ML20205R275

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Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit
ML20205R275
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/19/1999
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20205R270 List:
References
NUDOCS 9904220265
Download: ML20205R275 (50)


Text

Technical Specifications Millstone Nuclear Power Station Millstone Unit 1 Waterford, Connecticut

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1.0 U SE AN D APPLIC ATION.......................................................... 1.1 -1 i

1.1 Defi n it ion s........................................................................ 1.1 - 1 l

1.2 Logical C onnectors........................................................... 1. 2-1 l

1.3 Completion Times............................................................ 1.3-1 1.4 Frequency......................................................................... 1. 4-1 I

l 2.0 SAF ETY L IM ITS......................................................................... 2. 0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO)

AP P LI CAB I L ITY...................................................................... 3. 0-1 l

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.......... 3.0-2 3.1 Defueled S ystems.......................................................... 3.1 -1 l

3.2 S pent Fuel Hand ling....................................................... 3.2-1 i

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4.0 D E S I G N F EATU R E S................................................................ 4. 0-1 4.1 S ite Location............................................................. 4. 0-1 4.2 F uel Storage................................................................. 4. 0- 1 5.0 ADMINISTRATIVE CONTROLS........................................... 5.0-1 5.1 Re spon sibility............................................................. 5. 0-1 5.2 O rganization................................................................. 5.0-2 l

5.3 U nit Staff Q ualifications.................................................... 5.0-5 l

l 5.4 Tra i n i ng............................................................................... 5. 0 6 5.5 P rocedu res........................................................................ 5. 0-7 5.6 Programs and Manuals...................................................... 5.0-9 5.7 Reporting Requirements............................................... 5.0-13 5.8 H igh R adiation Area............................................................ 5.0-16

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Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CERTIFIED FUEL A CERTIFIED FUEL HANDLER is an individual who complies HANDLER with provisions of the CERTIFIED FUEL HANDLER training program required byTechnical Specification 5.4.1.

OPERABLE.

A system, subsystem, division, component or device shall be OPERABILITY OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its specified safety function (s) are also capable of performing their related support function (s).

(continued)

Millstone - Unit 1 1.1-1

r Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required

Actions, Completion
Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are

,A_NQ and QE. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions.

These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are ideniified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Millstone - Unit 1 1.2-1

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 Verify.....

AND A.2 Restore..

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Millstone - Unit 1 1.2-2

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 Trip.....

98 A.2.1 Verify.....

8HQ A.2.2 Reduce This exan.ple represents a more complicated use of logical connectors.

Required Actions A.1 and A.2 are alternative choices, only one of which must be performed as indicated by the use of the logical connector QB and the left justified placement. Either of the Actions may be chosen, if A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

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Millstone - Unit 1 1.2-3

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum 1

requirements for ensuring the safe storage of irradiated fuel. The ACTIONS associated with an LCO state Conditions that typically i

describe the ways in which the requirements of the LCO can fail to be met.

Specified with each stated Condition are Required Action (s) and Completion Times (s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO.

Required Actions must be completed prior to the expiration of the specified Completion Time.

An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

EXAMPLES The following examples illustrate the use of Completion Times with j

different types of Conditions.

l (continued)

Millstone - Unit 1 1.3-1

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Tirnes EXAMPLES (continued)

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Action and A.1 Verify.....

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion AND Time not met.

A.2 Restore 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Condition A has two Required Actions.

Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition A is entered. The Required Actions of Condition A are to perform the i

verification required by ACTION A.1 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND to perform the restoration required by ACTION A.2 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for performing ACTION A.1 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is i

allowed for performing ACTION A.2 from the time that Condition A was entered.

If ACTION A.1 is completed within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the time allowed completing ACTION A.2 is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed for completing ACTION A.2 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

IMMEDIATE When "Immediately"is used as a Completion Time, the Required COMPLETION Action should be pursued without delay and in a controlled TIME manner.

