Text

Proposed Tech Specs Re Permanently Defueled Status of Plant
	ML20212A621
Person / Time
Site:	Maine Yankee
Issue date:	10/20/1997
From:	; Maine Yankee
To:	;
Shared Package
ML20212A610	List: ML20212A602; ML20212A621;
References
	NUDOCS 9710240091
	Download: ML20212A621 (56)
	v • d • e

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Technical Specifications Maine Yankee Nuclear Plant Specifications s

la "iB8 u 31s8880, W PDR

- TABLE OF CONTENTS SPECIFICATIONS TABLE OF CONTENTS 1.0 USE AND APPLICATION 1.1 De fin i t h n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 1 1.2 Logical Connectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 1.3 Completion Times . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -4 1.4 F re q u e n cy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -7 2.0 S AF ETY LI M ITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY . . . . . . . 3-1 SURVEILLANCE REQUIREMENT APPLICABILITY . . . . . , . . . , . . . . . . . . , 3-2 3.1 DEFUELED SYSTEMS 3.1.1 Fuel Storage Pool Water Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 3.1.2 Fuel Storage Pool Boron Concentration . . . . . . . . . . . . . . . . . . . . . . . 3-4 4.0 D E SIG N FEATU RES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2- O rg a nizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 5.3 Unit Staff Qualifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-0 5.4 - Tra i n i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7 5.5 P roced u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-8 5.6 Prog ra ms a nd M a n u als . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-9 5.7 Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . 5-15 5.8 High Radiation Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 .

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Dsfinitions 1.1 1.0 USE AND APPLICATlON 1.1 Definitions.

............................................ NOTE...........................................

The defined terms of this section appearin capitalized type and are applicable

, i lh[ou,gho,g!,t,h,es,e ,T,eg,h,nipa!,Specifgagns,an,d, .. Bases,. ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,.

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

CERTIFIED FUEL HANDLER A CERTIFIED FUEL HANDLER is an individual who compits with provisions of the ~

CERTIFIED FUEL HANDLER training program required by Technical Specification 5.4.1, i

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s_ _ _ _ _ _ _ _ . _ _ _ _ - . _ _ _

Logical Conn:ctors 1.2

, 1,0 USE AND APPLICATION i

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 may appear in TS are AMR and OB. 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 oflogic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

If 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.

(continued)

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Logic 21 Connectors 1.2 1.2 Loalcal Connectors (continued)

E.MMPLES . The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 --

ACTIONS f CONDITION REQUIRED ACTION COMPLETIO.1 TIME A. LCO not met. A.1 Verify . . .

AND A.2 Restore . . .

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

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME f A. LCO not met. A.1 Trip . . .

RB A.2.1 Verify . . .

AND A.2.2 Reduce . . .

This example represents a more complicated use e' logical connectors. Required Actions A.1, and A.2 are cuernative choices, only one of which must be performed as indicated by the use of the logical connector DB 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 ANQ.

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Compl: tion 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 (LCO's) specify minimum requirements for ensuring the safe storage of irradiated fuel.

The ACTIONS associated with an.LCO state Conditions that typically describe the ways in which the requirements of the :,

LCO can fall 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 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. 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 l- until the Condition no longer exists or the facility is not within l the LCO Applicability.

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions.

. (continued)

Maine Yankee 1-4

Compittion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-1 l (continued)

ACTIONS CONDITION REQUIRED COMPLETION TIME ACTION A. Required A.1 Verify . . . 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated ANQ Completion Time not met. A.2 Rostore . . . 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 enterea.

The Required Actions of Condition A are to perform the verification required by ACTION A.1 within e hours AND to perform the restoration required by ACTION A.2 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hourc 's allowed for performing ACTION A.1 and a total of 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months )is allowed for performing ACTION A.2 from the time that Cond! tion A was entered if ACTION A.1 is completed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the tinie allowed for completing ACTION A.2 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for completing -

ACTION A.2 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

,_. (continued)

. Maine Yankee 15

Compl3 tion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3 2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO limit A.1 Verify . . . 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceeded.

M 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter M

A.2 Restore . . . 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time for Required Action A.2 also begins at the time the Condition is entered and runs concurrently.

