Text

Proposed Change No. 217: License and Technical Specification
	ML032950090
Person / Time
Site:	Maine Yankee
Issue date:	10/14/2003
From:	Williamson T; Maine Yankee Atomic Power Co
To:	; Document Control Desk, NRC/FSME
References
	-RFPFR, MN-03-064, RA-03-153
	Download: ML032950090 (89)
	v • d • e

Maine Yankee 321 OLD FERRY RD. WISCASSET. ME 04578-4922 October 14, 2003 MN-03-064 RA 153 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, DC 20555

References:

(I)

License No. DPR-36 (Docket No. 50-309)

(2)

Maine Yankee Letter to NRC, Certifications of Permanent Cessation of Power Operation and Permanent Removal of Fuel from the Reactor, (MN-97-89), dated August 7, 1997.

(3)

NRC Administrative Letter (AL) 95-06: "Relocation of Technical Specification Administrative Controls Related to Quality Assurance,"

dated December 12, 1995.

Subject:

Proposed Change No. 217: License and Technical Specifications Pursuant to 10 CFR 50.90, Maine Yankee hereby requests Nuclear Regulatory Commission (NRC) review and approval of a modification to the License and to the Technical Specifications.

The proposed changes to the License would eliminate License information that no longer applies to a licensee that has permanently ceased operation. Maine Yankee recommends deletion of the paragraph under License title "Maximum Power Level". Pursuant to 10 CFR 50.82, licensees who have docketed certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel (Reference 2) are no longer authorized to operate the reactor.

Maine Yankee also recommends the deletion of License paragraph 2.B.(8) since with permanent cessation of operations and pursuant to 10 CFR 50.51, the License continues in effect beyond the expiration date until the Commission notifies the licensee in writing that the License is terminated.

The proposed changes to the Technical Specifications would simplify the Technical Specifications by removing certain design and administrative requirements and relocating them to the to the Defueled Safety Analysis Report or the Quality Assurance Program. This relocation is being proposed pursuant to the criteria contained in 10 CFR 50.36 and in accordance with NRC Administrative Letter 95-06 (Reference No. 2). Additionally, Maine Yankee proposes to eliminate technical specifications that will no longer be applicable following the transfer of the last fuel assembly from the spent fuel pool to the Independent Spent Fuel Storage Installation (ISFSI).

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U. S. NUCLEAR REGULATORY COMMISSION

" -Attention:

Document Control Desk Page 2 of 5 The Technical Specification proposed changes consist, in part, of the following:

Deletion of Technical Specification, Section 1.0, USE AND APPLICATION since this section does not apply to a completely defueled plant.

Deletion of Technical Specification, Section 3.0, LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY since this section does not apply to a completely defueled plant.

Deletion of Technical Specification, Section 3.1, DEFUELED SYSTEMS since this section only applied during the storage of spent fuel assemblies in the fuel storage pool or during movement of irradiated fuel assemblies in the fuel storage pool.

Deletion of the specified minimum distance to the boundary of the exclusion area from Technical Specification Design Features Section 4.1 and relocation of the requirement to the Defueled Safety Analysis Report.

Deletion of Technical Specification, Section 4.2, Fuel Storage and associated Figure 4.1-1, Spent Fuel Pool Assembly Placement since this section only applied during the storage of irradiated fuel in the fuel storage pool.

Deletion of the following Technical Specification, ADMINISTRATIVE CONTROLS, and relocation of these administrative controls to the Maine Yankee Quality Assurance Program:

Section 5.1, "Responsibility" Section 5.2, "Organization" Section 5.3, "Unit Staff Qualifications" Section 5.4, "Training" Section 5.5, "Procedures" Subsection 5.6.1, "Radiation Protection Program" Subsection 5.6.2, "Offsite Dose Calculation Manual (ODCM)"

Subsection 5.6.3, "Radioactive Effluent Controls Program" Deletion of Technical Specification, Subsection 5.6.4, Technical Specifications (TS) Bases Control Program since as stated below the Technical Specification Bases Section will cease to exist.

Deletion of Technical Specification, SubSection 5.6.5, Spent Fuel Water Chemistry Program since irradiated fuel will no longer be stored in the Fuel Storage Pool.

Deletion of Technical Specification, SubSection 5.6.6, Inservice Testing Program since safety related ASME Code Class, 2, and 3 components, including associated supports, no longer exist at the Maine Yankee plant.

U. S. NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Page 3 of 5 Deletion of Technical Specification, Section 5.7, Reporting Requirements, and relocation of these administrative controls to the Maine Yankee Quality Assurance Program.

Deletion of Technical Specification, Section 5.8, High Radiation Area, and relocation of these administrative controls to the Maine Yankee Quality Assurance Program.

Deletion of Technical Specification - Bases Section since the Section is not applicable to a completely defueled plant.

The License and Technical Specification Proposed Changes, Attachment I, provides a description section, identifies the proposed changes and bases for changes, provides a no significant hazards consideration determination and an environmental impact consideration determination. Attachment II provides marked-up pages showing the proposed changes to the License. Attachment III provides a copy of the affected Technical Specification page with changes annotated. Attachment IV provides an updated version of the revised Technical Specification pages.

Maine Yankee is requesting approval of the proposed change prior to completion of transfer of spent fuel assemblies to the ISFSI. Transfer of spent fuel assemblies is expected to be complete by February, 2004.

Maine Yankee requests implementation of the approved license amendment to be within 30 days after transfer of the last spent nuclear fuel assembly from the spent fuel pool to the Independent Spent Fuel Storage Installation (ISFSI).

Also, as evident in the revised Technical Specification, Attachment IV, the Technical Specification when approved will be reduced to a single paragraph in Section 4 that provides a description of the plant location. This remaining information is not germane to Technical Specification requirements under 10 CFR 50.36. Maine Yankee therefore requests NRC consider the deletion of Technical Specifications from the Maine Yankee Part 50 License.

These changes do not involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in the margin of safety.

These proposed changes have undergone an Independent Safety Review. The Independent Review and Audit Committee has also reviewed these proposed changes. A representative of the State of Maine is being informed of this request by a copy of this letter.

U. S. NUCLEAR REGULATORY COMMISSION

\\----,Attention: Document Control Desk Page 4 of 5 If you have any questions, please contact us.

Sincerely, Thomas L. Williamson, Director Nuclear Safety and Regulatory Affairs Attachments: (1)

Evaluation of Proposed Technical Specification Change (2)

Proposed Technical Specification Changes (mark-up)

(3)

Proposed Technical Specification pages (retyped) cc:

Dr. R. R. Bellamy, NRC Region I Mr. J. T. Buckley, NRC NMSS Project Manager, Decommissioning P. Craighead, Esq., State of Maine, Nuclear Safety Advisor Mr. P. J. Dostie, State of Maine, Division of Health Engineering D. R. Lewis, Esq., Shaw Pittman Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. M. C. Roberts, NRC, Region I Mr. R. Shadis, Friends of the Coast

U. S. NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Wage 5 of 5 AFFIDAVIT STATE OF MAINE Then personally appeared before me, Thomas L. Williamson, who being duly sworn did state that he is the director, Nuclear Safety and Regulatory Affairs of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.

Notary Public My commission expires I l1GAG

I9 ATTACHMENT I PROPOSED CHANGE NO. 217 DESCRIPTION AND EVALUATION OF CHANGES

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217

Subject:

Proposed Changes: License and Technical Specifications Table of Contents DESCRIPTION.....................................

2 PROPOSED CHANGES & BASES FOR CHANGES.

2 SIGNIFICANT HAZARDS CONSIDERATIONS..

18 ENVIRONMENTAL CONSIDERATIONS......................

20 Page of21

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ATTACHIMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 DESCRIPTION This submittal is a request to amend Operating License No. DPR-36 for Maine Yankee.

Maine Yankee proposes changes to its License and to the associated Technical Specifications.

The proposed changes would eliminate License information that no longer applies to a license that has permanently ceased operation. The proposed changes would also simplify the Technical Specifications. Maine Yankee proposes to remove certain design and administrative requirements, relocate them to the to the Defueled Safety Analysis Report or the Quality Assurance Program and make other minor administrative changes. The Technical Specification relocation is being proposed pursuant to the criteria contained in 10 CFR 50.36 and in accordance with NRC Administrative Letter 95-06. Additionally, Maine Yankee proposes to eliminate technical specifications which will no longer be applicable following the transfer of the last fuel assembly from the spent fuel pool to spent fuel storage cask. The proposed changes to the Technical Specification are similar to the NRC approved changes provided to the Yankee Atomic Electric Company Technical Specifications on April 18, 2003 (TAC No. L52086).

PROPOSED CHANGES & BASES FOR CHANGES The proposed changes consist of the following:

Deletion of License paragraph under the title "Maximum Power Level".

Pursuant to 10 CFR 50.82, licensees who have docketed certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel are no longer authorized to operate the reactor. The paragraph under "Maximum Power Level" does not apply to the Maine Yankee plant since it has ceased from operations.

Deletion of License paragraph 2.B.(8).

Pursuant to 10 CFR 50.51, the License for a plant that has permanently ceased operation continues in effect beyond the expiration date until the Commission notifies the licensee in writing that the License is terminated.

Deletion of Technical Specification, Section 1.0, USE AND APPLICATION.

Deletion of this Section is proposed since the section does not apply to a completely defueled facility. Technical Specification use and application of terms, such as, Required Actions, Logical Connectors, Completion Times, and Surveillance Requirements are associated with Limiting Conditions for Operation (LCO's) minimum requirements for ensuring the safe storage of Page 2 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 irradiated fuel. With complete transfer of irradiated fuel to the ISFSI, Spent Fuel Pool Storage LCO's cease to exist and Section 1.0 is no longer required.

The definition for CERTIFIED FUEL HANDLER has been deleted. With completion of spent fuel transfer to the ISFSI, the handling of spent fuel will no longer be required and the Certified Fuel Handler position is also no longer required.

Minor modification to Technical Specification, Section 2.0, SAFETY LIMITS.

Replace the words "defueled facilities" with "a completely defueled plant". Note: Throughout this document and associated Attachments the term "plant" has been intentionally used to replace the various terms describing the plant, such as, unit and facility. As applied in this document and associated Attachments the term "plant" is used to denote the former nuclear plant and associated buildings, systems, and components used for the production of electric power and does not include the Independent Spent Fuel Storage Installation (ISFSI).

Deletion of Technical Specification, Section 3.0, LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.

Deletion of this Section is proposed since the section does not apply to a completely defueled plant. As stated above, with complete transfer of irradiated fuel to the ISFSI, Spent Fuel Pool Storage LCO's cease to exist.

Deletion of Technical Specification, Section 3.1, DEFUELED SYSTEMS.

Deletion of this Section is proposed since the section only applied during the storage of spent fuel assemblies in the fuel storage pool or during movement of irradiated fuel assemblies in the fuel storage pool. With complete transfer of irradiated fuel to the ISFSI, spent fuel assemblies will no longer be located in the fuel storage pool.

Minor modification to Section 4.1.1 in the first paragraph.

Minor modification to the first paragraph of Section 4.1.1 to better described the location of the plant. The plant is located on Bailey Point and not on any areas surrounding Bailey Point.

Therefore reference to the area surrounding Bailey Point is removed.

Deletion of exclusion area from Technical Specification, Section 4.1.1.

Deletion of the specified minimum distance to the boundary of the exclusion area from Technical Specification Design Features Section 4.1 and relocation of the requirement to the Defueled Page 3 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 Safety Analysis Report. Relocating this design element to the Defueled Safety Analysis Report is consistent with 10 CFR 50.36 regarding the required contents of the design features section of Technical Specification.

I OCFR50.36(c)(4) - states that design features to be included are those features of the facility such as materials of construction and geometric arrangement, which if altered or modified, would have a significant effect on safety and are not covered in categories (c)(l), (2) and (3) of this section.

