spent Fuel Pool Water Chemistry Program . . . . . . .... 6-11 6.6.2.10 Inservice Inspection and Testing Program . . . . . . . . . . . 6- 1 1 6.7 REPORTING REQUIREMENTS .................... ... 6-12 6.7.1 Annual Occupational Radiation Exposure Report ..... ..... 6-12 6.7.2 Annual Radiological Environmental Operating Report . . . . . .. 6-12 6.7.3 Annual Radioactive Effluent Release Report ........... .. 6-12 6.7.4 Special Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6- 13 6.8 RECORDS ................................. .... 6-13 6.9 REPORTABLE EVENTS ................ ...... .... 6-13 i

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ii AMENDMENT NO. 120 t

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1 BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS 1.1 ACTION ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

1.2 CERTIFIED FUEI HANDLER l

CERTIFIED FUEL HANDLER, is an individual who is qualified in accordance with BRP Program D25.1, " Certified Fuel Handler Initial Certification Program."

1 l 1.3 CHANNEL CAT IllRATION 1

l 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 of the parameter which the channel monitors. The CHANNEL l i

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

The CHANNEL CALIBRATION may be performed by any series of sequential, l- overlapping, or total channel steps such that the entire channel is calibrated.

i 1.4 CHANNEL CHECK 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 from independent instrumentation channels measuring the same l parameter.

1.5 CHANNEI FUNCTIONAL TEST 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.

1.6 CONTAINMENT CLOSURE l CONTAINMENT CLOSURE is that condition of containment in which there are l no direct paths from containment atmosphere to the outside atmosphere, except for i 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. l l

l 1-1 AMENDMENT N0. 120 ,

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BIG ROCK POINT DEFUEI FD TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS l t

i 1.7- DIRECT PATH !

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A DIRECT PATH is a visually observable opening which permits the free exchange of air between containment and the environs. Equipment configurations or an engineered feature such as a closed valve, check valve, water 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 FUFI HANDLING FUEL HANDLING means the activities associated with moving spent nuclear fuel, including moving the 24 ton fuel transfer cask when it contains spent fuel. When spent nuclear fuel is contained in a closed and sealed permanent storage cask or associated transfer device, the activities associated with moving the cask or device l

when it is outside the Spent Fuel Pool Area are not to be considered FUEL i HANDLING. I 1.9 IMMEDIATELY l

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 decommissioning process. The Control Room shall remain the MONITORING !

STATION until such time as a new facility is activated to serve this function.

1.11 OFFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE 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. i 1-2 AMENDMENT NO. 120

l BIG ROCK POINT DEFUEIID TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS

! 1.12 OPERABI E - OPERABILITY

[ A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capble of performing its specified function (s) and when l all necessary attendant instrum.ntation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that 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) I The PROCESS CDNTROL PROGRAM contains the methods and determinations l 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 l and 71, State regulations, burial ground requirements, and other requirements

governing the disposal of solid radioactive waste.

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

1.15 SHIFT l

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.

t 1-3 AMENDMENT NO. 120

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS j 2.0 ~ SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS There are no safety limits or limiting safety system settings applicable to the permanently defueled condition.

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2-1 AMENDMENT NO. 120

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l BIG ROCK POINT DEFUEI FD TECHNICAL SPEGEICATIONS l

'3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 3/4.0 APPLICABII ITY LIMITING CONDITIONS FOR OPERATION 3.0.1 Complianc. 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. )

SURVEILLANCE 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.

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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 l

the maximum allowable extension.

I 3/4-1 AMENDMENT NO. 120 l

BIG ROCK POINT DEFUEI ED TECHNICAL SPECIFICATIONS ~

3/4.1 FUFL STORAGE l 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'.

l l b. Spent Fuel Pool water temperature *all 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:

l pH 5.0 to 9.0 Conductivity less than or equal to 10.0 micrombos per cm at 77 "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 10 CFR 70.24(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.

APPLICABII ITY: 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 movement of fuel assemblies and 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 i fuel assemblies and the crane load in a safe condition. suspend L further movement of fuel assemblies and crane operations with loads 3/4-2 AMENDMENT NO. 120

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BIG ROCK POINT DEFUEIED TECHNICAL SPECIFICATIONS ;

i 3/4.1 FUEI STORAGE l l

L 3/4.1.1 SPENT FUEL POOL PARAMETERS l !

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L 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 i 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.