Millstone - Unit 1 1.3-2

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

1 DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "Specified Frequency es referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability.

The "Specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In the'se examples, the Applicability of the LCO (LCO not shown) is when irradiated fuel is stored in the fuel pool.

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i (continued)

Millstone - Unit 1 1.4-1

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVElLLANCE FREQUENCY Verify parameter is within limits.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which the associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in the specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified, then SR 3.0.3 becomes applicable.

(continued)

Millstone - Unit 1 1.4-2

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify parameter is within limits.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving irradiated fuel

.A.RQ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Example 1.4-2 has two Frequencies.

The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. The use of " prior to" indicates that the surveillance must be performed once before the initiation of fuel handling activities. This type of Frequency does not qualify

. for the extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the " prior to" performance in this example).

Millstone - Unit 1 1.4-3

Safety Limits 2.0 l

2.0 SAFETY LIMITS l

This section is not applicable since Millstone Unit 1 is permanently defueled.

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i LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.01 LCOs shall be met during the specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.02 Upon discovery of the failure to meet an LCO, the required actions of the associated Conditions shall be met.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time (s), complet;on of the required action is not required unless otherwise stated.

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Millstone - Unit 1 3.0-1

t SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during specific conditions in the Applicability for individual LCOs unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable j

equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met and the applicable Condition (s) must be entered.

The Completion Times of the Required Actions begin immediately upon expiration of the delay period.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met and the applicable Condition (s) must be entered. The Completion Times of the Required Actions begin immediately upon failure to meet the Surveillance.

i Millstone - Unit 1 3.0-2

Fuel Storage Pool Water Level 3.1 3.1 DEFUELED SYSTEMS 3.1.1 Fuel Storage Pool Water Level LCO 3.1.1 The Fuel Storage Pool Water Level shall be greater than or equal to 33 feet.

APPLICABILITY Whenever irradiated fuel is stored in the Fuel Storage Pool.

i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i

A. Fuel Storage Pool Water A.1 Suspend all Fuel Immediately Level not within limit.

Handling Operations.

AND A.2 Restore Fuel Storage immediately Pool Water Level to within limits.

SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY i

SR 3.1.1 Verify the Fuel Storage Pool Water 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Level is greater than or equal to 33 feet.

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Record the Fuel Storage Pool Water Level.

Millstone - Unit 1 3.1 -1

o Reactor Building Crane Operability 3.2 3.2 SPENT FUEL HANDLING 3.2.1 Reactor Building Crane Operability LCO 3.2.1 The Reactor Building crane shall be OPERABLE.

APPLICABILITY When the Reactor Building crane is used for handling of a spent fuel cask.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor Building crane A.1 Suspend all Spent immediately is INOPERABLE.

Fuel Cask handling and place the load in a safe condition.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1 Conduct a visual inspection of Within 4 days prior to crane cables, sheaves, book, yoke, and Spent Fuel Cask handling cask lifting trunnions. Conduct no-load operations and every 4 mechanical and electrical tests to verify days thereafter during proper operation of crane controls, spent fuel cask handling brakes, and lifting speeds. Conduct a load test by lifting the empty cask out of the pivot cradle.

Millstone - Unit 1 3.2-1

Reactor Building Crane Travel with a Spent Fuel Cask 3.2 3.2 SPENT FUEL HANDLING 3.2.2 Reactor Building Crane Travel with a Spent Fuel Cask LCO 3.2.2 The Reactor Building crane loaded with a Spent Fuel Cask shall be prohibited from travel over irradiated fuel assemblies. The Reactor Building crane mode switch shall be in a " Mode 2" position and the mode switch key removed.

APPLICABILITY When the Reactor Building crane is used for handling of a spent fuel cask.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor Building Crane A.1 Suspend all Spent immediately mode switch not in Fuel Csak handling

" Mode 2" position,ANQ and place the load in mode switch key not a safe condition.

removed.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2 Demonstrate OPERABILITY of Reactor Within 7 days prior to Building crane interlocks and limit Spent Fuel Cask switches which prevent crane travel handling operations over irradiated fuel assemblies.