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

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Fr;qu:ncy 1.4 1.0 USE AND APPLICATION 1.4 Frequency I PURPOSE The puraose of this section is to define the proper use and applicat on of Frequency requirements.

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"is 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.

l EXAMPLES The following exemples Illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown)is when irradiated fuelis stored in the spent fuel pool.

(continued) -

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. o

Frequ::ncy 1.4 l

-1.4 Frecuency EXAMPLES EXAMPLE 1.41 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

Verify parameter is within limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l Example 1,41 contains the type of SR most often encountered in the Technical Spec!fications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational fluxibility.

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 facility is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility 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)

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Fr:qutncy 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4 2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify parameter is within limits. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to moving irradiated fuel AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter l

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 "ANQ" indicates that both Frequency requirements must be met. The use of " prior to" I indicates that the surveillance mt:ct bo performed once before the l initiation of fuel handling activities. This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2. "Thereafter" indicates future performances inust 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).

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l SLs 2.0 2.0 SAFETY LIMITS (SLs) l This section is not applicable to defueled facilities.

4 1

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LCO Applic-bility ,

3.0 l

l 3.0 LIMITING COND; TION FOR OPERATION (LCO) APPLICABILITY

...... ._- ......_.. ..... _ .. - - . _ . . - - _ . _ . - . . . ~ . . _ . - - . . _ . . . . . . . . . _ . . . . . - . . . _ _ . - . . . . . . . . . . . . _ - . . . .

LCO 3.0.1 LCO's shall be met during the specified conditions in the Applicability, except as provided in LCO .'i.0.2.

LCO 3.0.2 Upon discovery of a 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), completion of the Required Action (s) is not required unless otherwise stated.

e

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SR Applicability 3,0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRn shall be met during specified conditions in the Applicability for individual LCO's, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between perfonnances 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 b::ve to be performed on inoperable equipment or variables outside specified limits.

l 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever, is less. This delay period is permitted to I allow performance of the Surveillance, if the Surveillance is not performed within the delay period, the I

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.

Maine Yankee 3-2

_ _ . = = == = -

Full Stortga Pool Wat:r Lcycl 3.1.1 1

{ 3.1 DEFUELED SYSTEMS l 3.1.1 Fuel Storage Pool Water Level LCO 3.1.1 The fuel storage pool water level shall be 2 23 ft over the top of 2

Irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel storage pool.

I*

ACTIONS i CONDITION REQUIRED ACTION COMPLETION TIME i

A. Fuel Storage pool water- A.1 Suspend movement of immediately level not within limit. Irradiated fuel assemblies in the fuel storage pool.

l SURVEILLANCE REQUIREMENTS

. SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify the fuel storage pool water level is 2 23 ft above 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the top of irradiated fuel assemblies seated in the storage

, racks.

i I

i i

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i Maine Yankee 3-3

0. . : _ ..-. . . - . - - _ - . . - . . - . .. ..L. -- --:

Fu:1 Stor:ga Pool Boron Concentrction 3.1.2 3.1 DEFUELED SYSTEMS 3.1.2 Fuel Storage Pool Boron Concentration LCO 3.1.2 The fuel storage pool boron concentration shall be > 1000 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool A.1 Suspend movement of fuel Immediately boron concentration not assemblies in the fuel within limit. storage pool.

ANQ A.2.1 Initiate action to restore fuel Immediately storage pcol boron concentration to within limit.

QB A.2.2 Initiate action to perform a Immediately fuel storage pool verification.

1 (Continued) l Maine Yankee 3-4 m

Fuel Storage Pool Boron Concentration 3.1.2 SURVEILLANCE REQUIREMENTS ,

SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify the fuel riorage pool boron concentration is Prior to movement within limit, of fuelif not performed within the past 7 days.

AND 7 days thereafter Maine Yankee 3-5

Design Features -

! 4.0 4.0 DESIGN FEATURES E4.1 Site-4.1.1. Site Descriotion The facility shall be located on property owned by Maine Yankee Atomic Power Company on and surrounding Bailey Point in the Town of Wiscasset, Lincoln County, Maine._.

The minimum distance to the boundary of the exclusion area, as defined in 10CFR100.3, shall be 2000 feet.