L i iv. With the requirements of 3.1.1.d not met, IMMEDIATELY provide I l - an alternate method of monitoring Spent Fuel Pool radiation levels.

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If the alternate instrumentation does not have an audible alarm, locally and in the MONITORING STATION, radiation levels shall be continuously monitored by personnel in communication with the MONITORING STATION, when personnel are in the vicinity of the l

Spent Fuel Pool.

l The provisions of Specification 3.0.3 are not applicable.

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

l- 4.1.1.b Twice per SHIFT, Spent Fuel Pool water temperature shall be determined to meet I 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 t

4' i p 3/4-3 AMENDMENT NO. 120 L

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s BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS

'3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS SURVEILLANCE REQUIREMENTS 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.

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3/4-4 AMENDMENT NO. 120 i

l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.2 - SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS

' LIMITING CONDITIONS FOR OPERATION 3.1.2 The capability to supply makeup to the Spent Fuel Pool shall be maintained as follows:

a. 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 an onsite electric motor-driven pump shall be available QE, h

One offsite source of ac power capable of providing power to operate an onsite electric motor-driven pump shall be available, .QE, i-l: An onsite 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 j 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 l temperature equal to or less than 100 *F to the Spent Fuel Pool. The l capability to manually initiate at least 28 gpm flow to the Spent Fuel Pool shall be maintained.

l APPLICABli TTY: When spent fuel is in the Spent Fuel Pool.

t ACTION: With 'he requirements of Specifications 3.1.2.a or 3.1.2.b not met, within l 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 l 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.

l 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.

t 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.

3/4-5 AMENDMENT NO. 120

s e i

l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS I

-3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS SURVEILLANCE REQUIREMENTS ii. Once per 12 months, Spent Fuel Pool makeup shall be determined to be l OPERABLE by verifying its flow capacity to be at least 28 gpm. ,

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4 3/4-6 AMENDMENT NO. 120 l

L

BIG ROCK POINT DEFUEI ED TECHNICAL SPECIFICATIONS

'3/4.1 FUEI STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.1.3 The following limitations shall apply to the storage of spent fuel in the Spent Fuel Pool.

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

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

APPLICABII3TY: When spent fuel is in the Spent Fuel Pool.

l l

' ACTION: With the requirements of Specifications 3.1.3.a or 3.1.3.b not met, suspend l Spent Fuel Pool work activities other than required surveillance activities l 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 requirements 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 l involving movement of components in the Spent Fuel Pool, verify that the requirements of Specification 3.1.3.b have been met.

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i 3/4-7 AMENDMENT NO. 120 t

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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING i

l 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS i LIMITING CONDITIONS FOR OPERATION-3.2.1 The following conditions apply when handling fuel inside containment. ;

1

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

! being closed.

L 1 g b. Radiation levels shall be maintained below the alarm setting requirements of l l Specification 3.1.1.d. !

l i

APPLICABTI TTY: When handling fuel inside containment. 1 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 inside containment.

l l . ii. With the requirements of Specification 3.2.1.b not met, initiate closure of containment ventilation inlet and wist valves and initiate corrective actions to reduce the iadia .on evels to acceptable

! values.

SURVEILLANCE REQUIREMENTS l

4.2.1 a. Prior to commencement of FUEL HANDLING activities, perform verification of CONTAINMENT CLOSURE for all containment I

penetrations or openings arxl verify OPERABILITY of containment ventilation valves (CV-4094, CV-4095, CV-4096, CV-4097).

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

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3/4-8 AMENDMENT NO. 120 m .

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.2.2 FUEL HANDLING operations shall conform to the following requirements:

a. Movement of spent fuel into and out of the storage racks or inspection 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 during FUEL HANDLING operations.

c. FUEL HANDLING shall be accomplished by manual guidance and visual 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 ofincreased 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.

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

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

l 3/4-9 AMENDMENT NO. 120

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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS

(

3/4.2 FUEL HANDLING l

3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS SURVEILLANCE REQUIREMENTS 4.2.2 a. None.

l l b. Prior to commencing, once per SHIFT decing 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 i requirements of Specification 3.2.2.b are met.

1

c. None.

d. None.

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3/4-10 AMENDMENT NO. 120 l

l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS LIMITING CONDITIONS FOR OPERATION l

3.3.1 Handling of heavy loads over or in the Spent Fuel Pool shall conform to the following requirements:

a. Use of the reactor building gantry crane over the Spent Fuel Pool for loads exceeding 24 tons is prohibited.