Maine Yankee Technical Specification Section 4.0 describes the design features of the Maine Yankee plant. The design features of Section 4.1 "Site Description" include a simple description of the site and a specified minimum distance to the Exclusion Area Boundary. As described below, the required distance to the Exclusion Area Boundary is controlled by 10 CFR Part 100 and is demonstrated to be within appropriate regulatory limits by accident analysis. The specification of a minimum distance to the Exclusion Area Boundary does not qualify as a Technical Specification design feature under I OCFR50.36(c)(4) since the distance is already controlled by 10 CFR Part 100 and can not, by regulation, be altered or modified in a manner which would have a significant effect on safety. Therefore, in accordance with 10 CFR 50.36(c)(4), this specification should be relocated to the DSAR.

Deletion of Technical Specification, Section 4.2.

Deletion of Section 4.2 and associated Figure 4.1-1, Spent Fuel Pool Assembly Placement Limitations is being proposed since this section only applied during the storage of irradiated fuel in the fuel storage pool. Fuel storage design features that apply to irradiated fuel stored in dry casks at the ISFSI are contained in the NAC UMS Technical Specification.

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.1, Responsibility.

Maine Yankee is proposing relocating this administrative control (with changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

Page 4 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 The following paragraph is being entered to the Organization Section of the Maine Yankee Ouality Assurance Program in place of the existing Technical Specification Section 5.1.1:

The ISFSI Manager shall be responsible for overall site operation and shall delegate in t'riting the succession of this responsibility during his absence. The ISFSI Manager or his designee shall approve, prior to implementation, each proposed test, experinvzent or modifcation to systems or equipment that are important to safety as defined in 10 CFR 72.3.

The above paragraph is being revised to address site organization after completion of spent fuel transfer to ISFSI. Responsibilities of ISFSI Manager are similar to previous responsibilities assigned to the replaced Plant Manager. The words "that affect the safe storage of irradiated fuel" have been replaced with "that are important to safety as defined in 10 CFR 72.3" since all irradiated fuel will now be stored at the ISFSI governed by Part 72.

The following paragraph is being entered to the Organization Section of the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.1.2:

The ISFSI Shift Lead reports to the ISFSI Manager and is the senior person onsite during backshifts and weekends.

Changes to the above paragraph are being made to address site organization after completion of spent fuel transfer to ISFSI. The Shift Lead responsibilities will change from control room command functions to senior oversight functions, after the transfer of spent fuel to the ISFSI is completed. Control Room command of the controls for rapid response to abnormal or accident situation wvill cease to exist at the plant after the removal of the spent fuel.

Section 5.1.3 has been deleted. ANSI Standard N1 8.1 provides ob titles and organizational structures for organizations operating power reactors. The Standard does not applv to an SFSI facility.

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.2, Organization.

Maine Yankee is proposing relocating this administrative control (with changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

Page 5 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 The following paragraphs are being entered to the Organization Section of the Maine Yankee Qualitv Assurance Program in place of the existing Technical Specification Section 5.2.1:

Site organizations shall be establishedfor the ISFSI operation and support management, respectively. The organizations shall include the positionsfor activities affecting the safe storage of irradiatedfiel.

a.

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and Updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, andjob descriptionsfor keypersonnelpositions, or in equivalentforms of documentation;

b.

The ISFSI Manager shall have control over those onsite activities necessary for maintenance and storage of irradiatediel in a safe condition;

c.

The President shall have corporate responsibility for overall site nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, andproviding technical support to ensure the safe storage of irradiated fiel; and

d.

The individuals who car)y out radiation protection finctions or perform quality assurancefutnctions may report to the appropriate line manager; hovever, these individuals shall have sufficient organizationalfreedoin to ensure their ability to perform their assignedfimnctions.

Changes to the above paragraphs were made to replace "unit organization" with "site organization", "unit operation" with "ISFSI operation", "Plant Manager" with "ISFSI Manager",

and "plant nuclear safety" with "site nuclear safety". These changes focus organization requirements to the irradiated fuel storage area (ISFSI) after completion of fuel transfer. The revised text for paragraph (a) removes reference to the FSAR or QA program since it will be self-evident that the requirements are located in the QA program. Reference to CERTIFIED FUEL HANDLER in paragraph (d) has been deleted. With completion of spent fuel transfer to the ISFSI, the handling of spent fuel will no longer be required and the Certified Fuel Handler position is also no longer required.

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~~~~~~~ATTACHIMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 The following paragraphs are being entered to the Organization Section of the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.2.2:

The ISFSI staff organization shall include the following:

a.

Each on duty shift shall be composed of at least one ISFSI Shift Leadperson. Ally unexpected absence of the on-ditty Shift Lead shall be restored within 2 hotrs. This does not pernit the Shift Leadposition to be unmanned upon shift change dule to an oncoming Shift Lead being late or absent.

b.

Administrative procedures shall be developed and implemented to limit the working hours of the ISFSI staff vho pelfornfimnctions that are important to safety.

Adequate shift coverage shall be maintained wtithout routine heavy use of overtime. The baselinefor determining overtime utse will be a 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week. However, i the event that Unforeseen problems require substantial amounts of overtime to be Used; or during major maintenance or modifications the following guidelines shall be followed on a temporary basis:

1.

All 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 bepermitted to work miore than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hourperiod, 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 of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time;

4.

The uise of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the ISFSI Manager or his designee, in accordance with establishedprocedures and with documentation of the basisforgranting the deviation. Routine deviation from the above guidelines is not authorized.

Changes to the above paragraphs were made to replace "unit staff'with "ISFSI staff', "facility" with "ISFSI", "Plant Manager" with "ISFSI Manager", and "Shift Manager" with "Shift Lead".

These changes focus staff requirements to the irradiated fuel storage area (ISFSI) after Page 7 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 completion of fuel transfer. After completion of irradiated fuel transfer to the ISFSI, the ISFSI staff organization will comprise of at least one ISFSI Shift Lead and paragraph (a) has been revised accordingly. In addition, paragraph (a) allows for an unexpected 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months absence of the Shift Lead. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months absence is acceptable since with all the spent fuel assemblies in ISFSI storage no actions will be required during this period to avoid departure from license conditions or technical specifications. Paragraph (b), (d), and (e) of the Technical Specification have been deleted since with completion of spent fuel transfer to the ISFSI, the handling of spent fuel will no longer be required and the Certified Fuel Handler position is no longer required. In addition, with respect to 10 CFR 50.54x, with all spent fuel assemblies in ISFSI storage no actions will be required that depart from license conditions or technical specifications. Paragraph (c) of the Technical Specification has been revised to require administrative procedures to limit working hours to staff personnel who perform functions important to safety at the ISFSI.

Since the staff for the defueled plant is no longer involved in functions that are safety related, minimum shift crew composition are no longer required in the plant Technical Specifications and therefore table 5.2.2.1 is being deleted.

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.3, Unit Staff Qualifications.

Maine Yankee is proposing to relocate this administrative control (with changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

The following paragraph is being entered to Section 11 of the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.3.1:

Each member of the ISFSI Staff shall meet or exceed the minimium qualifications ofRegldatory Guide 1.8 - September 1975 for comparable positions.

The above paragraph was changed to remove the phrase "unless otherwise noted in the Technical Specifications" since the Technical Specifications will no longer provide the administrative controls for staff qualification requirements. The words "unit staff" has been replaced with "ISFSI staff" since important to safety functions now exist at the ISFSI only.

Page 8 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.4, Training.

Technical Specification, Section 5.4.1 has been deleted since with completion of spent fuel transfer to the ISFSI, the handling of spent fuel will no longer be required and the Certified Fuel Handler training and retraining program is no longer required.

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.5, Procedures.

Maine Yankee is proposing relocating this administrative control (with changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

The following paragraph is being entered to Section V of the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.5.1:

J'ritten procedures shall be established, implemented, and maintained covering thefollowing activities:

a.

The procedures applicable to the safe storage of irradiatedftel recommended in Regulatomy Guide 1.33, Revision 2, Appendix A, February 1978;

b.

Emergency Plan implenentation;

c.

Quality assurance for radiological effluent and environmental monitoring;

d.

Fire Protection Program implementation; and

e.

Radiation Protection, Offsite Dose Calculation Manual, and Radioactive Efflutent Programs.

Technical Specification 5.5.1 (c) "Cold Weather Operations" has been deleted in its entirety since with completion of transfer of irradiated fuel to the ISFSI, the plant no longer contains any safety related systems, structures, or components. Therefore cold weather operation is not required for safe nuclear operation. Spent fuel stored at the ISFSI is stored in sealed canisters with a dry and inert environment and, as such, do not require cold weather operation or Page 9 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 rotection. Replaced subparagraph (f) of the Technical Specifications with new subparagraph (e) ecifically identify the remaining programs subject to written procedures. As stated later in

\\iical Specification 5.6, the Technical Specification (TS) Bases Control Program has been id since with the complete removal of spent fuel assemblies from the spent fuel pool the i,11 no longer contain any LCO's associated with the plant, therefore statements of bases Aical Specification LCO's will not be required. The Spent Fuel Pool Water Chemistry s been deleted since irradiated fuel will no longer be stored in the Fuel Storage Pool.

In additiu..2he Inservice Testing Program also has been deleted in its entirety since the plant no longer will contain any safety related ASME Code Class, 2, or 3 components, including any associated supports. Therefore written procedures associated with these programs are no longer required and are not included in the above paragraph (e).

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.6, Programs and Manuals.

Maine Yankee is proposing relocating this administrative control (with changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

The following paragraph is being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.6.1:

Radiation Protection Program:

Procedures for personnel radiation protection shall be prepared consistent tith the requirements of IO CFR 20 and shall be approved, maintained and adhered tofor all operations involving personnel radiation exposure.

There are no changes proposed to the above paragraph from Technical Specification 5.6.1.

The following paragraph is being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.6.2:

Offsite Dose Calculation Manual (ODCM):

a.

The ODCM shall contain the methodology and parameters Used in the calculation of off-site doses resultingfrom radioactive gaseous and liquid effluents, in the calculation of Page 10 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 gaseous azid liquid ejfluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and b

The ODCM shall also contain the radioactive effluent controls and the radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the ODCM.

Licensee initiated changes to the ODCM:

a.

Shlall be docutmetted and records of reviets performed shall be retained. This documentation shall contain:

1.

Sidicient information to support the change(s) together with the appropriate analyses or evaluations justilying the change(s);

2.

A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, and 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b.

Shall become effective after approval by the ISFSI Manager or designee; and

c.

Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affectedpages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change tas implemented.

The above paragraph (b) under ODCM was changed to replace the reference to Specification 5.7.2 and Specification 5.7.3 with reference to ODCM instead since Specification Sections 5.7.2 and 5.7.3 will be deleted. Under the heading "Licensing initiated changes to the ODCM",

changed subparagraph (b) from "Plant Manager" to "ISFSI Manager" since the Plant Manager position will cease to exist and approval of the ODCM will be assigned to the ISFSI Manager.

The MY ISFSI does not create any radioactive effluents or have any radioactive waste treatment systems. Therefore, specific operating procedures for control of radioactive effluents in accordance with 10 CFR 72.44(d) are not required. NAC-UMS Technical Specification, Section A.3.1.5 CANISTER Helium Leak Rate, provides assurance that there are essentially no Page 11 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 measurable radioactive effluents from the ISFSI. As such, an ODCM and environmental monitoring program for the ISFSI are not required.

The following paragraph is being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.6.3:

Radioactive Effluent Controls Program:

This program conforms to 10 CFR 50.36a for the control of radioactive effluents andfor maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The progran shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include thefollowing elements:

a.