4 Maine Yankee 4 _ _ _ . _ _

Design Features 4.0 4.0 DESIGN FEATURES 4.2 Fuel Storage 4.2.1 Criticality 4.2.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U 235 enrichment of 4.5 weight percent;

b. k, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in the FSAR

c. A nominal 9.085 inch center to center distance between fuel assemblies placed in Region ll racks;

d. A nominal 10.5 inch center to center distance between fuel assemblies placed in Region I racks; 4.2.2 Drainage The fuel storage poolis designed and shall be maintained to prevent inadvertent draining of the pool below elevation 40 ft.

4.2.3 Capacity

a. No more than 2019 fuel assemblies shall be storc d in the fuel storage pool. These assemblies will be stored in either Region I or i

Region ll of the fuel storage pool in accordance with the limitations of Figure 4.1-1. Unirradiated fuel assemblies shall be stored in either the New Fuel Storage Area or Region I of the fuel storage pool. Consolidated fuel shall be stored in Region ll only,

b. No more than 20 standard fuel assemblies may be in consolidated form. These are included in the 2019 fuel assemblies of specification a.

l l

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r D: sign Fe tur:s 4.0 40 35 S

$ 30 .

B z b

25 g-2 5 20 Region I or Region ll Storage l2 l g_

15 -

~.D E

10 -

E ReOlon i Storage Only 5 ,

0 i i i 1 2 3 4 5 Nominal Initial Enrichment (235 U Wolght Percent)

Spent Fuel Pool Assembly Placement Limitations Maine Yankee 43 Figure 4.1-1

Rssponsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The Plant Manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect the safe storage of irradiated fuel.

5.1.2 The Shift Manager on site shall be responsible for the command function.

5.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles as provided in Regulatory Guide 1.8 - 1975 and/or ANSI N18.1 - 1971. Plant specific, Maine Yankee titles for the functions and responsibilities associated with these generic titles are identified in the FSAR and/or QA program.

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Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 General Organizational Reaulroments Unit organizations shall be established for the unit operation and support management, respectively. The organizations shallinclude the positions for activities affecting the safe storage of irradiated fuel,

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediato levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsiollities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR or QA program;

b. The Plant Manager shall have overall responsibility for the unit and shall have control over those onsite activities necessary for maintenance and storage of irradiated fuel in a safe condition;

c. The President 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; and

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

(continued)

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OrganizCtion 5.2 5.2 Oraanization (continued) 5.2.2 Unit Staff The facility staff organization shall include the following:

a. Each on duty shift shall be composed of at least the minimum shift etew composition shown in Table 5.2.21.

b. At least_one person qualified to stand watch in the control room (non-certified operator or CERTIFIED FUEL HANDLER) shall be present in the control room when irradiated fuel is stored in the fuel storage pool,

c. All fuel handling operations shall be directly supervised by a CERTIFIED FUEL HANDLER.

e. 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 (e.g., CERTIFIED FUEL HANDLERS, non-certified operators, radiation protection personnel, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The baseline for determining overtime use will be a 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week. However, in the event that unforeseen problems require substantial amounts of overtime to be used; or during major maintenance or modifications (including decommissioning activities) the following guidelines shall be followed on a temporary basis:

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

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 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 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shift tumover time; (continued) 1 Maine Yankee 5-3

Organization 5.2 5.2 Oraanization 5.2.2 UnRStaff (continued) ;

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 use of overtime should be considered on an Individual basis i and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the Plant Manager or his dealgnee, in accordance with established procedures and with documentation of the basis for grant!ng the deviation.

Routine deviation from the above guidelines is not authorized,

f. The Shift Manager shall be a CERTIFIED FUEL HANDLER.'

g. The Shift Managers shall report to an individual who is a CERTIFIED FUEL HANDLER.

h 4

4 5-4

OrgInization 5.2 Table 5.2.2-1 Minimum Shift CrevcComoosition*

Position Minimum Crew Number Shift Manager i non-cedified operator 1 Total 2

(*)

The shift crew composition may be one less than the minimum requirements of 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 provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 5.2.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crew member being late or absent.

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Maine Yankee 5-5 l

_._,,,-.r ~---. , .,..,m.,- 4,-my, , , , _

,,..g ,, .-,r,. ,.m.. m - .. ,y.,- . . , , - -

. - . . . --.y_ -

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unlt_ Staff Oualificat1,on_s 1

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8 - September 1975 for comparable positions unless otherwise noted in the Technical Specifications.