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. ,

ii. Cask handling operations shall be limited to the southwest corner 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 shall exist.

APPLICABII TTY: 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.

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3/4-11 AMENDMENT NO. 120 l

1 . ,

l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 1

3/4.3 CONTROL OF HEAVY LOADS SURVEILLANCE REQUIREMENTS l 4.3.1 a. Prior to moving a load over the SFP, verify that the load does not exceed 24 l tons.

l b. Prior to moving a cask over the SFP, verify that the cask is the properly rigged 24 ton fuel transfer cask, or another cask specifically approved by l NRC for use in or over the Spent Fuel Pool.

l l c. Prior to handling of the 24 ton fuel transfer cask over or in the Spent Fuel Pool, the trip mechanism of the cask safety catch device shall be I

functional.ly tested.

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

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l I

l 1

l 3/4-12 AMENDMENT NO. 120 l

i i

L BIG ROCK TOINT DEFUELED TECHNICAL SPECIFICATIONS l'

l 3/4.4 SEATED 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 em;tting material shall not l l have removable contamination which equals or exceeds 0.005 microcuries. l APPLICABII ITY: At all time .

l 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 I by Specification 6.7.4.b.

l SURVEILLANCE REQUIREMENTS l 4.4.1 Except for: 1) sealed sources which are stored and not in use, and 2) start up sources and fission detectors previously subjected to core neutron flux, sealed sources containing radioactive materials in any form other than gas and with a half-life greater than 30 days (excluding 3H3) shall be tested for contamination and/or leakage at least 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 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 of leak test results shall be kept in units of microcuries and maintained for inspection by the NRC.

a. Scaled 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.

i 3/4-13 AMENDMENT NO. 120

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES u

l 5.1 SITE 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).

I 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 j assemblies to ensure a k,n less than or equal to 0.95 when the ract:s are flooded with unborated water.

The fuel loading per axial centimeter of any assembly placed in the Spent Fuel Pool shall be less than or equal to a maximum of 28.3 grams of U2" 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.

l l 5.2.2 WATER LEVEL l

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.

5-1 AMENDMENT NO. 120 i

l

i Il1GRQCK POINT DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES Figure 5.1-1, BRP Site Map I-2 0 0 4

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~. /i 5-2 AMENDMENT NO. 120

]

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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES 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 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 subcriticality.

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

1

+ 2500 kilograms of contained uranium 235.

10.32 grams of uranium 235 as contained in fission counters.

150 kilograms of plutonium contained in PuO2 -UO2 fuel rods. l

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

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

1 5-3 AMENDMENT NO. 120

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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS l 6.1 RESPONSIBIIITY AND AUTHORITY 6.1.1 SENIOR NUCLEAR OFFICER The Senior Nuclear Officer shall be the Senior Vice President - Nuclear, Fossil, end Hydro Operations and shall be responsible for the overall operation, maintenance and deconunissioning 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 in writing the succession to this responsibility. Unless otherwise specified, the Site General Manager's delegate has authority to perform all actions and grant !

p approvals assigned by these specifications to the Site General Manager The !

Site General Manager may delegate specific tasks to other individuals who may l

perform those tasks whether the Site General Manager is absent or present at i the site.

6.1.3 SHIFT SUPERVISOR l

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 l Onsite organization and corporate reporting relationship shall be established for activities affecting safety of the facility.

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

I

b. The Site General Manager shall be responsible for safe operation of the facility and shall have control over those onsite activities necessary for i

safe operation and maintenance of the facility. The individual filling this position shall report directly to the Senior Nuclear Officer.

c. The individuals who perform audits, surveillances and independent 6-1 AMENDMENT NO. 120

l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS l l

'6.0 ADMINISTRATIVE CONTROLS I safety reviews report to the Manager, Nuclear Performance Assessment Department.

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

l

\

l 6.2.2 FACILITY ORGANIZATION '

The facility organization shall be subject to the following: l

a. Each on-duty shift shall be comprised of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one individual, who shall be qualified to stand watch in the !