Limitations on the finctional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations ofradioactive material released in liquid effluents to Unrestricted areas, conforming to I0 times the concentration values in IO CR 20, Appendix B; Table 2, Column 2;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with J0 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents releasedfrom the plant to Unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of ctunlative dose contributionsfr-om radioactive effluentsfor the current calendar quarter and current calendaryear in accordance with the methodology and parameters in the ODCM at least every 31 days; f

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the estimated doses in a period of3I days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix l, Page 12 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 g

Limitations on the dose rate resltingfi-om radioactive material released in gaseous etluents to areas beyond the site boundaty shall be limited to the following:

(1)

For noble gases: Less than or equal to dose rate of 5OO mrems/yr to the total body and less than or equal to a dose rate of3 000 mrems/yr to the skin, and (2)

For Iodine-131, Iodine-133, tritium and all radionuclides in particulateform with haylives greater than 8 days: Less than or equal to a dose rate of 1500 mrems/yr to any organ.

h.

Limitations on the annual and quarterly air doses resultingfrom noble gases released in gaseous effluentsfi-om the plant to areas beyond the site boundaty, conforming to 10 CFR 50, Appendix I;

i.

Limitations ont the annual and quarterly doses to a member of the public from tritium and radionuclides in particulate form w ith half-lives greater than 8 days in gaseous effluents releasedfrom the plant to areas beyond the site boundaly, conforming to 10 CFR SO, Appendix I; and

j.

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

The only change proposed to the above paragraph from Technical Specification, Section 5.6.3 is to replace the term "unit" in paragraphs (d), (h), and (i) with "plant" to provide consistency in use of terms as described in Section 2.0 of this Attachment.

The MY ISFSI does not create any radioactive effluents or have any radioactive waste treatment systems. Therefore, specific operating procedures for control of radioactive effluents in accordance with 10 CFR 72.44(d) are not required. NAC-UMS Technical Specification, Section A.3. 1.5 CANISTER Helium Leak Rate, provides assurance that there are essentially no measurable radioactive effluents from the ISFSI. As such, a Radioactive Effluent Controls Program for the ISFSI is not required.

Section 5.6.4. Technical Specifications (TS) Bases Control Program, has been deleted in its entirety since with the removal of spent fuel assemblies from the spent fuel pool the plant will no longger contain any LCO's and therefore statements of bases for Technical Specification LCO's will no longer be required.

Section 5.6.5. Spent Fuel Pool Water Chemistry Program, has been deleted in its entirety since irradiated fuel is no longer in the Fuel Storage Pool.

Page 13 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 Section 5.6.6. Inservice Testing Program, has been deleted in its entirety since with completion of transfer of irradiated fuel to the ISFSI, the plant no longer contains any safety related ASME Code Class 1.2. or 3 components, including associated supports.

Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.7, Reporting Requirements.

Maine Yankee is proposing relocating this administrative control (without changes) to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

The following paragraph is being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.7.1:

Occupational Radiation Exposure Report:

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors% for whom monitoring was performed, receiving an annual deep dose equivalent >

100 mrem/yr and the associated collective deep dose equivalent (reported in person-rem) according to work andjobfunctions (eg., fuel handling, surveillance, routine maintenance, special maintenance [describe maintenance] and waste processing). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various dltyfunctions may be estimated based on pocket dosimeter, thermoltminescent dosimeter (TLD) orfln badge measurements. Small exposures totaling < 20% of the individual total dose need not be accountedfor. In the aggregate, at least 80% of the total deep dose equivalent receivedfrom external sources should be assigned to specific major vorkfinctions. The report shall be submitted by April 30 of each year.

There are no changes proposed to the above paragraph from Section 5.7.1.

The following paragraphs are being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.7.2:

Annual Radiological Environmental Operating Report:

The Annual Radiological Environmental Operating Report covering the plant activities during the previous calendar year shall be submitted by May 15 of each yeas-The report shallinclude Page 14 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 summaries, interpretations, and analyses of trends 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 Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I Sections IV.B.2, IV.B.3, and IVi C The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursutant to the locations specified in the table andfigures in the ODCM as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion twith the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementaiy report as soon as possible.

The only change proposed to the above paragraph from Technical Specification, Section 5.7.2 is to replace the term "unit" in the first paragraph with "plant" to provide consistency in use of terms as described in Section 2.0 of this Attachment.

NAC-UMS Technical Specification, Section A.3.1.5 CANISTER Helium Leak Rate, provides assurance that there are essentially no measurable radioactive effluents from the ISFSI. As such, a Radiological Environmental Operating Report is not required for the ISFSI.

The following paragraph is being entered to the Maine Yankee Quality Assurance Program in place of the existing Technical Specification Section 5.7.3:

Radioactive Effluent Release Report:

The Radioactive Efflutent Release Report covering the activities of the plant in the previols year shall be submittedprior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste releasedfrom the plant. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance -with 10 CFR 50.36a and J0 CFR Part 50, Appendix I,Section IV.B. 1.

The only change proposed to the above paragraph from Technical Specification, Section 5.7.3 is to replace the terms "unit" in the paragraph with "plant" to provide consistency in use of terms as described in Section 2.0 of this Attachment.

NAC-UMS Technical Specification, Section A.3.1.5 CANISTER Helium Leak Rate, provides assurance that there are essentially no measurable radioactive effluents from the ISFSI. As such, an annual report of liquid or gaseous releases from the ISFSI is not required.

Page 15 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 Deletion of Technical Specification, ADMINISTRATIVE CONTROLS, Sections 5.8, High Radiation Area.

Maine Yankee is proposing relocating this administrative control to the Maine Yankee Quality Assurance Program.

Relocating organizational responsibilities from the technical specifications to the Quality Assurance Program is consistent with the criteria contained in 10 CFR 50.36 and the guidance in NRC Administrative Letter 95-06.

The following paragraphs are being entered to the Maine Yankee Oualitv Assurance Program in place of the existing Technical Specification Section 5.8.1. 5.8.2. and 5.8.3:

High Radiation Area:

Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mr-em/hr but < 1000 mrem1hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (R IP,). Idividuals qtalified in radiation protection procedures or personnel coniituioursly escorted by such individuals may be exemptfrom the R JWP issuance requirement during the performance of their assigned ditties in high radiation areas with exposure rates < 1000 mrem/h; provided they are othervise following plant radiation protection procedures for ent),

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 that continuously indicates te radiation dose rate in the area.

b.

A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c.

An individual qualifled in radiation protection procedures with a radiation dose rate monitoring device, who is responsiblefor providingpositive control over the activities Page 16 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 within the area and shallperform periodic radiation surveillance at the frequency specified by Radiation Protection in the R WP.

In addition to the above requirements, each high radiation area, as defined in 10CFR 20, with radiation levels > 1000 niren/lr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained uander the administrative control of the Shift Lead on duty or radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved R VP that shall specify the dose rate levels in the immediate work areas and the naximtm allowable stay times for individuals in those areas. n liet of the stay time specification of the R JWP, direct or remote stch 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, as defined in 10 CRR 20, with radiation levels of > 1000 mrem/lr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constncted around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

The only change proposed is to replace the term "Shift Manager" in third paragraph with "Shift Lead. With spent fuel removed from the plant, the ISFSI Shift Lead or radiation protection supervisor will now be responsible for providing administrative control of any keys to high radiation areas. There are no additional changes proposed to the above paragraphs from Technical Specifications Sections 5.8.1, 5.8.2, and 5.8.3.

Deletion of Technical Specification, Bases Section.

The current Technical Specification Bases provides bases or reasons for current Limiting Conditions for Operations (LCO's). The proposed Technical Specifications after spent fuel transfer to the SFSI will no longer contain any LCO's associated with the plant, therefore statements of bases for Technical Specification LCO's will not be required.

Page 17 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 SIGNIFICANT HAZARDS CONSIDERATION Maine Yankee has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed License changes delete License information that does not apply to a plant that has permanently ceased operation. These changes are in compliance with 10 CFR Part 50 regulations and are not associated with the probability or consequences of accidents previously evaluated.

The proposed Technical Specification changes reflect the complete transfer of all spent nuclear fuel from the Spent Fuel Pool (SFP) to the Independent Spent Fuel Storage Installation (ISFSI).

Design basis accidents related to the Spent Fuel Pool are discussed in the MY Defueled Safety Analysis Report (DSAR). These postulated accidents are predicated on spent nuclear fuel being stored in the Spent Fuel Pool. With the removal of the spent fuel from the Spent Fuel Pool, there are no remaining safety related systems required to be monitored and there are no remaining credible design basis accidents related to the SFP.

The proposed relocation of the specified minimum distance to the Exclusion Area Boundary from the Technical Specification to the DSAR has no impact on the probability or consequences of the remaining applicable design basis accidents.

The proposed changes do not affect design functions of structures, systems or components (SSC's) associated with the safe storage of fuel or radioactive material. Nor do any of these changes increase the likelihood of the malfunction of an SSC. The proposed changes do not affect operating procedures or administrative controls that have the function of preventing or mitigating any design basis accidents.

The MY DSAR provides a discussion of radiological events postulated to occur as a result of decommissioning with the bounding consequence resulting from a materials handling event. The proposed changes do not have an adverse impact on decommissioning activities or any of their postulated consequences.

Page 18 of 21

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 In addition, the proposed Technical Specification changes are consistent with the guidance provided in NRC Administrative Letter 95-06. Therefore, these proposed changes do not involve a significant increase in the probability or consequences of any accident previously evaluated.

2.

Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed License changes delete License information that does not apply to a plant that has permanently ceased operation. These changes are in compliance with 10 CFR Part 50 regulations and are not associated with any accidents previously evaluated.

These proposed Technical Specification changes relocate requirements from the Technical Specifications to the Defueled Safety Analysis Report, eliminate Technical Specifications associated with the storage of spent fuel in the SFP, and relocate Technical Administrative Controls to the MY Quality Assurance Program. With the complete removal of spent fuel assemblies from the plant there are no safety related SSC's that remain at the plant. Thus, these proposed changes will not have any affect on the operation or design function of safety related SSC's. These changes do not create new component failure mechanisms, malfunctions or accident initiators. Therefore, these proposed changes would not create the possibility of a new or different kind of accident from any accident previously evaluated.

3.

Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed License changes delete License information that does not apply to a plant that has permanently ceased operation. These changes are in compliance with 10 CFR Part 50 regulations and do not involve a reduction in a margin of safety.

The design basis and accident assumptions within the MY DSAR and the Defueled Technical Specifications relating to spent fuel are no longer applicable. The proposed Technical Specification changes do not affect remaining plant operations, systems, or components supporting decommissioning activities. In addition, the proposed changes do not result in a change in initial conditions, system response time, or in any other parameter affecting the course of a decommissioning activity accident analysis.

Page 19 of 21

I -

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 The relocation of the specified minimum distance to the Exclusion Area Boundary from the Technical Specifications to the Defueled Safety Analysis Report is consistent with the criterion set forth in 10 CFR 50.36 (c)(4). This criterion states that design features to be included in the Technical Specifications are those features of the facility such as materials of construction and geometric arrangement, which if altered or modified, would have a significant effect on safety and are not covered in other Technical Specification categories. The minimum distance to the Exclusion Area Boundary is established to maintain compliance within the limits specified in 10 CFR Part 100. The relocation of the specified minimum distance to the Exclusion Area Boundary to the DSAR continues to provide the safety analysis controls to-assure compliance with 10 CFR Part 100 regulation.

Therefore, the proposed changes will not involve a significant reduction in the margin of safety.

Based on the above, Maine Yankee concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

ENVIRONMENTAL CONSIDERATION This amendment request meets the criteria specified in 0 CFR 51.22(c)(9) for categorical exclusion or otherwise not requiring environmental review. Specific criteria contained in this section of the regulations are discussed below:

1.

The above amendment involves no significant hazards consideration. As demonstrated above, this requested amendment does not involve any significant hazards considerations.

2.