Maine Yankee 5-6

Trcining 5.4 5.0 ADMINISTRATIVE CON TROLS 5.4 - Trainina 5.4.1 A NRC approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained under the direction of the Plant Mana';er or his desigr.se.

l 57

F Procedurcs 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures 5.5.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The procedures applicable to the safe storage of irradiated fuel recommended in Regulatory Guide 1.33 Revision 2, Appendix A, February 1978;

b. Emergency plan implementation; -

d. Quality assurance for radiological effluent and environmental monitoring;

e. Fire Protection Program implementation; and

f. All programs specified in Specification 5.6.

5-8

Programs and Menuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals The following programs shall be established, implemented, and maintair ed. -

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

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 resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; 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 Specification 5.7.2 and Specification 5.7.3.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. Sufficierit information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s);

(continued) 5-9

Programs, and Manuals 5.6 5.0 Programs, and Manuals 5.6.2 Offsite Dose Calculation Manual (ODCM)(continued)

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 1, and not adversely impact the accura::y or reliability of effluent, doso, or setpoint calculations;

b. Shall become effective after approval of the Plant Manager or designeo; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM es 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 affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.6.3 Radioactive Effluent Controls Proaram This program conforms to 10 CFR 50.36a for the control of radioactive eifluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program 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 shallinclude the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrum6ntation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; (continued) 5-10

Programs, and M:nucls 5.6 5.6 Programs, and Manuals 5.6.3 Radioactive Effluent Controls Program (continued)

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 CFR 20, Appendix B; Table 2, Column 2;

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

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid 2

effluents release from the unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

, e. Determination of cumulative dose contributions from radioactive 4

effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the 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 of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resultin0 from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table 2, Column 1;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; (continued) 5-11

_ _ . _ . - ~ _~ __ __ _ __ _. _ _ . - _ . _ . _ , _ _ . .

Programs, end MCnuals i 5.6 5.6 Programs, and Manuals 5.6,3 Radioactive Effluent Controls Proaram (continued)

1. Limitations on the annual and quarterly doses to a member of the public from tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and 0

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

/ continued) 2 4

r i

5-12

Programs, cnd Manu Is 5.6 5.6 Programs, and Manuals 5.6.4 Technical Soecifications (TS) Bases Control Prograrn 1 his program provides a means for processing changes to the Bases of these Technical Specifications,

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

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

A change in the TS incorporated in the license; or A change tu the updated FSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

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

d. Proposed changes that meet the criteria of 5.6.4.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented witnout prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

(continued) 5-13 p

i .

Programs, and Manuals 5.6

. 5.6 Programs, and Manuals 5.6.5 InaQIYlce Testina Program This program provides controls for Inservice testing of ASME Code Class 1,2, and 3 components including applicable supports. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda as follows:

- ASME Boller and Pressure Vessel Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Weekly At least once per 7 days Monthly At leact once per 31 days Quarterly or every 3 months At least once per 92 days i Semlannually or every

6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days 4

Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activiCes; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS, L

1 3

5-14

,,...,..,.,....c__... _

, ,, . ~ _ , , ,, _ _ , _ . , . . . , _ , . , _ . . , . ,

R:: porting R:quircm:nts 5.7 5.0 ADMINISTRATIVE CONTROLS L

5.7 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.7.1 Occupationt' Badiation Exoosure Reoort A tabulatica on an annual bcsis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performer' receiving an annual deep dose equivalent > 100 mrem /yr and tu assodated collective deep dose equivalent (reported in pr -

according to work and job functions (e.g., fuel handling, < "r-routine maintenancc, special maintenance [ describe.ms -

' .i sod waste processing). This tabulation supplements the req, ..ents of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on oocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totaling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from extemal sources shculd be assigned to specific major work functions. The report shall be submitted by April 30 of each year.

5.7.2 Annual Radiological Environmental Ooerating Reoort The Arqual Radiological Environmental Operating Report cover:ng the unit activities during the previous calendar year shall be submitted by May 15 of each year. TGe report shal! include summaries, interpretations, and analyses of trends of'.he results of the radiological en'/ironmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offs!te Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix 1, Sections IV.B.2, IV.B.3, ar,d IV.C.