MONITORING STATION, shall be in the MONITORING STATION I when irradiated fuel is in the Spent Fuel Pool.

c. During operations without FUEL HANDLING either the SHIFT l 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.

i

d. When spent fuel is stored in the Spent Fuel Pool or during FUEL HANDLING operations, administrative procedures shall be i implemented to limit the working hours of the facility staff who perform safety-related functions, and activities important to the safe storage of spent fuel (ISSSF) and the monitoring and control of radiological hazards (IMCRH). These individuals include the minimum l 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 o. f overtime. However, in the event that unforeseen problems l require substantial amounts of overtime to be used, the following guidelines shall be followed:

An individual should not be permitted to work more than 16 (1) hours straight, excluding SHIFT turnover time.

6-2 AMENDMENT NO. 120

< a BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (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 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 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 I POSITION OPERATIONS WITHOUT DURING FUEL HANDLING FUEL HANDLING OPERATIONS SHIFT Supervisor (CERTIFIED FUEL HANDLER) 1 1 Non-Certified Operator 1 1 CERTIFIED FUEL HANDLER 1 Radiation Protection Technician 1* 1 44

If Shift Supervisor or Non-Certired Operator are not certired in Radiation Protection 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.

6-3 AMENDMENT NO. 120

i BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS '

~6.0 ADMINISTRATIVE CONTROL.S

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.

i

h. Personnel requirements of (a) and (c) above may be less than the l 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 l to accommodate unexpected absence of on-duty personnel provided immediate ACTION is taken to restore the minimum requirements specified. This provision only applies to on-SHIFT personnel and does not permit any SHIFT crew position to be unmanned upon SHIFT change due to oncoming SHIFT crew member being late or absent.

6.3 STAFF OUAI IFICATIONS Each member of the facility management and supervisory staff shall meet the miarmum 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 1975.3 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 N18.1-19.71.

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 onsite and offsite reviews and audits are described in CPC-2A, Quality Program Description.

1 As applied to this specificatim, " 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 fe.owing: (a) formal training in science engineering or (b) operational or technical experience and training in nuclear power.

6-4 AMENDMENT NO. 120

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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS i 6.0 ADMINISTRATIVE CONTROLS 6.6 PROCEDURES AND PROGRAMS 6.6.1 PROCEDURES 6.6.1.1 Scope i Written procedures shall be established, implemented and maintained for safety related structures, systems components and safety actions defm' ed in the Big Rock Point Decommissioning Quality List and those structures, systems, components and activities important to the safe storage of spent fuel (ISSSF) i and monitoring and control of radiological hazards (IMCRH). These procedures shall meet or exceed the requirements of ANSI N18.7-1976, as ndorsed by the Quality Program Description (CPC-2A). i l

Written procedures shall also be established, implemented, and maintained covering the following activities:

a. Defueled Security Plan;

b. Defueled Emergency Plan;

c. Quality Program Description (CPC-2A); and,

d. All programs listed in Specification 6.6.2.

6.6.1.2 Review and Anoroval 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 Chanoes Requirements for making temporary changes to procedures which fall within the scope of this section are described in CPC-2A, Quality Program Description.

1 i

6-5 AMENDMENT NO. 120

, 7 l

BIG ROCK POINT DEFUELED TECilNICAL SPECIFICATIONS j L 6.0 ADMINISTRATIVE CONTROLS 6.6.2 PROGRAMS l The following programs shall be established, implemented and maintained in accordance with written procedures meeting the requirements contained in l Specification 6.6.1:

6.6.2.1 Radiation Protection Procram l Procedures for personnel radiation protection shall be prepared consistent with !

the requirements of 10 CFR Part 20 and shall be approved, maintained and l

adhered to for all operations involving personnel radiation exposure.

6.6.2.2 Mich Radiation Area

6.6.2.2.1 Dose Rates less than or equal to 1000 Millirem per Hour In lieu v 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 or equal to 1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation 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 working under an RWP during the performance of their i

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 u facility radiation protection procedures for entry into such high radiation areas.

l ' Any individual or group of individuals permitted to enter such areas shall be i provided with or accompanied by one or more of the following:

[ a. A radiation monitoring device which continuously indicates the l rediation dose rate in the area, or

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas may be made after 'he dose rate levels in the area have been established and personnel have been made knowledgeable of them, or

c. A radiation protection qualified individual (e.g., Radiation Protection I

Technician) with a radiation dose rate monitoring device, responsible 4

6-6 AMENDMENT N0. 120

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g__ _ _ _ _ _ . _ . . _ _ - _ . . _ . _ _ - _ . . . . _ . _ . _ . . _ . _ _ . _ _ _

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS for providing positive control over the activities within the area.