There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The amendment removes operational and administrative requirements for systems that are no longer functionally required to support the safe storage of spent nuclear fuel within the Spent Fuel Pool. In addition, Technical Specification administrative controls are being relocated to the Quality Assurance Program. These changes are administrative in Page 20 of 2l

ATTACHMENT I DESCRIPTION AND EVALUATION OF CHANGES PROPOSED CHANGE NO. 217 nature and do not affect any systems such that there may be an increase or change in type of effluents discharged offsite.

3.

The elimination of non-applicable operational and administrative requirements from the Technical Specifications will not result in a significant increase in individual or cumulative occupational radiation exposure.

Based on the foregoing, it is concluded that the proposed amendment meets the criteria for categorical exclusion set forth in 10 CFR 51.22 (c)(9) and therefore, no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

Page21 of 21

ATTACHMENT II PROPOSED CHANGE PAGES TO LICENSE 2.B.(7)

This amended license is subject to the following conditions for protection of the environment:

(a)

Deleted.

(b)

Deleted.

2.B.(8)

This amended licnco is offoctivo a of tho dato of isuanco and hall expire at midnight October 21, 2008.

2.B.(9)

Lands Released from the Jurisdiction of Facility Operating License No. DPR-36 The lands described in the following correspondence have been released from the jurisdiction of Facility Operating License No. DPR-36. The NRC may require additional surveys and/or decontamination only if, based upon new information, it determines that the criteria of 10 CFR Part 20, Subpart E were not met and residual activity remaining at the site could result in a significant threat to public health and safety.

(a)

MYAPC Letter to USNRC dated August 16, 2001 Early Release of Backlands, Proposed Change No. 211 as supplemented and as approved in Amendment No. 167.

2.B.(10)

License Termination (i)

The Maine Yankee License Termination Plan describes an acceptable approach for demonstrating compliance with the radiological criteria for unrestricted use, as defined by 10 CFR 20.1402, by meeting a site release criteria of 10 millirem TEDE per year over background (all pathways) and 4 millirem (as distinguishably from background) TEDE per year for groundwater sources of drinking water using appropriate dose modeling methods, pathways and parameters and acceptable final radiation survey methods.

The licensee shall implement and maintain in effect all the provisions of the approved License Termination Plan submitted on August 13, 2001, as supplemented and as approved in the SER dated February 28, 2003, subject to and as amended under the following stipulations:

The licensee may make changes to the License Termination Plan without prior approval, provided the proposed changes do not:

(a)

Require Commission approval pursuant to 10 CFR 50.59; (b)

Violate the requirements of 10 CFR 50.82(a)(6);

(c)

Reduce the coverage requirements for scan measurements; AM.14 (2)

IPursuant to the Act and 10 CFR Part 70, to receive, 11.13.75 possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as supplemented and amended.

AM.14 (3)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to 11.13.75 receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required.

AM.14 (4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to 11.13.75 receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration, or associated with radioactive apparatus or components.

AM.14 (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to 11.13.75 possess, but not separate, such byproduct and special nuclear material as may be produced by the operation of the facility.

AM.14 (6)

This amended license shall be deemed to contain and is 11.13.75 subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Parts 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 below:

AM.1 13 (a)

Maximum Power Level 07.10.89 The liccnsec is authorized to operate the facility at steady state reactor core power 1c'.'lz nt in excess of 2700 megawatts thermal.

AM. 164 (b)

Technical Specifications 05.05.99 AM. 169 The Technical Specifications contained in Appendix A, as revised through 1 07.27.03 Amendment 169, are hereby incorporated in the license. The licensee will maintain the facility in accordance with the Technical Specifications.

(c)

Deleted.

ISSUED DATE:

Amendment No. 156, +64 +6-, +66, +0, 169 S:\\license\\tspage3

ATTACHMENT III PROPOSED CHANGE PAGES TO TECHNICAL SPECIFICATIONS

Technical Specifications Technical Specifications Maine Yankee Nuclear Plant Specifications

TABLE OF CONTENTS SPECIFICATIONS TABLE OF CONTENTS 1.0 USE AND APPLICATION.....................................................................

1-1 1.1 Defintc ios

4.

42 1.3 Completion Times............................................ 4-4 1.4 Freuency 2.0 SAFETY LIMITS............

........................................ 2-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY....

......... 3-1 EQIE2.

e LEFUELED SYSTEMS 3..1 Fue Storage P Watr Level...................................

3 3.1.2 Fuel Storage P Boron Concentraion 4

4.0 DESIGN FEATURES.................................................

4-1 I

I I

4.1 Site.........................................................

4-1 5.0 ADMINISTRATIVE CONTROLS.5-1 5.1 Responsibility................................................54 5.2 0I ganzation

.5-2 5.3 Un

'tF Qualifications~.....................

5-6 5.4 Tia.iinj..

5.5 Piocedues................................................... z

_~Ju 58 5.6 Programs and Manuals.........................................59 5.7 Repoing* Requiireets

................... 6 5.0 iIo gh Radiation A, ea......................

547 Maine Yankee i

Amendment +61

Defonotons I

I I

1.0 USE AND APPLICATION This section Is not applicable to a completely detueled plant.

1.1 efihons The defined terms of tIs section ap ricpitalized type and a, e applicable Terml Definition ACTIONS ACTIONS shal be that par of a Specficato that prescribes Required Actions to be taken undei designated Gndition~s within specified Completon T.imes.

GERTIFIED FUEL I IANDLER A CRTIFIED FUEL I IANDLER is an nd'vicdual who comrpls r

ins of the CERTIIED FUEL hANDLER tganinq picoram requred by Techical Specification 5.4.1.

Maine Yankee I -I Amendment +61

I 1

onnectors 2

l 1.0 UE AND APPLICATIN 1.2 Logical Connectors PURPOSE Th~e purpose of this section. s to explai t~e mean;n-of lcalors.

Logcal connectors ae used rn Technrical Specifications (TS) to disc ImInIa.~t between, and yet conn.ect, discrete Conditions, Requh ed Actons, Co 1 plet.o i Times, Surveilances, and FRequencies Te ol ogical connectors3 that mayapea i TS a, e AND and OMR-The physical arrangemn o

!hse connectors constitutes ogical cnvenftons wth specific me s

BACI(GROUND Several levels of logic may be used to state Required Actoons. These levels are dentifed by the placenment (o nesting) of the logical connectors and byF the numbe-r as~ed to each Reqjuhed Action. The first eve' of logic dtfed by t~e f ast digt of the number assigned to-a Requred Action and the placement of the logical conn, ectos in the fst eve' of nesting (.e., left justified with the nmbe, of the Required A-ction). The successive evels of logic ar e identef.e b dtonal digits of the Required Action number and by iucssendentations of the lgial conectors.

If logical connectors9 a, e used to state a Conditon, Completior Thme, Surveillance, or Frequency, only the frst level of logc s used, and the logical connector left justified with the statement of the Condition, Gompletion Time, Surveillance, or Rrequency.

(Con.[ined)

Maine Yankee I1-2 Amendment +6I I

Logical Connectors 1.2 Lci:

Connectors (contnued)

_v

^ "^.

T L _ r _ l l _

Lfjuk1vlLt_

I he ollowin examples illusrate te use of ogical connct(MS.

E1%JA AM A

^

A I

n r

I I

CONDITION REQUIRED ACTIOtN COMPLEIOH-TIME A. LCO not met.

A.!VerIHy...

AND A.2 Restore...

.L L

_s__

A kl J

J.

__s_

sLs ss

WzV J

A _A-_ _

rlf JA M3FI r A

A7l*

I LL I

ACTIONS GONDIfION REQUIREDATION COMPLETION TIME A. LO not met.

A. Tip OR A 21Ve AN A.2.2 Rute...

I 11110 CAUISIjD I ~jJIl9QUIILQ Q IIIIJI U~

I~JI~L.

UQU WI IMjuI.,Cl connectors. Reiuied Actios A.1, aiidA.2 are alteinjatve choices-I only on~e of which must be performed as indcated by the use of the Iogical coniector OR an~d the left justified placement. Ethei of the Actions may be chosen IfA.

chosen, then both A.2.1-and-A A.2.

-- ;to IasmFeA AND-a Iv tI-Ia u

v avylD

-1 Maine Yankee I1-3 Amendment +6-1G

Completion Times 1.3 1.0 USE AND APPLIGATIGN 1.3 6oipletoon Tanes PURPOSE The purpose of this section is to establish the Completion Tome convention and to provide guidance for its use.

BAC(GROUND Limiting Conditions for Operation (LCO's) specify mininium reunmei ts for ensuring the safe stoi age of !iadiate d fuel.

The ATIONS associated wit's an LCO state Condtfons that typically describe the ways in which the quiemenits of the LCO can fail to be..met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed-for completing a Required Actio. Iti eeenced to the ine ofl discovery of a situation (e.g., va iable not within 'emits) that reurs entering an ACTIONS Condition unless otherwase spcfed. Requi~ed Actions mnust be completed prio, to He exphration of th~e specified Completion Time,.

An. AGTlON Condition emains n effect and the Required Actions apply until the Condition no onge eitor the facility is not within the 1LC0 Applicability.

EXAMPLES The following examples illustr ate the use of Completion Times with differ ent types of Conditions.

.£

..conte.uedr Maine Yankee 14 Amendment +6+1 I

CnnImplin Toimes-4 1.3 Cmpleion.Thnes-EXAMPILES EXAMPLE 1.3-1

-(continuted)

ACTtGNS CONDITION REQUIRED ACTION GOMPLETION IME A-Requ ed A

Vefy 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s-oeaated AND Competon Tome n~ot met. A.2 Resto e...

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (3ondtion A has two Required Actions. Each Requied Action hac its own1 separate Gom letbon Tome. Ech 6ompletion Tom refer en ced to t e tme that Conditior.i A s e, te, ed.

rov

~

~ ~ ~

r^

-IA The Required Actions Of ConCdtion A ase to peomn tie veficatIo requ ed by

~wiNl wthinrhousANDtoperfom 6the restor at~on reurd yATION A.2 wthin 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A totat-of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is elkoe fr perfoiniing ACTION A.! and a total ol 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months s (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for perfo ming ACTION A.2 f om.

the time that Conditon A was entered. f ACTION A.! is completed thin 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months s, the tme a e

competin ACTION A.2 is the net 33 hourauet total allowed foI complet ing ACTION A.2 is 36 hows.

_^

i-J

. ^ _*s a^

.oe emcoa

e.

I Maine Yankee 1-5 Amendment +6II I

Completion Hines 1.3 1.3 ComplItaon Tlme~s (contnued)

ACTIONS CONDIffGN REQUIRED ACTION COMPLETION-TIME A.

LeO Ini*

A.! Verify--...

1 hui exceeded.

AND 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s thereafter

~AND

-72 hours Required Actfion A.1 as to Completon Tomes. Te 1 _hoi Ccompletion Tom1 e begins at the tne the Condtion s entered and each "8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereaftcr" terval begins upon pefomance ot Requi'ed Action A.!. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months compet te

f. Requhed Ac~on A.2 also begins at the te the (3odition s entered an~d runs concurrentfl.

IMMEDIATE When. "Ingne1 dately" s used as a Com 1 pletion Thne 1, tec GOMPLETION Reqursed Action shouId be pur sued without delay and i a TIM1 E ccntrclled m.ann1 e.

Maine Yankee I1-6 Amendment -- 1

I -quncrIy 1.4 1.0 USE AD APPLICATION 1.4 Frequency PURPOSE Thec pur.pose of this section s to defin1e te pirope ue an d application of Ruequency equirements.

DESGRIPfIGN Each1 Surve"ance Requrem 1 ent (R) h~as a specifed FRequency in which the Surveillance mustb e

orde to meet t e associated LCO. A un der stan ding of the correct application oF the specified Freunc snecessary Fo.

comipliance with. the SR.

