ML20126E760

Permanently Defueled Tech Specs

ML20126E760
Person / Time
Site:	Yankee Rowe
Issue date:	12/21/1992
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20126E749	List: ML20126E746 ML20126E760
References
NUDOCS 9212290306
Download: ML20126E760 (49)

Text

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-ATTACHMENT C YANKEE NUCLEAR POWER STATION =

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS R12\80 9212290306 921221 PDR

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INDEX-1 DEFINITIONS-SECTION 'PAGE~

1.0 DEFINITIONS

_ACT!0N.-.................................................. 1-1 CHANNEL CALIBRATION........... .......................... 1 l'

' CHANNEL CHECK................................. ........... ~1 CHANNEL FUNCTIONAL TEST.................................. il-1' MEMBER (S) 0F-THE PUBLIC.................................. 1-1 0FF-SITE DOSE CALCULATION MANUAL (0DCM).................. 1-2 OPERABLE 0PERABILITY..... ............................ 1-2 PROCEFS CONTROL PROGRAM (PCP)......................... . ... 2 REPORTABLE EVENT.......................................... 2 SITE B0VNDARY............................................. 142 l

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b INDEX LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE $ -

SECTION PAGE 3/4.0 APPLICABILITY.......................................... 3/4-1 3/4.1 SPENT FUEL PIT WATER' LEVEL.............................

3/4 2-3/4.2 CRANE TRAVEL SPENT FUEL PIT.........................-. 3/4 3 3/4.3 SPENT FUEL STORAGE AREA RADIATION MONITOR.............. '3/415 3/4.4 LIQUID HOLD-UP TANKS................................... 3/4 6 3/4.5 SEALED SOURCE CONTAMINATION............................. 3/4-7 -!

BASES SECTION PAGE -

3/4,0 APPLICABILITY.......................................... 'B3/4 21-3/4.1  : SPENT FUEL-PIT WATER LEVEL............................. .

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3/4.2 CRANE TRAVEL'- SPENT. FUEL PIT........i...............,.- -B3/4-4 3/4.3 83/4 ~

SPENT FUEL-STORAGE AREA RADIATION MONITOR.............

3/4.4 L I QU I D H O L D - U P TA N KS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B3/4 3/4.5 SEALED SOURCE: CON'TAMINATION...................,........ B3/427:

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area.... .. ................................. . 5-1 5.2 FUEL STORAGE Criticality. ... ......................... .. ... .... 5-1 Drainage.. ....... ....... ............................ 5-1 Capacity......... ...... .... .................. ........ 5-1 YANKEE-ROWE iii R12\90

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- :I INDEX-ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY........................................... ;6  !

6.2 ORGANIZATION -

On-Site and Off-Site Organization.......,,................. 61 Facility Staff........................................... 2' 6.3 FACILITY STAFF 0VALIFICATIONS............................ 6-5.

6.4 TRAINING................................................. 6 '

6.5' REVIEW AND AUDIT Plant Operation Review Committee Function........................................... 6 Composition........................... ............ 65-Alternates......................................... 6-5 Meeting frequency.................................. 6-6 0uorum.... ...................-..................... 66 Responsibil_ities................................... 6 Authority.......................................... 6 Records......................................,..... 6 Nuclear Safety' Audit and Review Committee-L Function........................................... +6-8 Composition........................................ 6-8' Qualification...................................... 68 Alternates......................................... 6-9 Consultants........................................ 9

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INDEX ADMINISTRATIVE CONTROLS (continued)?

s SECTI'ON . PAGE'.

6.5 REVIEW AND AUDIT (continued) ,.,

Nuclear Safety Audit and Review Committee (continued)

Meeting-Frequency.................................. f6 9 0uorum............................................. 6 9; Er Rev1ew............................................. 6 10 Audits............................................. 6-11 Authority.......................................... 12-Records............................................ 6 12 6.6 REPORTABLE. EVENT ACTION.................................. 6 13; .