6.6.2.2.2 Dose Rates 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 1000 mrem /hr at 30 cm (12 inches) but less than 500 rad /hr at I meter from the radiation source or from any .curface 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 which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. 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 activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels greater than 1000 mrem /hr that are located within large areas where no 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 warning device.

6.6.2.3 Process Control Program (PCP) 6.6.2.3.1 Changes to the PCP l

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

L 6.6.2.3.2 Reports l

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 not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

6-7 AMENDMENT NO. 120

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS for providing positive control over the activities within the area.

6.6.2.2.2 Dose Rates greater than 1000 Millirem per Hour In addition to the requirements of 6.6.2.2.1, areas accessible to personnel with l radiation levels greater than 1000 mrem /hr at 30 cm (12 inches) but 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 which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. 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 activities being performed within the area. l For individual high radiation areas accessible to personnel with radiation levels greater than 1000 mrem /hr that are located within large areas where no enclosure exists for pwposes oflocking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuo asly posted, and a flashing light shall be activated as a warning device.

6.6.2.3 Process Control Program (PCP) 6.< 2.3.1 Changes to the PCP 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 ar.d a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

I' 6-7 AMENDMENT NO. 120

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l BIG ROCK POINT DEFUEIED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.6.2.4 Offsite Dose 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. The program shall include the following elements:

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;

b. Limitations conforming to 10 times the concentration values specified in Appendix B, Table 2, Column 2, to 10 CFR 20.1001 - 20.2402 for the radioactive material release in liquid effluents to unrestricted areas.

c. Monitoring, sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and para"eters in the ODCM;

d. Limitations conforming to Appendix I to 10 CFR Part 50 on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the facility to unrestricted areas; 6-8 AMENDMENT NO. 120

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS

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. Limitations 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. The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the site boundary (see Figure 5.1-1) shall be limited to the following:

(a) For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and (b) For tritium and for all radionuclides in particulate form with halflives greater than 8 days: less than or equal to 1500 mrems/yr to any organ,

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 Pan 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.

j. The dose to a member of the public from tritium and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at or beyond the site boundary (see Figure 5.1-1) shall be limited to the following:

(a) During any calender quarter: Less than or equal to 7.5 mrems to any organ, and (b) During any calender year: less than or equal to 15 mrems to any organ.

6-9 AMENDMENT NO. 120

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l s e BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS i

6.6.2.6 Radiological Environmental Monitoring Procram _ _

q l A program shall be provided to monitor the radiation and radionuclides in the i environs of the facility. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (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 i and parameters in the ODCM; l

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 i of radioactive materials in environmental sample matrices are

performed as part of the quality assurance program for environmental monitoring.

l 6.6.2.7 Fire Protection Program l 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.

6-10 AMENDMENT NO. 120

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BIG ROCK POINT DEFUEI FD TECHNICAL SPECIFICATIONS l 6.0 ADMINISTRATIVE CONTROLS 6.6.2.9 Soent Fuel Pool Water Chemistry Program This program uses procedures to provide controls for monitoring Spent Fuel Pool water chemistry.

t 6.6.2.10 Inservice Insnection and Testino Program

a. Applicability 1

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.

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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, Section 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.

l 6-11 AMENDMENT NO. 120 l

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l BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS l 6.0 ADMINISTRATIVE CONTROLS 6.7 REPORTING REOUIREMENTS The reports identified in this section shall be submitted in accordance with ;

10 CFR 50.4. !

l l l 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 I 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 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 t.wigned 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 and 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.

6-12 AMENDMENT NO. 120

BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.7.4 SPECIAL REPORTS The following special reports shall be submitted to the NRC as indicated.

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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 proposeo corrective action (s) to ensure future water quality is in compliance and submit to the NRC by 31 days following entry into the LCO.

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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 l of identification of the existence of the excessive contamination. The report shall describe the equipment involved, the test results and corrective actions taken.

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c. Inservice Inspection reports required by 10 CFR 50.55a and Section XI l of the ASME Boiler and Pressure Vessel Code.

6.8 RECORDS Record retention requirements are described in CPC-2A, Quality Program Description.

6.9 REPORTABLE EVENTS l A reportable event is any event or condition that must be reported to the NRC l in accordance with 10 CFR 50.72,10 CFR 50.73, or 10 CFR 50.9(b).

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i 6-13 AMENDMENT NO 120 l

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