(continued) 5-15 3 - i

< Rnporting Requiremsnts 5.7

^

5.7 Reportina Requirements 5.7.2 ' Annual Radioloalcal Environmental Ooeratina Reoort (continued)

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 pursuant to the locations specified in tne table and figures in the ODCM, as well as summarized and tabulated. results of these analyses and measurements.

In the ever't that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.7.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the as'ivities of the unit in the previous year shall oe sul;mitted prior to May 1 of each year in L accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste -

released from the unit. The material provided shMI be consistent with the i

objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5-16

m. .. ..- . . - - - . - - . . . . .

High R:diation Area 5.8 5.8 High Radiation Area l

5.8.1 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 whlch the intensity of radiation is > 100 mrem /hr but < 1000 mrem /hr, 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 (RWP). Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 51000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual cr 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 inat continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that contir.uously integrates the radiation dose rate in the area and alarms when a preset integrated dose is roccived. Entry into siich aress with this monitoring device may be made after the dose rate lews in the area have been established and personnel are sware of them.

c. An individual qualified in radiat!r.n protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by Radiation Protection in the RWP.

(continued) x 5-17

l High Redistion Arsa 5.8 i

5.8 High Radiation Area (continued) 5.8.2 in addition to the requirements of Specification 5.8.1, each high radiation area, as defined in 10 CFR 20, with radiation levels > 1000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrativo control of the Shitt Manager on duty or radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation prctection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 For individual high radiation areas, as defined in 10 CFR 20, with radiation levels of > 1000 mrem /hr, 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 constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

a 5-18

ATTAC}NENT IV PROPOSED CHANGE NO. 207 ,

i Maine Yankee Proposed Technical Specification Buis 1

u m

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Technical Specifications Maine Yankee Nuclear Plant Bases l " l2.M

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. . igg gi i q Inside Cover

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TABLE OF CONTENTS BASES

-TABLE OF CONTENTS B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY , . . . . B 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY . . . . . . . . . . . . . B 3.0-3 <.

B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3.1-1 B 3.1.2 Fuel Storage Pool Boron Concentration . . . . . . . . . . . . . . . . . . . . . . B 3.1-4 I

d 4

Maino Yankee i

LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCO's LCO 3.0.1 and 3.0.2 establish the 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 feciPty is in the s ecified 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 coint in time that an ACTIONS Condition is entered. The Required Actions establish those remedia! measures that must be taken within specified Completion Times when the rec uirements of an LCO a.e not met. This Specification establishes tlat:

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 loncjer applicable, unless otherwise stated in the individual Specifications.

(continued)

Maine Yankee B 3.0-1

LCO Applicability B 3.0 BASES LCO 3.0.2 The Completion Times of the Required Actions are also (continued) applicable vi'len a specified condition in the Ap,plicability 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 the safo storage of irradiated fuel.

Intentional entry into ACTIONS should not be made for convenience.

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, Maine Yankee B 3.0-2

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

S R 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 specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. i 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 to SR 3.0.2 are stated in the individual Specifications.

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

(continued) 4 Maine 'i ankee B 3.0-3

SR Applicability B 3.0 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 aeriod of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months applies from the point in time that it is discoverec; that the Surveillance has not been per'ormed in accordance with SR 3.0.2, and not at the time that the specified Frequency 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 cor.ditions, adequate olanning, availabilit,y of personnel, the time required to perform the Surveilance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of i any particular Surveillance being performed is tha verification of conformance with the requirements. When a Surveillance with a l 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Surveillance intervals.

(mntinua i

Maine Yankee B 3.0-4

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SR Applicability B 3.0 BASES SR 3.0.3 If a Surveillance is not completed within the allowed delay period, then the (continued) variable is considered outside the specified lirr.its and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay penod. If a Surveillance is failed within the delay period, then the variable is outside the specified limits and the Completion Times of the Required Actions for the a failure of the Surveillance.pplicable LCO Conditions begin immediately upon the 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.

l Maine Yankee 8 3.0-5

Fu:1 Stor:gs Pool Wattr Lcval B 3.1.1 B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level BASES l

BACKGROUND The minimum wate. ;evel in the fuel storage pool meets the assumptions of lodine decantamination factors followinc a fuel handling accident. The specified water level provides slielding during the movement of spent fuel and minimizes the general area dose.