Th~e "specified Frrequency" s efen ed o t, ough~out tis section and each of the Specfications of Section 3.0, Surveillance RequhreFMnT (ZVVR) Applicabity. The "specifiJ Frequency" consists of the requirements of the F, equency columin of each SR as well as certain Notes n the Surveallance column thatnmodify perornance equirements.

EXAMPLES T!iec Following examples illustr ate the maoswys that Frequenie-ae pecified. II these examples, the Applicablty of the LCO (LCO ot shown) s when inradiated fuel s stoi ed n the spent fel pool.

(confinue Maine Yankee 1 -7 Amendment 16-1I I

rrequency 1.4 1.4 FReZuencv r'

A knr~r

-C-r lAv RarI

.4 4 4

-(continued)

SURV'EILLANE REQUIREMENTS SURVEI sAN1E FREQUENY Verify pa rnete, s within :;mits.

42-hours Il inma nMal-v*

rI-

--.- -1 I- -

the-Technical specitications (T). he irequency speciies an inter-val (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) du, ng which the associated Surveillance must be perfor med at east on~e tme.

erforman~ce of the Surveillance intfiates the subsequent interval. Although the Frequency s stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the tme nterva to 1.25 times the stated FRequency is allowed by SIR 3.0.2 for operational flexibility.

Themnieasuiesent off' e

contnues at all tmes, even when the SR s not requed to be met per SR 3.0.1 (such as when a vvkg k

~t n ffi;tf

__:t;fit Iimif_

r tI-.A fk:1!t.

t*

0 lIdA I.

_t__ I :..

_£.--

lt

-L

__.l_

_t..

N iPPulCaolILiY 0? Lhe t~wp~ne inera specified by SRi 3..2 exceded whle he facility is isn the s.pecified condition n the Annior-bilitv of t! e LOG Mid NMhe foinkance of the Survellance s r

r Z

not othe, wise mo1CIitaezl, then bi U.U.6 beCOmleS appolaai;e.

.t (contwnue.

Maine Yankee 1 -8 Amendment +61 I

e I I I requency 1.4 1.4 Rrecuene.v EXAMPEEX-MPE I4A2

-(contnued)

SURVEILLANCE-REQUIREMENTS SURVEILLANCE FREQUENeY Ver ify paraneter s wit' dri limits.

Withii 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to mlov~lng irradilated fuel AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-ls orreqe*cies. The fir st s a oe t 1 e Perfor mance Fsrequency, an~d the second s of the type shown i Example 1.4-1. The loical connector "AND" ndicates that both Fr equency reueets must be mnet. The ef"pirto" ndicates that uvilance must be performed onice before the iniflatoon of fuel handling ac'IVtiLes. This type of Frequency does not indicates future perforsances must be established lie, SR 3.0.2, but only after a specified coriitio.i s first met (i.e., the "p ior to" performiance in this exanES te).

Maine Yankee 1 9 Amendment +61I I

SLs 2.0 2.0 SAFETY LIMITS (SLs)

This section is not applicable to a completely defueled plant.

I Maine Yankee 2-1 Amendment 161

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY This section s not appicable to a completely defueled plant.

Lee 3.0.1 LO's shall be met durin the specifed conitons i the Applicability, except as provided i LCO0 3.0.2.

LCO 3.0.2 Upon discovery of a failur to meet an LCO, the Required Actons of the assocated Condos shall be met.

If the LCO is niet o is no lngeF applicable pror to expration oF te specifed Completion Time(s), completion of the Required Action(s) is not requred unless otherwise stated.

Maine Yankee 3-1 Amendment +6-F

bippliabil 3.0 SR 3.0.1 SRs shall be met during specfied nditions n the Applicability fot individual LCO's, unless otherwise stated 'i the SR. Failure to meet a Survellance, whether such failur isprienced dus ng ' he pefformnance of the Su.rve"Iance o. bewe ieformances of the Surveillance, shall be failu e to meet the LCO).

ailure to perform Surveffance within the specified Frequency shall be failure to meet.

the LGO except as provided n SR 3.0.3. Sur veillances do not have to be performi ed o i nosperable euipment or va, ables outside specified SR 3.0.2 The specified FRequency for each SR is met if the Surveei-is-.

perfor med Within 1.25 fines the nterval specified' n tIe -rFqency, as measured from the peoserformance or as sneasur ed f om the tne a specfe odio fte F

uency isinet.

SR 3.0.3 If t s discover ed h at a Surveillance was not performed within its specfied FRequency, then compliance with the equiesnent to declare the ICO not met may be delayed, fo m the tme of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the ltit of the specified Frequency, whichever, is lss. This delay pe, od is per mitted to allow performance of the Surveillance.

i t~e Surveillance s not perform 1 ed witin t~e delay period, the LO must mmediately be declared not met, and the applicable Conditon(s) must be entered. The Completion Times of the Requised Actions bei immediately upon expiration of the dela.y peiod.

WheZ. tec Surveillance s performed within t~e delay period and tec Survefflance is notimet, the LO must mmniediately be declared not met, and he applicable Conditon(s) must be entered. Te.,

Completion Tomes of he Required Actions begin imediately upon.

falure to meet the Suvelance.

Maine Yankee 3-2 Amendment +6-1 I

I U storage P-ool ater-tevel 3.1.1 3.1.1 Fuel Storage Pool Water Level Lee 3.1.1 The fuel storage pool water level s~aII be > 21 ft over the top of iradiated fue assembiess eated i APPLIGBILIT-.

D i

ent ofonadiaed fue assemblies *n the fuel storage A68N GONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel Stoage pool water A.1 Suspend movement of iniediately level not within lt.rradeated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS_

SURVEILLANCE FREQUEN'Y SR 3.1.1.1 Vify the fuel storage pool wate, level is > 21 ft above the 24-hours top of irradiated fuel assemblies a

he storage Maine Yankee 3-3 Amendment 161

Fuel 'toorage Pool Boron C oncentration 3.1.2 3.1 DEFUELED SYSTEMS 3.1.2 uel Storage Pool Bos on Gonct aton LCO 3.1.2 TI se fuel sto age poo bor on i oientration shll be

> 1000 ppm.

APPLCABlUTY:

WAhen fuel assembHes a, e stored an the fuel stoi age pool a~d a fuel storage pool verification has not bee performed sne the last movement of fuel assmbles in the fuel storage po AGTBONS CONDITION REQUIRED ATION COMPLETION THIE A.

Fuel storage pool boro A-Suspend movement of fuel Immediately conceiton ot assemblies 'n-the fuel withimit.

stoage pooh AND A.2.l liteate acton to estore ful ninmedoately storage pool bo, c crncenjtiatoon to wthn "mit.

-OR A.2.2 litoateactioto perftiona hnnediatel fuel sto age pjool veifflcatoon.

(Continuted)

I

/

Maine Yankee 3-4 Amendment +6

Fuel Storaije rl Bron Con~centfaton 1

3.1.2 I

SURVEILLANCE REQUIEMENTS SURVEILLANE FREQUEN SR 3.1.2.1 Ve~ify the feI sto, age pool boron. concen~tratio i Piior to movenment wethin imitz of fue' fnot performed wthi the past 7-days-AN4D

7 days thereafter

_I Maine Yankee 3-5 Amendment 16+

I

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site Description The plant shall be located on property owned by Maine Yankee Atomic Power Company on and uidunding Bailey Point in the Town of Wiscasset, Lincoln County, Maine.

The inimm dostance t the bounidary of the exclusion area, as defined I 4OFR4*h3 sall-be 2000eet.

I I

I Maine Yankee 4-1 Amendment +-6--

I

Design Features 4.0 4.0 DSIG FATURES 049 Fuel Stoage stored.n the fuel storage pool.

4.2.1.1 The spent fuel storage racks are designed anid sisall be maintained with:

A-H r-Wvvighlt pe cs.t,

....0

b.

ke~ < 0.95 if fully flooded with unborated water, which includes an allow Ic foun.cetanties as desc. obed 1. i H e FSAR Aominal 9.085 ich cente, to cente. distace between fuelr assemblies placed n Region II acks;n

d.

A nominal 10.5 nch center to cente. distance between fuel assemblies placed in Region I racks; 4.2.2 Drainage The fuel storage pool s designed and shall be maintained to prevent vnadvertent di ainng of the pooi below elevation 40 ft.

4.2.3 Vqpifh..

a.

No nor tan 2019 fuel assembles shall be stored n the fuel stor age pool. These assemiblies wll be stor ed ;ni eith er Reg"n I o Region II of the fuel storage pool i accor dan ce with the liitations of Figure 4.1-1. Uninadiated fuel assemblies shall be stored n either the New Fuel Storage Area or Region of the fuel storage pool. Consolidated fuel shall be stored Oi Region II only.

r-

tr

T11 tr InrI tuBal

m?I la mr lplt*?l b*...fl

... 3 form. These are inluded in toe 2019 fuel assernbes specfieton-

-Of Maine Yank;ee 4-2 Amendment i

, 16 6 I

40 35 D

530 0

a25 E

a) 20 0)

< 15 E

,, 10 5

0

. 1 2

3 4

5 Nominal Initial Enrichment (235 U Weight Percent)

Spent Fuel Pool Assembly Placement Limitations Figurm 4%1i (DELETED)

I I

Maine Yankee 4-3 Amendment 16-1, 166 i

is

-~

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS Appropriate administratlve controls are located In tho Maine Yankee Quality Assurance Program.

I I

I

5.

Rspnsbii S.1.

The Piant Manages shall be responsible for overall unit operation and shall delegate n wrtng the succession to this esponsibilty duting hs Thei Plan1 t Manage o his desinee shaIl aprvpior to im.plem.enaion, each proposed test, expe iment or modefica~o tsytems o euipment that affedtthe safe storage of iradiated fuel.

5.1.2 The Shift Manage, on-site shall' be responsible for the comnnand fnction.

5.1.3 Unless otherwise defined, the technica specification titles for mebers of the staff ar e

ctitles as provided n Regulatory Guide 1.0 5 arndlor AN~

I 1971.

lant-specific, Maine Yankee ttles for the functions and responsibilities associated with these generic titles ar.

1denfedin the FSAR-andlor QA progran-.

Maine Yankee 5-1 Amendment +6-

~~

~5.2 5.0.A ENIU.TR1ATIVE GONTRGLS 5.2 Or c 3Ha On 5.2.1 GenieralOrcianizaflonal Reureet Unit organizations shl~al be established for t~e uint opeiation ai id support management, respectively. The oiganizations shal: nclude the positions for activties affecting the safe torage of 2rradiated fuel.

a.

Lines of auth~ority, esponsiblity, anCd coIImmmi.c.tion sall-be defined and established throughout highest managem ent levels, intennedoate evels, and a": operating oiganization positions. These relationships shall be documented and updated, as appropriate, n organization charts, functional descrptions of departmental responsillIt~es and elati nships, and job desc iptions for key personnel positions, rin e.uvaent forms of documentation.

These equ~irements shall bedcmnted n the FSAR or QA plogr-amll

b.

Thec Plant Manager sh~all have overall eponsiblit, for t~e ui~mt an*d shall have control over those onsite acttles necessaryfor maintenance and storage of irradiated fuel in a safe condition, C. The Presiden1 t sIhall have corporate responsibilit f, oveall plant nuclear safety and sha!l take any nkeasures needed to ensure acceptable performance of the staff in operating, maintai ng, and Providing technical suppo. to en sure the safe storage of radiated fueland

d.

Thec ndivduaL wh trai te~ CERTR~ED FUEL m JANDLERS, carr out adiation pirotection functions, or perfor m quality assurance functions may report to the appropriate line manager, however, these ndovduals shall have sufficient or ganizational f eedom to ensure theh ability to performn the asg fctons.

Maine Yankee 5-2 Maine Yankee 5-2 ~~~~~Amendment 1-6+/-

UCrganization 5.2 5.2 Orcianization (contred) 5.2.2 Unit Staff The faclty staff organizaton shall nclude the followg:

a.