Every 7 days thereafter during Spent Fuel Cask handling I Il 11 Millstone - Unit 1 3.2-2

m Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Unit 1 Reactor Building is located on the site at Millstone l

Point in Waterford, Connecticut. The nearest site boundary on land is 2063 feet northeast of the reactor building (1620 feet l

northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10CFR100.3(a). No part of the site that is closer to the reactor building than 2063 feet shall be sold or leased except to The l

Connecticut Light and Power Company, Westem Massachusetts l

Electric Company or the Northeast Nuclear Energy Company or l

their corporate affiliates for use in conjunction with normal utility operations.

4.2 Fuel Storage 4.2.1 The new fuel storage facility shall be such that the K.n dry is less than 0.90 and flooded is less than 0.95.

4.2.2 The L of the spent fuel storage pool shall be less than or equal to 0.9. This kvalue is satisfied with fuel assemblies having a maximum k-infinity of 1.24 in the normal reactor configuration at cold conditions, and an average U-235 enrichment of 3.8 weight percent or less.

4.2.3 The number of fuel assemblies stored in the spent fuel storage pool shall not exceed 3229 bundles.

Millstone - Unit 1 4.0-1

f-Responsibility 5.1 I

l 5.0 ADMINISTRATIVE CONTROLS l

5.1 Responsibility 5.1.1 The _ Designated Officer shall be responsible for overall operation of the Millstone Station Site and shall delegate, in writing, the succession to this responsibility. The Designated Manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession of this responsibility.

l 5.1.2 The Shift Manager shall be responsible for the control room command function.

5.1.3 Unless otherwise defined, the technical specification titles for members of the I

staff are generic titles. Unit-specific titles for the functions and responsibilities l

associated with these generic titles are identified in the Quality Assurance Topical Report.

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Millstone - Unit 1 5.0-1

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite And Offsite Oroanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safe storage of irradiated fuel.

a.

Lint,s of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the Quality Assurance Topical Report.

b.

The Designated Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities and resources necessary for maintenance and storage of irradiated fuel in a safe condition.

c.

The Designated Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to ensure the safe storage of irradiated fuel.

d.

The individuals who train the CERTIFIED FUEL HANDLERS and those who carry out radiation protection functions or perform quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.

(continued)

Millstone - Unit 1 5.0-2 f

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5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.2 Facility Staff 1

a Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 5.2-1.

b.

At least one person qualified to stand watch in the control room shall be present in the control room when irradiated fuel is stored in the fuel storage pool.

c.

Deleted d.

An individual qualified in radiation protection procedures shall be onsite during fuel handling operations.

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e.

All fuel handling operations shall be directly supervised by a qualified individual.

f.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform functions important to the safe storage of irradiated fuel assemblies. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

g.

The Shift Manager shall be a CERTIFIED FUEL HANDLER.

l (continued)

Millstone - Unit 1 5.0-3

l Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization l

5.2.2 Facility Staff (continued) i TABLE 5.2-1 l

MINIMUM SHIFT CREW COMPOSITION (1)

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Certified Fuel Handler 1

i Non-Certified Operator 1

(1)

The above shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided expeditious actions are taken to fill the required positions.

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(continued)

Millstone - Unit 1 5.0-4

Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:

l 5.3.1.1 The Operations Manager or Assistant Operations Manager shall be a CERTIFIED FUEL HANDLER.