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

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

APPLICABLE - The Maine Yankee facility is permanently shutdown and the time SAFETY ANALYSES since the last operation of the reactor has allowed significant decay of fission 3roducts (especially the daughter products with short half-lives) conlained in the spant fuel. The spent fuel pool water level is adequate to provide necessary shielding for the fuel handlers to minimize occupational dose during normal spent fuel handling

. activities.

The existing accident analysis for the fuel handling accident, ac described in the FSAR, assumes two cases. The first case is the realistic case where the accident is assumed to occur one week after shutdown from operations and a decontamination factor for lodine of 500. The second case is the conservative case where the accident is assumed to occur seventy-two hours after shutdown from operations and a decontamination factor of 133 for inorganic iodine and a decontamination factor of 1 for organic lodine. For the purpose of establishing an upper limit on the amount of fuel damage resulting from a fuel handling accident. it is assumed that the fuel assemb y is dropped during handling. The number of ruptured fuel rods which would result depends on several variables including the kinetic energy at impact and fuel assembly orientation during impact.

The existing analyses indicate that if a fuel assembly were dropped to the bottom of the fuel storage pool and then rotated and struck a 3rotruding structure, only the outer row of fuel rods would fail.

-iowever, to assure that the limiting case is considered, it is assumed that all rods in the dropped assembly fail upon impact.

The resulting doses which are calculated for the fuel hundling accident are below the values specified in 10CFR100.

(continued)

Maine Yankee B 3.1-1

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Fuel Storage Pool Water Level l B 3.1.1 BASES l

APPLICABLE The normal o aerating water level of the fuel storage pool is SAFETY ANALYSES established al approximately 36.5 feet above the floor of the pool.

The Technical Specification value of 23 feet over the top of

' (continued) irradiated fuel assemblies seated in the storage racks is satisfied by 36.5 feet of water above the fuel storage pool floor. The to)of the ,

fuel assembly is defined as the bottom of the flow late, whica ls the top of the fuel rods. In the case of a fuel assembl dropped to the bottom of the fuel storage pool and standing uprig ,36.5 feet of water above tho floor of the fuel storage pool provides more than 23 feet of water for lodine decontamination, in the case of a fuel assembly dropped and lying horizontally on top of the spent fuel racks, however, there may be less than 23 feet of water above the top of the bundle and the surface. To offset this nonconservatism, the analysis assumes that all fuel rods fail, although only the first row of fuel rods would likely fail.

LCO The fuel storage pool water level is required to be > 23 ft over the top of irradiated fuel assemblies seated in the storage racks. The specified water level preserves the assumptions of the fuel handling accident analysis anc! providas shielding to minimize the area dos 6 when irradiated f Jelis being moved. As itsuch, is the general minimum level required for uovement of irradiated fuel within the fuel storage pool.

APPLICABILITY This LCO applies whenever irradiated fuel assemblies are being moved in the spent fuel pool, since the potential for a release of fission aroducts exists and increased water level shielding is needec.

ACTIONS Al When the initial conditions for an accident cannot be met, stops should be taken to preclude the accident from occurring. When the spent fuel pool water level is lower than the required level, the movement of irradiated fuel assemblies in the spent fuel pool is immediately suspended. This effectively precludes a spent fuel handling accident from occurring. This does not preclude movement of a fuel assembly to a safe position.

(Continued)

Maine Yankee B 3.1-2 l

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Fuel Storage Pool Water Lovel B 3.1.1 BASES SURVEILLANCE SR 3.1.1.1 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 spent fuel pool must be checked periodically when moving fuel. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency is appropriate because the volume in the pool is normally stable.

Water level changes are controlled by facility procedures and are acceptable, based on operating experience 1

l Maine Yankee B 3.1-3 o

Fuel Storage Pool Boron Concentration B 3.1.2

)

B 3.1 DEFUELED SYSTEMS B 3.1.2 Fuel Storage Pool Baron Concentration BASES BACKGROUND The water in the fuel storage pool normally contains soluble boron, which results in large subcriticality margins under normal conditions.