Each o. duty shift shall be composed of at least the minium shi ciw composition shown n Table 5.2.2-1.

b.

All fuel h~anding operations shall be directly supervised by-a GETF UD ER Administ.ative procedures shall be developed and m...ented t*

2mit the workJng hours of unit staff who per formi functkis Smporant to the safe storage of radiated fuel assemblies (e.g.,

GERTIFRED FUEL-IANDL 9-10var Certified opIezators, adiation protection esonnel aI dkenaintena. nce personnel).

Adequate shift coverage shall bent.aintained without routine heav~

use of oveloe. Te baseline for deternng overtime use wll be a 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week.

owever, n the event that unforeseen p. oblems mequhe substantial amounts of overime to be used; or during mjo maintenance or snodifecafions icluding decommi

.ssioning.

activities) the following guidelines shall be followe ona eporry i

An idevidual should not be permitted to work more than I6C hours stranight, excluding shaft tur nove tme;

2.

An.

idividua sho~uld no~t be pecr...Uttd to wor k m.ore tl a, iC hours n any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months perod, sior more than 24 hiours n an 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months perod, nu~...-

e hn72 hours i. any 7 day period, all excluding shift tur nove tme; (continued Maine Yankee A

5-3 Amendment +69 I

Crgzation 5.2 5.2 Ocianizatio.

5.2.2 Uit Staff (on~tnued)

3.

A b. eak of at least h~ous sh~ould be allowed between1 wor k perods, incluing shift turnover time,

4.

Th~e use of oveiVt.ne alhouId be considered o ai ndidu~al bas

a. ' ot for the entire staff on a shiftL Any devitio fom the above guidelines shall be authorized advance by the rant Manage, oi his desiee,

[i accordance wth establshed proceclures and with cfocumentaton of the basis for 9anting the deviation.

Routne deviatio fomi the above guidelines s not autho. zed.

d.

The Sift Man.age sll b a CERTIFIED FUEL I IANDLER.

e.

The Saft Man.ageis sll aepoir to an ndividual who s a CERTIFIED FUEL HANDLER:

Maine Yankee 5-4 Amendment No. 469 1

Or ganization 5.2 Table 5.2.2-I Minimum Shift Crew Comnpstion Position Minimum Ciew Number Shift Manager-I InooIcertof~e operator 14 TOW1 I

I A.

E.~

_~fl FF flfljfja..

._.'ttn.

p...,.

Ik____

[_n_,e.

FrFn sll.

w-e lp Ja l

A_-.

i i..ii i~iliii i...ii

-i Table 5.2.2-1 for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to accommodate unexpected absences of on-duty shift crew members provued s edate acto is taken to restoe the shiftcrew compostoo itow thin the mnu r

hurements of Tale 5.2.2 -1.

This piov on does not permit any saft crew postoi tobe u"manned upon _hf Chalkce due to an 5 01C~l~ n~Shift cm-w meamber beino ate or absarht

I Maine Yankee 5-5 Amendment +f

3 Unit Staff Qualtficaions

, 3

-V.0 WI COl1RlI VNTROVL 53 Uni Stffi _ _ f _ monm Each snembe f the unit staff shall me

e.

othe mi nm FusC qualifications of Regulatry Guide 1.

- September 197 f comparabl positis un~less otherise note i the Techical Specifcatios.

Maine Yankee 5-6 Amendment +61 I

I I aIIIluI 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Trainin-q 5.4.1 A NRG appi ove taini and ieb ati=nn p, gam f, the CERTIFIED FUEl IHANDLERS shaI be maintaned unes the di ection of the Mant Manage o hidesgnee Maine Yankee 5-7 Amendment i6-1

Procedures

5. 5 ADMINITRATIVE GONTROLS 5.5 Piocedures 5.5.1 Witten procedures shall be established, nmplemented, and maintained

~.,.~the following activties:

a.

The piocedues applicable to the safe storage of i diated fuel seconmmended on Regulatory Guide 1.33, Revision 2, Appendix-A,

b.

Emiergency plan mplementation; C. old Weath~er Oper atio is-

d.

Quality assur ai ce for adiological effluen t a, d envriosmieftal monitojng,

e. Re Notection.

ojiam. implem1 entation; and f.

All programns specifed n Specifcation 5.6.

Maine Yankee 5-8 Amendment 1 p

eml A mfl. Ff

-Pl f..

t

...s1-

__ __sznrrs on _1 5.6 5.0 ADMSRAIE GONTRGLS 5.6 Pogiamns and Manua's The followin ig p. ogram a.cs sllI be established, mplemented, and maintaned.

5.6.1 Radiation Protection Program Procedures for personnel radiation pi otectir pillb repared consistent with the eqjuirements of 10 CFR 20 and shall be approved, maintained, and adhered to fo a operations inovn persel adiation exposure.

5.6.2 ffsite Dose C'c-ulation1-MAngAiODeM a.The ODOM sall contai t~e me*thodology and para..eters used the ca'culation of off-site doses resulting fromn adioactive gaseous and iquid effluents, in the calculat jon of gaseous and luid effluent Monitoring alarm and trp setpoints, and n the conduct of thee radoloc esivironmental monitoring progrm; and

b.

The ODCM shall also contai t e adfoactive effluen t con trols and the adiol ogical env onmi ental onitoriOng acrvtes and dese, ptions of the information that should be ncluded n te Annual Radio! gcal Envrionmental Operating and Radioactive Effluent Release Reports required by Specification 5.7.2 and Specification 5.7.3.

Licensee inikiated changes to the ODCM:

a. Sall be docum 5 ented an r.ods of rviews peffor.n1ed sh~alI bVc retained. This docuniertation Shall contain.

1.

Sufficent nformation to support the change(s) together with the appropriate analyses or evaluatn justifying the changeds),

_cntnud Maine Yankee 5-9 Amendment +6 I

f.r

Programs, and Manuals I.-

. -I..~~~~~~~~~~~.

5~~~~~~~~~~~~~~~~~~

Uttsde Vose Uawcula~~on Manuaw

(.

_ (continued.

2.

A deteriaflao. t~at tec ch~ang~e(s).,aintai tec levels of radioactive efflueo t co&ntrol areq~uhed by 1 0 CFR 20.1302, a id 40 GFR 190, 10 CFR 50.36a, anid 10 CFR 50, Appendix, and not adversely mpa~ct the accuracy or reliability of effluent, dose, or setpoit calculationris

b.

SW'al become effectivc after approval of the Planit Manager or designee; and C.

Sh~alI be submit[ted to tc NRC ' tec foint of a com~plete, kegibl~e copy of the entire ODeM as a pa. of o. coi cur ent wHt the Rad'oactive Effluent Release Report for the period of the report i which any change n the ODOM was made. Ech change shall be dentifed by markings n the marg_.. of the affected pages, clearly vndicatngthe area of tI page Iat was cIaged, and sli ndII t the date (.e., mionth and year) the change was mplemnented.

5.6.3 Radeoacteve Effluent Gontrols-rotwam Tis pr ogrami conf, rms to 1 0 CFR 50.36a for te control of r adioactve effluents and for mantanng the doses tor iebers of the public from radIoactive effluents as low as easonably Ihieae The program shal be contained n te ODOM, shall be mplemented by procedures, and Shall Include remedfal actions o be taken whenever the program lintts are

a.

Limitations on te fuinctional-L-g*

gaseous inonotoing n-Strum.enta ahd setpoit deteinhato O ac the ODGM9 Pe C

D ibillty of radioactive liquid and ion including surveillance tests ordance wit the methodology :r (conthued, Maine Yankee 5-10 Amendment 1-6

Progiams, and Manuals S.G6 5.6 rograms, and Manu-als 5.6.3 Radact've Efflent eont, olsr~a. (conin;.ued)

b.

LimitaLtons on tec concenratoons of radioactive mater-ial released n li quid eff luen ts to unriest icted ar eas, confo ming to 1 0 tmes the corcentation values n 10 CFR 20, Appendix D; Table 2, Column 2-,

C.

Montoring, sampling, and analysis of radioactive liquid and gaseous eff luents n accor dancte with 1 0 GFR 20.1302 and with the methodology and parameters in the ODOM;

d.

U. itatis on th e a.nn ual and quarterly doses o. dose co.mmiitnt to a m em ber of the public ftom r-adioactive mate ials n liquid effluents eleased fomt the unit to unrestricted areas, confonnmng to 10 CFR 50, Appendix i

e.

Determination of cumulatwve dose contributions fom rad'oacive effluents for the cur rent calendar quarter and cur rent calendar yea.

in accordance with theimethodology and paramleters hk the ODCM at least every 31 days;

f.

Lhnitat'ons on-the fnctional capablity and use of the luid and gaseous effluent teatment systems to en sur e that appr oprtWe portions of these systemns are used to educe eleases ot radioactivty whenl 4th( estimated doses n a period of 31 days would exceed 2%ofth Uel'ines for the annual dose or dose conititinent, conforming to 10 GFR 50, Appendix ;

released n gaseous effluents to areas beyond the site bounda~

shal be l"mted to the following:

(1)

For noble gases, Less t an or equal to dose rate of 500 ousefnsy to the total body and less thar tequal to a dose rate of 3000 mremsr to the skin, and (2) o lodne-131, odine-I33, itium and all adionucldes n part-cuate form wth half lives greater than 8 days* Less than or equa to a dose rate of 1500 mreslyr to any o gan.

(c Ine IU Maine Yankee 5-1 1 Amendment I61163 I

Pirograms, and Manuals

[_~~~~~~~~~~~.

-~

-n 5.6 Pi ogramis, and Manua's 5.6.3 Radioactive Effluent Controls PEPrOEM! (continued)

h.

Limitations on the annual asnd quarterly ah doses esulting fron noble gases eleased n gaseous effluen ts f om the unit to ar eas beyond the site boundary, cofimn to 10 CFR 50, Appendix ;

Limitation1s on te annual and quarterly doses to a menembe o t~

public f on tium and adionuclides in particulate form with half-lves 9greater than 8 day ngeous effluents released fom the unit to areas beyon te t boundary, confoiniing to 10cr Appeni,and imitations on the annual dose or dose commitment to any memibei of the public due to releases of r adioactivity and to radiatios fron u~anium fuel cycle sources, conformng to 40 CFR 190; (continued)

Maine Yankee 5-12 Amendment 1 1, 1 63 1

Programs, and Manuals 5.6 5.6 Programs, and Manuals This pro pjai --

pr.des a means for p, ocessg1 canges to te Oases o tseTechnical Sp i

a.

haniges to the Bases of the TS shall be made undler appropriate admnstrative controls and revews.

b.

Lci esmy make changes to Oases without pi'or NRC approval provided the changes-do hot nvolve eithe, of the followinT:

A clange in t.e TS ricc porated.i t e lcense, o_

A change to te updated FSAR or Bases tat Ivolves an uireviewed safety question as defined in 10 CFR 50.59.

-c.

The Bases Control Progrn shall contain provisions to ensure that the Bases are maintahted consistent with the FSAR.

d.

Proposed clhang tlatet tle cdtera of 5.6.4.b above 11all be reviewed anid approved by the NRC prioi to implementation.

Changes to the Bases implemented without pror NRC appr oval shall be pr ovided to te NRC ori a f equency consistent with 0 CrFR 50.1 e).

5.6.5 Spenit Fuel Poo' Water Ghemistry Program The spent Fuel Pool Water Ghemistry Progr am shall be established,

i. plenme. ted, a.rid, maintained, whenever hrradiated fuel s stor ed in the Fuel Storage Poo'.

Tl1;s pi

!es co.t.ols for o

spent f_ poo t.r chemistry to minimize the potental effects of corrosion which could affec the safe storage of radiated fuel. The program shall include identfication of cretcal vaiables and control poits for these variables. The pPoola shall also nclude sampling fie inesad defin e coi rectve action s to be taken for off covt ol-p c

stry conditons. The NRC wll be notified pior to elimination or changes to the acceptance critera fr critcal varables-monitored.