5.3.1.2 The Health Physics Manager shall meet or axceed the qualifications of Regulatory Guide 1.8, Revision 1.

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Millstone - Unit 1 5.0-5 e

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l Training 5.4 5.0 ADMINISTRATIVE CONTROLS l

5.4 Training

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l 5.4.1 An NRC approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

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Millstone - Unit 1 5.0-6

r Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS l

5.5 Procedures l

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

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a. The procedures applicable to the safe storage of irradiated fuel recommended in Appendix "A" of Regulatory Guide 1.33, February 1978;
b. Fire Protection Program implementation;
c. Cold Weather Operations;
d. Quality assurance for radiological effluent and environmental monitoring;
e. Liquid and gaseous radioactive effluent discharges from the unit for all operations involving offsite releases of radioactive effluents.

These procedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM; l

f.

Fuel handling operations;

g. All programs specified in Specification 5.6.

5.5.2 The Designated Manager, Designated Officer, or Designated Senior Officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. The review per the PORC, SORC, or Station Qualified Reviewer Program shall be in accordance with Northeast Utilities Quality Assurance Program (NUQAP).

5.5.3 Procedures listed in Specification 5.5, and changes thereto, shall be approved by the Designated Manager, or Designated Officer or by cognizant managers or directors who are designated as the Approval Authority by the Designated l

Manager, or Designated Officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.

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(continued)

Millstone - Unit 1 5.0-7

Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures (continued) 5.5.4 Each procedure of Specification 5.5.1, and changes thereto, shall be reviewed by the PORC or SORC and shall be approved by the Designated Manager or Designated Officer, or be reviewed and approved in accordance with the Station Qualified Reviewer Program prior to implementation.

Each procedure of Specification 5.5.1 shall be reviewed periodically as set forth in administrative procedures.

5.5.5 Temporary chartus to procedures of Specification 5.5.1 above may be made provided:

a.

the intent of the original procedure is not altered; b.

the change is approved by two members of the plant management staff, at least one of whom is a CERTIFIED FUEL HANDLER; c.

the change is documented, reviewed by the PORC or SORC, or the Station Qualified Reviewer Program, as applicable, and approved by the Designated Manager, Designated Officer, or the Station Qualified Reviewer Program Department Manager within 14 days of implementation.

5.5.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 5.6.1 shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision.

5.5.7 Temporary changes may be made for the Radiological Environmental Monitoring

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Program provided the intent of the original procedure is not altered and the i

change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

(continued)

Millstone - Unit 1 5.0-8

Programs and Manuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals The following programs shall be established, implemented and maintained.

5.6.1 Radioloaical Effluent Monitorina and Offsite Dose Calculation Manual (REMODCM)

Section I, Radiological Effluents Monitoring Manual (REMM), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.

Section 11, The Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications.

Changes to the R,EMODCM:

a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1) sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and 2) a determination that the change will maintain the level of radioactive effluent control required by 10CFR20.106, 40CFR Part 190,10 CFR 50.36a and Appendix I to 10CFR50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by SORC and the approval of the Designated Officer; and Millstone - Unit 1 5.0-9

Programs and Manuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals 5.6.1 Radioloaical Effluent Monitorina and Offsite Dose Calculation Manual (REMODCM)(continued)

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

(continued)

Millstone - Unit 1 5.0-10

l Programs and Manuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals l

5.6.2 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications 1

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

l b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

1.

a change in the TS incorporated in the license; or 2.

a change to the updated FSAR or Bases that involves an unreviewed l

safety question as defined in 10CFR50.59.

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

l d.

Proposed changes that meet the criteria of Specification 5.6.2b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10CFR50.71(e).

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i (continued)

Millstone - Unit 1 5.0-11

I I

J Programs and Manuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals 5.6.3 Fuel Storaae Pool Water Chemistry Proaram f

This program provides controls for monitoring fuel storage pool water chemistry to minimize the potential effects of corrosion which could affect the safe storage of irradiated fuel. The program shall include identification for critical variables and control points for these variables. The program shall include sampling i

frequencies and define corrective actions to be taken for off control point chemistry conditions. The NRC will be notified prior to elimination or changes to the acceptance criteria for critical variables monitored.