However, the design of the fuel storage pool is based on the use of unborated water, which maintains a subcritical condition (k with the spent fuel racks fully loaded in accordance with C Niky 5 0.95) guidance.

APPLICABLE The analyses performed to evaluate the effects of a postulated SAFETY ANALYSES misplacement of an fuel assembly assumes the presence of soluble boron in the fuel storage pool water. The negative reactivity effect of the soluble boron compensates for any increased reactivity caused by postulated accident scenarios. This analysis value for boron concentration of 663 ppm provides 5%Ak/k safety margin to criticality. As additional operating margin the fuel storage pool boron concentration will be maintained at equal to or greater than 1000 ppm whenever this LCO applies.

As described in Figure 4.1.1, " Fuel Storage Pool Assembly Placement Limitations", fuel assemblies are stored in the spent fuel racks in accordance with criteria based on initial enrichment and discharge burnu.a. Although the water in the fuel storage poolis normally boratec: to >1000 p 3m, the criteria that limit the storage of a fuel assembly to specific rac( locations is conservatively devefoped without taking credit for boron. The fuel assembly misplacement accident scenario is associated with the misplacement of an fuel assembly during fuel handling opemtions. This could potentially increase the Keff of the fuel storage pool. To mitigate the reactivity increase due to such a' postulated accident, boron is dissolved in the pool water. The double contingency principle discussed in ANSI N16.1-1975 and the April 1978 NRC letter allows credit for soluble boron under abnormal or accident conditions, s nce only a single accident need be considered at one time.

(continued)

Maine Yankee B 3.1-4

Fuel Storage Pool Boron Concentration B 3.1.2 I

BASES LCO The fuel storage pool boron concentration is required to be > 1000 ppm when the LCO applies. The specified concentration of dissolved boron in the fuel storage pool preserves the assumptions used in I.he analyses of a potential criticality accident resulting from the misplacement of an fuel assembly in the fuel storage pool. This concentration of dissolved boron is the minimum rec uired concentration when fuel assemblies are stored in the

_ fuel storage poo anc' a pool verification has not been performed.

APPLICABILITY This LCO a pplies whenever fuel assemblies are stored in the spent fuel pool and a tuel pool verification has not been preformed since the last movement of fuel assemblies in the s 3ent fuel pool. This LCO does not apply following the verification since tie verification would confirm that there are no misplaced fuel assemblies. This verification includes a demonstration that fuel assemblies are properly located in the correct fuel storage rack in accordance with Figure 4.1.1 and that there are no fuel assemblies outside of or on top of the fuel storage racks. With no further fuel assembly movements in progress, there is no potential for a misplaced or a dropped fuel assembly.

l ACTIONS A.1. A.2 and A.3 When the concentration of boron in the fuel storage pool is less than required, immediate action must be taken to preclude an accident from happening or to miti ate the consec uences of an accident in progress.

This is most efficien achieved by mmediately suspending tle movement of fuel assemblies. is does not preclude movement of a fuel assembly or load to a safe position, in addition, action must be immediately initiated to restore boron concentration to within limit. Altemately, beginning a verification of the fuel storage locations, to ensure proper ocations of the fuel can be performed.

SURVEILLANCE SR 3.1.2.1 REQUIREMENTS This SR verifies that the concentration of boron in the fuel storage pool is within the required limit during the movement of fuel assemblies. As long as this SR is met, the analyzed accidents are fully addressed. The 7 day Frequency is appropriate because no major replenishment of pool water which could result in a dilution of the boron concentration is expected to take place over a shor period of time.

Maine Yankee B 3.1-5

ATTACHMENT.y PROPOSED CHANGE NO. 207 l l

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Haine Yankee Requirements Replacing PORC/NSARC Review To Be Relocated to the Quality Assurance Program

)

ADMINISTRATIVE CONTROLS Reviews and Audits

1. Indeo3ndent Safety Reviews Independent Safety Reviews shall be a thorough review by a qualified Independent Safety Reviewer. Persons perforaing these reviews shall be knowledgeab'e in the subject area being reviewed. These independent Safety Reviews are completed prior to implementation of proposed activities.

1.1 Composition

[ 1.1.1 Reviewers Independent safety reviewers shall be en individual not having direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual or group performing the original work.