(continued)

I Maine Yankee 5-13 Amendment 16I, 166 I

I v; Programs, and Manuals 5.6 5.6 Noggams, and Manua's This

~ pi o-es controls for nservice testing of ASME Code Olasa 1,2 n 3 components neluding applicable supports. The p og ashall includle the following:

a.

Testing fiequc cs pcfod n Secton Xl of tl~ aeAAME D-.oiler and P ressure Vestsel Cod

-an d applicable Addendap as follows:

ASME Boiler and Pressure Vessel Code and applicable Required rFequniesflor Addenda ter minology for peIrfo min~ inservice testing inse.rice testinci actvties-atve Week'y At least once per 7 dlas Monthly At least once lie, 31 days Quarterly or every 3 nionthE At least once pei 92 days Semiannually or every-

-6nmonths At east once pe, 104 days Every 9 moniths At east once pei 276 day.

Yearly or annually, At least once per 366 dlayZ Biennially oreej er At east once pet 731 dlas

b.

Th~e pirovsons of SR 3.0.2 are applicable to time above equired Fs eqencies for perfo v

naece testing activities; C. The pi ovsons of SR 3.0.3 ar e applicable to nser tt'n activities, andl

d.

Nothing n t~e ASM1IE Boilei an d Pi essure V~essel Code shall be construed to supersede the ecquirements of any TS.

I Maine Yankee 5-14 Amendment I-6-f I

Reporting Requirements 5.7 Anmimi TRATIVE CONTROLS I

Z.7 eporting R~equirements The following reports shall be submitted n accor dance with 1 0 CFR 50.4.

5.7 Occuatnal Radiatio Ex osu A tabulat'.

Oil all amnnual basis of the number of station, utility, and othe.

personnel (including contr actors), for whont nonitwrng was perfo... ed, recevn~an annual deep dose equivalent > 100 nuenmly, and thc associated collective deep dose equivalent (esported r.pro-em

~.. 9 to work and ob functions (e.g., fuel handl'ns su

-rmne, 1out'ne maintenance, special maintenancei [dscbemintenance] and waste pi ocessh q). This tabulation supplements the.equiements of 1 0 GFR 20.2206. The doeas

~

nents to vai ous duty functions may-be estimated based on pocket dosimeter, thermiolumniescent'dosimeter (TLD), or film bodge meastraments. Small exposures totaling 20% of the

ndvicual total dose need not be accoun.ted for. In the agregate, at least 00% of the total deep dose equivalent receilved from ex-tenal sour ce should be assigned to specific m ajor wor k functions. The eport shall be submitted by Aprl2 30 of each year.

5.7.2 Annual RadioloefleaI-Environmental O~eratenc Reno.t The Annual Radiological Environmental Operating Report covering the unit activties du n the

-rvu alendar year shall be submitted by M~ay 15 of each year. The report shall nclude summrsiter pretations, and analyses oftrenidsof the results oftheradtIolgi I enironnmental iioiio egpo aifor the reporting period. The mate5 al provided shall be consistent with the objectives outlined in the Offsite Dose Calculatio~n Manual (ODOM), and in 10 CFR 50, Appendix, Sections :V.B.2, V.B.3, and W

wG._:

I Maine Yankee 5-15 Amendment i+-GI

,* v Reporting Requirements 5.7 5.7 Reinoinci Req~uirements 5.7.2 Annual Enkca voonmental Operatron1 Report- (continued)

The Annual Radiological Environm.ental Operating Report shall nclude the results of analyses of all adiologcal enviionmental samples and of all irrnentaI rad'atoon measurements taken dwing the period pursuant to tohe locatio, s specifed n H e table and fu.es ai te ODGM, as well as summared and tabulated results of these analyses and measuiemnents.

In the event that some indivdual results are not available for nclusion with the report, themrport shall be submitted noting and exlinn the easons for the issin resuls. The nissing data shall be submitted ina supplementary epo t as soon as possible.

5.7.3 Radoactve Effluent Release Reot The Radaoact've Effluent Release Report cover ng the ctivities of the unt

.n the priou arshall be submitted piror to May I of each yea in accor danc wt 1 FCR 50.36a. The epoit shall hiclude a sunmnary of thec quanttfeQ of radioactive liguid and gaseous effluents and solid waste released fron the unit. Te mateialprovided shal be consistent with the objectives outlined n the ODCM and Process Control Piogram and n conformance with 10 CFR 50.36a and 10 GFR Part 50, Appendix, Section

=_k-_WB.I Maine Yankee 5-16 Amendment f61

t -

I A".:n High Radoatc Aea 5.80 5.0 igh Radiatio* A, ea 5.0.1 Pu~suan.t to 10 CFR 20, paragraph 20.1601(c), in leu of the requirenents f 10 CFR 20.1601, each high radiatio area, as defined in 10 CFR 20, n which the ntensity of radiation s 100 mrem/h, but 1000 nuenmlhr, Shall be barricaded and conspicuously posted as a high radiation area and en t, an ce thereto shall be co. t. olled by regurioisunce of a Radiation Work Pe~mit (RWP). Individuals qualified in adiation protection procedures or personniel continuously escorted by such individuals may be exempt from the RWP issuace euiement during the performat nce of their assigned duties in high radiation a, eas with exposur e rates 1 000 niremlhr, provided they a, e otherwise following plant radiation protection pi ocedu, es fo. entry into suich h-.gh radiation ar eas.

Any idividual or gru of individuals permitted to en.ter such. as eas shl.l be pr ovided with or acopaid by one oi miore of the following:

a.

A adiation monito.ring device that co, tinuously ndicates tec gadiation dose ate i the ar ea.

b.

A radeation moitoing~ device that continuously tegrates tlh iadeatio dose rate in the area and alarms when a preset ntegrated dose is received. Ent. 7 into such areas with this monitoring devce may be made a-fter thle dose rate levels in te area have been established and personnel are aware of themn.

C.

An individual qualified in raito pi otection p. ocedui es wth. a aadiation dose ate moiosn device, who is responsible for providing positive control over the activities within the asrea asnd" shall perfor m pe iodic adiation surv'eillance at the f equency specified by Radiation Protection in the RWP; (connued)

I Maine Yankee 5-17 Amendment +6 I

V I lhRadiation Area

5.

lgh eadiaton Area (nt inued) 5.0.2 In additioi t o t e equhements of Specification 5.8.1, each high radiation ar ea, as defi. ed i 1 0 CFR 20, with radiation eve's > 1 000 mremll i sall be provided with locked or continuously quar ded door s to prevent unauthor ized entry and the keys shall be mnaintained under the administr ative contr ol of H i Sohift Manager o. duty or adiation protection spriion. Dooms shall remain locked except during periods of atcess by

~e~sonnel us der an appr oved RWP that shall specify the dose ate levels in the imediate work areas and the maximunm allowable stay tmles for indoviduals in those areas. In lieu of th e stay tme specification of te RWP, direct or em ote (such as closed circuit TV' cameras) con~tinuous surveillance may be made by personnel qualified in adiation pr otection pr ocedur es to pr ovide positive exposur e control over the activities being performed within the-area.

levels of > 1000 mrenmlhr, accessible to personnel, that ar e located within Varge areas such as reactor containment, where no eniclosure exists for purposes of locking, or that. ca.nn ot be continuously guar ded, and wher e n o en closur e ca.n be easonably constr ucted ar ound t e individual ar ea, that ndivodual area shall be barr icaded and ospcusly posted, anda flashing light shall be activated aa

-rng I Maine Yankee 5-18 Amendment +61 I

Technical Specifications Maine Yankee Nuclear Plant Bases This Setion is not applicable to a completoly defueled plant,

TABLE OF CONTENTS stASES TALGF CONTENTS B 3.0 LIMIFTING-O DOPRATION (LO) AR0 O0 B 3.0-1 SU A G E

R M N

S )A PW BLT B 3.0 B 3.1 DEFUELED SYSTEMS o 3...

Fue. Sto. agePoo' Wate Leve B 3.1-1 o 3.1.2

_ Storag _

_..PB

o.

.Hc ll........................

r 3D.

.4 Maine Yankee i

Amendment i6 I

LCO Applicability I;.'

C 3.0 LIMITING ONDITION FOR O

N APP ABIW BASES LCO's LCO 3.0.1 and 3.0.2 establish the general requirements applicable to all Specfcations and apply at all times, unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicabilty statement withn each indivdual Specficatio i as te equirement fo when the LO s euried to be met (i.e., when the facilty s i the specified conidtions oF the Applicability statement of each Speciflca ion)-.

LGO 3.0.2 LCO 3.0.2 establishes that upon~ discover-y of a faiug.e tonmeet an LCO, the associated AC3TIONS shall be met. The Completion Time of each Requied Action fo a~ ACTIONS COo.dftio.. s applicable fonm the point n tme that a, ACTIONS Cond~ton'is entered. The Required Actions establish those remedial measures thatimust be taken within specified Completion Tames when the equiemen~ts of an LC) are not met. This Spicao establishes that,

a.

Com1 pletion of thec Requred Actions witi tec specified Coplefion Times constitutes compliance with a Specficor-nd

b.

Completion of the Required Actions is not required when-an ICO s mnet-within the specified eompletion Time, unless othewse specfied.

C3ompleting the Requied Actions es not equid when an LCO s met ori no onger applicable, unesother.s wstae the nd'vdtmI Specifiatins`;

(confitedt)

Maine Yankee B 3.0-1 Amendment -64

LCO Applicability B3.0 BASE LCO 3.0.2 Tl e Competion T. es o t e Regquii d Action5s a, e also (contnued) applicable when. a spcfe con~ditio i the Applicabil ty s enerd

!ntentionally. The eason~s fos teionally elying on the ACTIONS include, but are not "imeted to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation ol problerms. EnterngACTIONS for-thiese -:easons m-u-t be done n a snan~e, that does not cornp om~etesf tr of rradiated fuel.

intentona ni ito ACTIONS should n~ot be mrade for convenience.

Maine Yankee B 3.0-2 Amendment 46I I

IRR Arinlof-Abilf B1 3.0 BASES SRs SR 3.0.1 trough SR 3.0.3 establis te genera' requirements applicabl-eto al Specif'cat-osandapplyataltimes, unless otherisestated.

SR 3.0.1 SR 3.0.1 estalishes the requirement that SRs must be met du ing the specified uzvon n the Applicablity for which the requirements of tt LCO apply, unless othe efed in the indvdua SRs. ThIs Specfcaton s to ensuie that Surveillances are prfrmed to verfy tha variables re within spiecified limits. Failure to meet aSurveillance within the specified Fsrequency iacodance with SR 3.0.2, coi stitutes a failur e to meet an LCO.

Surveilances do not haive to be pe fonned when the facility is in a specified condition for which the equireeits of the associated LCO are not applicable, unless oth spe ified_

S R 3.0.2 SR 3.0.2 permits a 25% extension of te i te val specified in the Fr equency.

This extension facltates Srveillance scheduling and considers facility Conditons that may not

utable for conducting the Surveillance (eg.-,

other ongoing Sureillance or mantenance activities).

Thme 25% extension does not significantly degrade the reliability that results fioi performing the Su. vllan~ce at its specified Freuec. This is based on the ecogniton that the nost probablem re.l of a particulai Surveillance being prfrmd is the verification of confooonance with the SRs. Any ecpontoSR 3.0.2 are stated in the ndividual Specifications.

The provisions of SR 3.0.2 are not intended to be used epeatedly merely as a convenience to extend Surveillance intervals or periodic Completion Tomc intervals beyond those specified.

(conti nud)

Maine Yankee B 3.0-3 Amendment 64

SR Aplability B 3.0 BASES S R 3.0.3 ZIRn..