Millstone - Unit 1 5.0-12

Reporting Requirements l

5.7 l

5.0 ADMINISTRATIVE CONTROLS l

l 5.7 Reporting Requirements The following reports shall be submitted in accordance with 10CFR50.4.

5.7.1 Occupational Radiation Exposure Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mremlyr and their associated man-rem exposure according to work and job functions (e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10CFR Part 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report shall be submitted by March 1 of each year.

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Millstone - Unit 1 5.0-13

Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.2 Annual Radioloaical Environmental Operatina Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year.

The Annual Radiological Environmental Operating Report shall include that information delineated in the REMODCM.

)

(continued)

Millstone - Unit 1 5.0-14

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Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.3 Annual Radioactive Effluent Release Report l

NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radweste systems, the submittal shall specify the releases of radioactive material from l

each unit.

A routine Radioactive Effluent Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year.

The report shall include that information delineated in the REMODCM.

Any changes to the REMODCM shall be submitted in the Annual Radioactive Effluent Report.

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(continued)

Millstone - Unit 1 5.0-15 l

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High Radiation Area 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 High Radiation Area 5.8 Hiah Radiation Area 5.8.1 Pursuant to 10CFR Part 20.1601(c), in lieu of the requirements of 10CFR Part 20.1601(a), each high radiation area as defined in 10 CFR Part 20 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 or equivalent. Individuals trained and qualified in i

radiation protection procedures (e.g., a health physics technician) or personnel continuously escorted by such individuals may be exempted from this RWP requirement while performing their assigned duties in high radiation areas where radiation doses could be received that are equal to or less than 1 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (measured at 30 centimeters from any source of radiation) provided they are othenvise following plant radiation protection procedures, or a general radiation protection RWP, for entry into such high radiation areas.

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

a.

A radiation monitoring device that continuously indicates the 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 rates in the area have been determined and personnel have been made knowledgeable of them, c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device.

This individual is responsible for providing positive radiation protection control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation protection procedures or the applicable RWP.

(continued)

Millstone - Unit 1 5.0-16

High Radiation Area 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 High Radiation Area 5.8 Hiah Radiation Area (continued) 5.8.2 In addition to the requirements of Specification 5.8.1, areas that are accessible to personnel and that have radiation levels greater than 1.0 rem (but less than 500 rads at 1 meter) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source, or from any surface penetrated by the radiation, shall be provided with locked or continuously guarded doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the appropriate supervisor on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that specifies the dose rates in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of a stay time specification on the RWP, direct or remote continuous surveillance (such as closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could result in radiation doses greater than 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and that are within large areas where no enclosure exists to enable locking and where no enclosure can be reasonably constructed around the individual area shall be barricaded and conspicuously posted. A flashing light shall be activated whenever the dose rate in such an area exceeds or is expected to exceed 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface penetrated by the radiation.

Millstone - Unit 1 5.0-17

Docket No. 50-245 B17621 i

Millstone Nuclear Power Station Unit No.1 Retvoed Bases Paaes for Permanentri Defueled Technical Specifications April 1999

i Technical Specifications Bases l

Millstone Nuclear Power Station Millstone Unit 1 Waterford, Connecticut

TABLE OF CONTENTS B 3.0 LIMITING CONDITION FOR OPERATION (LCO)

AP P LICAB I LITY.................................................................... B 3. 0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR)

AP P L I C AB I L ITY...................................................................... B 3. 0-2 B 3.1 D E F U E LE D SYSTEMS................................................... B 3.1 -1 B 3.2 S P E NT F U E L HAN D LING................................................ B 3.2-1 l

Millstone Unit No.1 i

LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 and 3.0.2 establish general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when the LCO is required to be met (i.e., when the facility is in the specified conditions of the Applicability statement of each specification).

LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered.

The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This specification establishes that:

a.

Completion of the Required Actions within the specified Completion Times constitutes compliance with a specification; and b.

Completion of the Required Actions is not required when an LCO is met within the specified Completion Time, unless otherwise specified.

Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications.

The Completion Times of the Required Actions are also applicable when a specified condition in the Applicability is entered intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to',

performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise i

the safe storage of irradiated fuel. Intentional entry into ACTIONS should not be made for convenience.

Millstone Unit No.1 8 3.0-1

SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through 3.0.3 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise specified.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs.

This Specification is to ensure that surveillances are performed to verify that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Surveillances do not have to be performed when the facility is in a rpecified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified.

SR 3.0.2 SR 3.0.2 permits a 25% extension of the interval specified in the Frequency.

This extension facilitates Surveillance scheduling and considers facility conditions that may not be suitable for conducting the Surveillance (e.g., other ongoing Surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs.

Any exceptions tri SR 3.0.2 are stated in the individual Specifications.

The provisions of SR 3.0.2 are not intended to be u=ed repeatedly merely as a convenience to extend Surveillance intervals ar periodic Completion Time intervals beyond those specified.

(coritinued)

Millstone Unit No.1 B 3.0-2

SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> applies from the point of time that it is discovered that the Surveillance has not been performed in accordance to SR 3.0.2, and not at tne time that the specified Frequer.cy was not met.

This delay period provides adequate time to complete Surveillances that have been missed.

This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of facility conditions, adequate planning, availability of personnel, the time required to perform the Surveillance. the safety significence of the delay in completing the required Swveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements. When a Surveillance with a Frequency based not on time intervals, but upon specified facility conditions or operational situations, is discovered not to have been performed when specified, SR 3.0.3 allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the Surveillance.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3.

is a flexibility which is not intended to be used as a convenience to extend Survst!!ance intervals.

(continued)

Millstone Unit No.1 B 3.0-3 l

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SR Applicability B 3.0 i

l B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SR 3.0.3 (continued)

If a Surveillance is not completed within the allowable delay period, then the variable is considered outsido the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. K a Surveillance is failed within the delay period, then the variable is outside the specified limits-ar:d the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.

Millstone Unit No.1 B 3.0-4

r Fuel Storage Pool Water Level B 3.1 B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level BASES BACKGROUND The minimum water level in the fuel storage pool provides shielding during the movemerit of irradiated fuel and minimizes the general area dose.

I A general description of the fuel storage pool design and the fuel storage pool cooling and purification system is given in the FSAR.

The assumptions of the fuel handling accident are given in the FSAR.

APPLICABLE With the permanent cessation of operations, the limiting fuel SAFETY handling accident (i.e., fuel assembly drop onto the top of ANALYSIS the core during fuel handling operations) is no longer part of the plant's design basis. However, several fuel handling accidents in the fuel storage pool are still possible.

Several fuel handling events, dropping of equipment onto irradiated fuel and fuel storage racks in the fuel storage pool were analyzed. These included dropping the following:

Fuel pool gate drop New fuel assembly Irradiated fuel assembly items such as filters, boxes, and pumps e

The analysis of these existing scenarios has determined that the limiting event is the drop of the fuel pool gate, which can result in extensive damage of the fuel assemblies, showing a total of 54 ruptured fuel rods. The drop of a new or irradiated fuel assembly did not result in the rupture of any fuel rods.

(continued) j 1

Millstone Unit No.1 B 3.1-1

1 Fuel Storage Pool Water Level B 3.1 B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level BASES APPLICABLE A bounding calculation of the radiological consequences of a SAFETY fuel handling accident in the spent fuel pool was performed, ANALYSIS -

based on the following:

(continued)

Actual source term - three years of decay time Failure of four assemblies - 248 fuel rods for 8x8 assemblies e

Unfilte.ed ground release - no credit for secondary containment e

or standby gas ireatment The results of this analysis demonstrate: 1) calculated doses at the exclusion area boundary and the low population zone are within 10CFR100 limits; 2) calculated doses to the Unit 1 and Unit 2 Control Rooms are within the limits specified in GDC-19, and 3) results are significantly less than the fuel handling accident over the core that was the design basis fuel handling accident prior to cessation of operations.