1.1.2 Qualifications The Independent Safety Reviewers shall h" ' five years of professional level 3xperience and either a Bachelor i Degree in Engineering or the Physical sciences or equivalent in accordance with ANSI /ANS-3.1 1981.

The Chairman of the Independent Review and Audit Committee shall designate the Independent Safety Reviewers in writing.

1.1.3 Respons1bilities The following subjects shall be independently reviewed by a qualified Independent Safety Reviewer:

a. Safety evaluations for (1) changes to equipment or systems and (2) tests or experiments completed under the provisions of 10CFR50.59 to verify -

that-such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equtoment or system which involve an unreviewed safety question as defined in 10CFR50.59.

c. Approval of the review of the Offsite Dose Calculation Manual and its implementing procedures and ensuring that recommended changes are submitted to the Plant Manager,

d. Approval of the review of the Process Contral Program and its implementi g procedures and ensuring that recommended changes are submitted to tne Plant Manager.

e. Approval of the review of the Fire Protection Program and implementing procedures and ensuring that recommended changes are submitted to the Chairman of the Independent Review and Audit Committee.

f. Proposed changes to the Technical Specification Bases.

V1

2. Indeoendent Review and Audit Committee

-The Independent Review and Audit Committee (IRAC) is responsible for reviewing and advising the Plant Manager on matters relating to safe storage of fuel.

This review and audit function is independent of the line organization responsibilities.

2.- 1 Composition 2.1.1 The IRAC shail be composed of a minimum of 5 members. Alternates may be substituted for regular members. The Plant Mar.ager shall designate in writing the chairman, the members and alternates for the IRAC. The chairman shall not have management responsibilities for, or report to, the hne organizations responsible for the storage, control or monitoring of fuel.

2.1.2 The IRAC shall collectively have experience and knowledge in the following functional areas:

1. Storage control and monitoring of fuel.

2. Chemistry and Radiochemistry

3. Engineering

4. Radiation Protection

5. Quality Assurance '

2.1.3 . Meeting Frequency The IRAC shall hcid meetings as required, with 6t least one meeting per-quarter.

2.1.4 Ouorum ,

A_ quorum shall consist of 3 regular members or duly appointed alternates.

Those members representing the line organizations responsible for the storage, control and monitoring of fuel shall not constitute a majority of the quorum.

At least one member of the cuorum shall be the chairman or the chairman's designated alternate.

2.2 Review Responsibilities The IRAC shall be responsible for the review of:

a. The safety evaluation for (1) changes to equipment or systems and (2) tests or experiments completed under the provisions of 10CFR50.59 to verify that-such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10CFR50.59.

c. -Proposed tests or experiments which involve an unreviewed safety question as defined in 10CFR50.59.

9 Proposed changes to Technical Specifications or this Operating License.

e. Violations of codes, regulations, orders. Technical Specifications, license requirenents, or of internal procedures or instructions having nuclear safety significance.

V2

f. Significant operating abnormalities or deviations from normal and l . expected performance of plant equipment that 3ffect nuclear safety.

g .- All reportable events.

h. Perform special reviews and investigations and render reports thereon as

requested by the President. Maine Yankee or his designated alternate.

i, Significant accidental, unplanned, or uncontrolled radioactive releans, j- including corrective action to prevent recorrence.

2.3 Audit Responsibilities Audits of facility activities shall be performed under the cognizance of the

! IRAC.

These audits shall encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 24 months.

b. The performance, training and qualification.of those members of the facility staff who have a direct relationship to the storage, control and monitoring of fuel at least once per 24 months.

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of storage, control or monitoring of fuel at least once per 6 months.

-d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix ~B" 10 CFR 50, at least once per 24 months.

4

e. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

f. An independent fire protection and loss prevention inspection and audit <

shall be performed at least once_ per 12 months utilizing either qualified offsite licensee personnel or.an outside fire protection firm.

g. The Offsite Dose Calculation Manuals and its implementing procedures at least once per 24 months.

h, The Process Control Program and its implementing procedures at least once per 24 months.

i. Any other area of facility activities considered appropriate by the IRAC or the President. Maine Yankee.

Reports or records of these audits, including any recomendations for. improving the safe storage, control or monitoring of fuel, shall be forwarded to the Plant Manager within 30 days following completion of the audit.

i V3 i

ML20212A621

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