3 establishes the flexibiIty to defe. declaring an affected variable otsd hesecified lmits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months applie.

from the point in time that it is discovered that the Surveillance has not been perormed n accordance wth SR 3.0.2, and not at the tme that the specified Requency was not met.

TIs delay perod provide adeqate t 1e to complte Suvellan=ces tha have been missed. This delay pe, od permits the completion ofa Survefflance before comply ng wath Required Actions o. other remediaI measur es that might preclude completion of the Surveillance.

The basis for this delay period ncludes consideration of facli~ty Conditions adequate planning, availability of per sonnel, the time required to pes fo...l the Surveillance, the safety ifnificance of the delay in completing the r equired Survellance, a.nd Elhe cgnto t at h e most probable resulIt of any particular Surveillance being perfor med s the ver fication of conformance with the requrements. When a Surveillance wit', a Frequency based not on tne intervals, but upon specified facilty conditions o.

oper ation al situationis, is discover ed not to h ave been pe formived when specified, SR 3.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perfo1 m the Surveillance-Faifur e to compl, with spetifed F eue. ces for SRs s expected to be an infiequent occurrence. Use of thiedelay peodestablished by SR3.0.3 sa flexib~ity which SWo ntended tLo be used as aioveece to extend hW~f-rR F-Maine Yankee B 3.0-4 Amendment 4,64

SR Applicability B.O BASES S R 3.0.3 If a Surveillance s not completed within the allowed delay period, then the (continued) variable is co.nsider ed outside the specified imits an d the Comnp1etio n Times of the Required Actions for the applicable LCO Co, ditio. s begin mmediately upon exphationoffthe delay period. f aSurve"'anceis fa;Ied wthinthe delay periodt, thien thievaiableis outside tie specfled imots and the Compiceon Trnes of the Requied Actions for the applicable LCO Go. dtio.s begin mmediately upon to failure of the Survefflance.

CTornpaetion of the Surveillance wthn the delay period allowed by-this Specification, o, within the Cormpletion Time of the ACTIONS, restores compliance woth SR 3.0.1.

Maine Yankee B 3.0-5 Amendment 461 I

Fuel Storage Pool Water Level t j {,

' ('r J

B

~~* 3.1.1 B 3.1 DEFUELED SYSTEMS B3.1.1 Fuel toage Poo' Water Level BASES BACKCGROUND Th~einniu watr lvel i te feJ storage pool m.eets t~e assumptions of odine decontamination factors following a fuel han~dlig acciden~t. The specified wate, level pirovides shielding dse.

ung th ometosetfuland miizs te _eeaae A gen.eral descriptio1 of tme fuel storage pool design and tec fuel storage pool cooling and purficaton system s given n the SAR. Th assuiptnios of the fuehl hndling accideae in the SAR.

APPLUGABLE Th~e Maine Yainkee facltei pe njtly shutdowniand the tme SAFETY ANALYSES si ice the last ope o

ftereactor has allowed significan.t decay offissio pioducts (especially the daughter poducts wth short half-B ves) cntained-n the spent fuel. The spent fuel pool water level s adequate to pi ovde necessary shelding for the fuel hanidlers to minimze occupatioral dose durng normal spent fuel handlng actavties-Tih accident agiasis for the fuel handling accident, as described th e FSAR, assumes-that t e aciden t occurs9 on e-year after shutdown from operation~s and a decontamination factorfor iodie of 75 (19 feet of water.) No credit is taken for ventilation air fltration or solatio.

Fr. the pur pose of establish'n anuprlimit on the anmount of fuel damage resultng from a fue ann

acIent, it is assuied thet the fue' assembly s dropped during handling. The numbe of Utured fuel ods which would esut depeids on seve ral varables including the kinetic ener gy at impact ai d fuel assembly or ientatioi dming impact. The analysis assumes that all ods _ the dropped assembly fail upon impact. The esulting doses calculated for the fuel hanidlig cidenit are below t e NRC acceptance Bimit for this accidert, which s 10% of 10 GFR Part 100 limits*

(coiniiued)

Maine Yankee B 3.1-1 Amendment 161, 12,

.S 98 01, 99.

Fuel Storage ool Water Level 3.1.1 BASES APPLICABLE TIhe i iorm~aI operating wa~ter eve' of th~e fel stor age pool is SAFETY ANALYSES establishead at approximately 36.5 (44 foot elevation ) feet above the (con tinued) floor of thec pool. Thec Techni.cal Spcification. value of 21 feet ove.

the top of irrsadiated fuel assemblies seated n the stor age acks Is vlent to 34.7 feet of water above the fuel storage pool floor (42.2 foteevation~). The top of the fuel assembly is defoied as thebottomi ofteflow plate, which is the top of the fuel rods. In the case of a fuel assembly dropped to the bottom ouf the fuel storage pool and standing upright, the Techical Specificationi Water Level pr ovides more than 19 feet of water for odene decon~taminationi. in the case ol a fuel assembly dropped an~d lying hoi zon~tally on top of the spent fuel r acks, the Technical Specification Water Level pr ovides more than 19 feet of water above the top of the bundle.

A reduction i margin~ of safety for the fuel handlin~g accident occurs when the acceptance limit (10% of 10 CFR Part 100 limits) is no longer met. The mnasg that exists between the technical specification limit for the fuel storage pool water eve' an~d the fuel handling accident acceptan~ce limit represents opeintiosn margiit Radiological shi;eldin analysis has deteanflned tat t~e Techn.icel Specification Water Level provides a sufficient amounit of water above the top of a fuel assembly (bottom of the flow plate ) raised o Its maximum height to mainitain the radiationi dose ates less than0 irrenmlir at the su. face of the water an~d ess than 50 mr-enmlhr at thte fuel hanidling hoist platfkrm or the walkway aroun.d the pool.

A reduction inm..rin~of safety for thieradiological shield'ng an~ayI occur hen the a cceptance limit is no longer met. The acceptanc limit is defined as that combin~ation of occupancy timte and dose rate such th at o statios per sonn, el r eceive n excess of 5 rem per year-(10 CFR 20.1 201).

-~ ~ ~ ~

~

~~~~~~~~~~Gniud Maine Yankee B 3.1-2 Amendment 16&1, 162, TS 9 01, 99-01 I

I

Fuel Storage Pool Water Level B 3.1.1 LCQ The fel stor age pool water level s requied to be > 21 ft over the top

-of rradated fuel assembies seated in. th ks. The specified water level pi eserves the assumptions of t e fuel a, Mig accident analysis and provides shielding to minimize the general area, dose when irradiated fuel is being moved. As such, t's the mnimum level requred for movement of rradiated fuel within the fuel storage PF APPLlCABlLlTY This LGO applie-Ihnve radiated fuel assemblies a, e being n oved n the spent fuel pjool, sh ce the potential fo a elease of fission products ex..ts and icreased wate. eve' sheldn, s needed.

ACTIONS A.j When the nitia condffions for ah accident antb met, steps should be taken to preclude the accident-fiorn occurring. When the spent fuel pool water level is owe, than the required level, the movement of is iadated fuel assemblies in the spent fuel pool S mniedatlysupnded. This effectively precludes a spen t fe handling accident from occurrIing. ThS de not pr eclude movement of a fuel assembly to a safe poiin SURVEILLANE R-sR-B-1A REQUI REM ENTS This SR verfles sufct fue stoinge pool water s available n the event of a fei h ndlin.g accident and to provide shielding to mnimize the general area doso during the movement of iradlated fuel. The water level in the spent fuel pool must be ec eked per iodicallyhe mvgfuel. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Fie~e c

p, opriate because the vouen the pool is noinatabLe&..

W-c level chare are cont.olied by facility ocedures and are acceptable, based on operatin exeie Maine Yankee B 3.1-3 Amendment 161, 12, TSB 98-01, 99-01 I

I

Fue Storage Pool Boron. Conce.tratioi B 3.1.2 BASES LCQ Th~e fel stor age pool bo, o11 cnent. ation. is eqjuhed to be ): 1 000 ppm when the L O apples. The Speed concentraton of dissolved boon in the fuel storage pool p eserves the assumptions used in the analyses of potential criticality accident esulting from the misplacement oF an fei assembly the fuel storagepool. Thisconceati oiof dIssoIved boroI I the ininimnt resud concentrate see !

ful assembles are stored n te fuel sto age pool and a pool verficatim h 1 ias not been pe fo, r m Ied.

APPLIGABILIT' This LGO applies wheneve; fuel assenibles are Mtmred n the spent fuel pool and a fuel pool vefcation has not been prefonmed since the last movemtent of fuel assemblies n the spent fuel pool. This LCO does not apply following the ver fication since the verificatlon would cos finn 1 that t e. e are n o misplaced fuel a-sembIe"s. This veefication ncludes a demonstration that fuel assemblies as e pr operly located n the correct fuel storage ack in accordance with gure 4.1.1 and that there are no fuel assem~blies outside of or on top of the fuel storage rack~s. With no futher fuel assembly movements in p.es -s, t~ere s no potential for a misplaced o a dr opped fuel assemW.

ACTIONS A.. A.2 an dA.

Wh~e te concenhtation of boron, n flhe fuel storage pool s less llan required, mnniediate action must be taken to preclude an accide.,t from happening or to mitigat the conseqences of an accident n progress.

This s most efficieny "chIeI d by mmediately suspending the movement of fuel assemblies. This does not preclude movem~ent of a fuel assembly 0 load to a safe position. n addition, action must be immediately intiated to restore boron concentration to within "Iit. Alternately, beginninga verfcatoon of the fuel storage locations, to ensure pr oper locationis of the fuel can be perfo*.1ed.-

SURVEI=L:ANCE SR-3.1.2.1 This SR veralie t~at t~e cocen1traton, of bo. on n t~e fel storage pools within the required limit during te mnovement of fuel assemblies As long as this SR is met, the analyzed accidents ae fully addressed. The 7 day Frequency' saporAte because no mlaJor replenishment of pool wate, which could Ieul Ma '=~ of the boron concentration is expected-to take place over a s ort pe iod of thmte.

B.3.1-5 Amendment 464 TSB 99 O2

ATTACHMENT IV PROPOSED UPDATED VERSION OF REVISED TECHNICAL SPECIFICATIONS

Technical Specifications Technical Specifications Maine Yankee Nuclear Plant Specifications

TABLE OF CONTENTS SPECIFICATIONS TABLE OF CONTENTS 1.0 USE AND APPLICATION..............................................

1-1 2.0 SAFETY LIMITS....................................................

2-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.....

........ 3-1 4.0 DESIGN FEATURES..................................................

4-1 4.1 Site........................................................

4-1 5.0 ADMINISTRATIVE CONTROLS............

............................. 5-1 Maine Yankee i

Amendment 161

Use and Application 1.0 1.0 USE AND APPLICATION This section is not applicable to a completely defueled plant.

Maine Yankee I -I Amendment +6-

SLs 2.0 2.0 SAFETY LIMITS (SLs)

This section is not applicable to a completely defueled plant.

I LCO Applicability 3.0 Maine Yankee 3-1 Amendment +6+/-

I

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY This section is not applicable to a completely defueled plant.

I Maine Yankee 3-2 Amendment +6-1

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Site Description 4.1.1 The plant shall be located on property owned by Maine Yankee Atomic Power Company on Bailey Point in the Town of Wiscasset, Lincoln County, Maine.

I I

Maine Yankee 4-1 Amendment +-1-+

I

Administrative Controls 5.0 5.0 ADMINISTRATIVE CONTROLS Appropriate administrative controls are located in the Maine Yankee I

Quality Assurance Program.

I Maine Yankee 5-1 Amendment +6

Technical Specifications Maine Yankee Nuclear Plant Bases This Section is not applicable to a completely defueled plant.

Maine Yankee 5-2 Amendment +61 I

RA-03-153, Proposed Change No. 217: License and Technical Specification

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RA-03-153, Proposed Change No. 217: License and Technical Specification

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