LCO The fuel storage pool water level is required to be greater than or equal to 33 feet.

The specified water level preserves the assumptions of the fuel handling accident analysis and provides shielding to minimize the general area does when irradiated fuel is being moved.

As such, it is the minimum level required for movement of irradiated fuel within the storage pool.

Applicability This LCO applies whenever irradiated fuel assemblies are stored in the fuel storage pool.

(continued)

Millstone Unit No. ',

B 3.1-2

Fuel Storage Pool Water Level B 3.1 B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level BASES ACTIONS A.1 When the initial conditions for an accident cannot be met, steps i

should be taken to preclude the accident from occurring. When the fuel storage pool level is lower than the required level, fuel handling activities should be suspended immediately.

This effectively precludes a fuel handling accident from occurring. This does not preclude movement of a fuel assembly to a safe position.

AL2 This action is intended to iestore the fuel storage pool level as soon as possible to minimize the time that the initial assumptions of the accident analysis are not being met.

SURVEILLANCE SR 3.1.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident and to provide shielding to minimize the general area dose during the movement of irradiated fuel. The water level in the fuel storage pool must be checked periodically.

The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on engineering judgement and is considered adequate in view of the large volume of water in the pool. Water level changes are controlled by facility procedures and significant unplanned level changes are unlikely based on operating experience.

i Millstone Unit No.1 B 3.1-3

Reactor Building Crane Operability B 3.2 l

B 3.2 SPENT FUEL HANDLING B 3.2.1 Reactor Building Crane Operability BASES BACKGROUND The purpose of this specification is to preclude the possibility of dropping a spent fuel cask over irradiated fuel in the fuel storage pool.

A description of the Reactor Building crane design improvements was provided by NNECO to the NRC on June 29, 1973. The modification improvements were described as a " Cask Drop Prevention System." By letter dated December 30,1975, the NRC informed NNECO that the proposed improvements were acceptable. However, the NRC also requested NNECO to submit proposed Technical Specifications to assure safe operation and continued surveillance of the Reactor Building crane.

NNECO submitted the proposed Technical Specifications on April 1,1976, and the NRC approved new Technical Specifications, including the

" Crane Operability" LCO, as Amendment 27 to License No. DPR-21.

APPLICABLE Tho ' Cask Drop Prevention System" utilizes a redundant hoist SAFETY system rated at 110 tons for the main hoist. This redundant ANALYSIS system ensures that a load will not be dropped for all postulated credible single-component failures. The range of component failure

)

examined extends over the total load path from the cask trunnions through the cask lifting yoke and redundant hoist system to the crane bridge structure. In addition, once the crane is set into the cask handling mode, its travel over the fuel pool will be limited to the cask storage area of the spent fuel pool.

The operability requirements of the Reactor Building crane ensure that all redundant features of the crane have been adequately inspected.

Spent fuel cask drop over irradiated fuel in the fuel storage pool is precluded by these features as well as the features described in LCO and Surveillance Requirement 3.2.2 of these Technical Specifications.

(continued) i Millstone Unit 14o.1 B 3.2-1 i

i.

Reactor Building Crane Operability B 3.2 B 3.2 CPENT FUEL HANDLING B 3.2.1 Reactor Building Crane Operability BASES LCO The Reactor Building crane is required to ODERABLE.

The operability is established by:

. a visual inspection of the crane cables, sheaves, book, yoke, and cask lifting trunnions, conducting no-load mechanical and electrical tests to verify e

proper operation of crane controls, brakes and lifting speeds, conducting a load test by lifting an ampty cask out of the pivot e

cradle.

Maintaining the Reactor Building crane OPERABLE preserves the assumption of preventing a cask drop accident.

Applicability This LCO applies whenever the Reactor Building crane is used for handling of a spent fuel cask, ACTIONS A.1 When the operability requirements for the Reactor Building crane cannot be met, steps should be taken to preclude a Spent Fuel Cask drop accident from occurring. Fuel cask handling activities should be suspended immediately and the load placed in a safe condition. This will effectively preclude a spent fuel cask drop accident from occurring.

SURVEILLANCE SR 3.2.1 REQUIREMENTS This SR verifies operability of the Reactor Building crane and ensures that the redundant features of the crane have been adequately inspected. The redundant hoist system ensures that a load will not be dropped for all postulated credible single-component failures.

The Frequency is appropriate because operability is required to be established before Spent Fuel Cask handling operations commence.

(continued)

Millstone Unit No.1 B 3.2-2

Reactor Building Crane Travel with a Spent Fuel Cask B 3.2 B 3.2 SPENT FUEL HANDLING B 3.2.2 Reactor Building Crane Travel with a Spent Fuel Cask BASES BACKGROUND The purpose of this specification is to preclude the possibility of dropping a spent fuel cask over irradiated fuel in the fuel storage pool. The Reactor Building crane has a 2-pca. ion mode switch which is designed to restrict crane motion, when in " Mode 2," as follows:

It prevents a spent fuel cask height above the refueling floor not greater than 6 inches, and

)

It establishes a predetermined path which specifically excludes j

the area above irradiated fuel by interlocks and limit switches.

This specification, in conjunction with LCO 3.2.1, ensures that a fuel cask drop over irradiated fuel in the fuel storage pool is prevented from occurring.

APPLICABLE The " Cask Drop Prevention System" features a single-failure proof SAFETY design that prevents a spent fuel cask drop over the fuel storage ANALYSIS Pool with resultant damage to irradiated fuel and/or plant equipment and structures. Once the Reactor Building crane mode switch is set into the cask handling mode, its travel over the fuel storage pool will be limited to the cask storage area of the fuel pool. This design feature as well as associated crane interlocks and limit switches ensure that a spent fuel cask drop will not occur over the irradiated fuel in the fuel storage pool.

An event initiated by a spent fuel cask drop over the irradiated fuel in the fuel storage pool is precluded by these features as well as the features described in LCO and Surveillance Requirement 3.2.1 of these Technical Specifications.

(continued)

Millstone Unit No.1 B 3.2-3

Reactor Building Crans Travel with a Spent Fuel Cask B 3.2 B 3.2 SPENT FUEL HANDLING B 3.2.2 Reactor Building Crane Travel with a Spent Fuel Cask BASES LCO The Reactor Building crane mode switch is required to in the

" Mode 2" position with its key removed. This mode switch position is an engineered control which restricts crane travel to a path which excludes the area above the irradiated fuel in the fuel storage pool. Also, the height of a spent fuel usk loaded on the crane is restricted to a height of no greater than 6 inches above the refueling floor.

Maintaining the Reactor Building crane mode switch, associated crane limit switches, and interlocks preserves the assumption of preventing a cask drop accident.

Applicability This LCO applies whenever the Reactor Bui; ding crane is used for handling of a spent fuel cask.

ACTIONS A.1 When mode switch requirements for the Reactor Building crane cannot be met, steps should be taken to preclude a spent fuel cask drop accident from occurring. Fuel cask handling activities should be suspended immediately and the load placed in a safe condition.

This will effectively preclude a spent fuel cask drop accident from occurring.

SURVEILLANCE SR 3.2.2 REQUIREMENTS This SR demonstrates operability of the Reactor Building crane interlocks and limit switches which restricts the height of the crane load (i.e., the spent fuel cask bottom) to no more than 6 inches above the refueling floor and restricts crane path from traveling over the irradiated fuel assemblies. The Frequency is appropriate I

because operability is established before spent fuel cask handling operations start and operability is periodically assured during spent fuel cask handling.

Millstone Unit No.1 B 3.2-4

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