6.7 PROCEDURES AND PR0 GRAMS.................................. .6-13 6.8 REPORTING REQUIREMENTS A n n u a l R e p o r t . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . , 6-16 Unique Reporting Requirements ........................... 6-17l _

Special-Reports =.......................... ............... . '6-17' 6.9 RECORD RETENT10N......................................... 6 18-6.10 RADIATION' PROTECTION PR0 GRAM............................. 6-19 6.11 HIGH RADIATION AREA,..................................... 6-20 6.12 PROCESS CONTROL PROGRAM (PCP)............................ 6 21 6.13 0FF-SITE-DOSE CALCULATION MANUAL-(0DCM).................. 6-22:

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1.0 DEFINITIONS The defined terms of this section appear in capitalized type-and are applicable throughout these Technical Specifications. 4 ACTION 1.1 ACTION shall be those additional requirements specified as corollary statements to each principle specification and-shall be part1of the-specifications.

CHANNEL CAllBRATION 1.2 A CHANNEL' CALIBRATION shall be the adjustment, as necessary, of-the channel output such that it responds with the necessary range and accuracy to known -values of the parameter which the. channel monitors. The CHANNEL CAllBRATION'shall encompass the entire channel including the alarm'and/or trip functions, and shall include-the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by 'any series of sequential, overlapping or total-channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.3 A CHANNEL CHECK shall be-the qualitative assessment of channel behavior during operation by observation. This determination shall e include, where possible, comparison of the channel indication'and/or status-with other. indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.4 A CHANNEL FUNCTIONAL TEST shall be the injection-of a simulated signal into the channel as-close to the primary sensor.as.

practicable to verify OPERABILITY including' alarm -and/or' trip functions.

MEMBER (S) 0F THE PUBLIC 1.5' MEMBER (S) 0F THE PUBLIC shall include;all' persons'who are not occupationally associated. with the plant. .This category does not

' include employees.of'the utility, its contractors, or vendors. Also

-excluded from this category.are persons who enter-the site to. .

service equipment or to make deliveries. This' category does include persons who -use portions of the site for recreational, occupational or other purposes.

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1.0 DEFINITIONS'(Continued) - '

OFF-SITE DOSE CALCULATION MANUAL (ODCM) 1.6- The OFF-SITE DOSE CALCULATION MANUAL (ODCH) contains- the methodology -

and parameters used in the calc'ulation of off* site doses resulting

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from radioactive. gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in' .

the conduct of the Environmental' Radiological Monitoring Program.

The ODCH also.contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by: ._

Section 61.d. .and-(2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports. required by Specifications 6.8.2.a and 6.8.2.b.

OPERABLE - OPERABillTY 1.7 - A system subsystem, train, . component or- device shall- be OPERABLE or ~

have OPERABILITY when it is capable of performing its specified safety function (s). Implicit in thisiefinition shall be the assumption that all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or; other auxiliary equipment that are required for the system, ' subsystem, train, component or device to' perform its safety function (s) are also capable of. performing their necessary support function (s).

PROCESS CONTROL PROGRAM (PCP) 1.8 -The-PROCESS CONTROL PROGRAM contains the current formulas,Lsampling, analyses.. test, and determinations.to be made to ensure-that -

, ' processing and packaging of solideradioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10- CFR Parts 20, 61, and ~ 71, state regulations, burial ground requirements, and other requirements, governing the. disposal of1 solid. radioactive waste.

REPORTABLE EVENT-1.9' A REPORTABLE' EVENT shall be any of those conditions specified .in 10

-CFR 50.73.

l SITE BOUNDARY 1.-10 .The SITE BOUNDARY shall-be that line beyond which the land is..not owned, leased, or otherwise controlled by the licensee. Any area

.within the SITE BOUNDARY used for residential quarters or -

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j 1.0 DEFINITIONS (Continued) --

recreational purposes shall be considered to be..beyond the;-SITE.

BOUNDARY for purposes of meeting gaseout. effluent dose specifications. (Realistic occupancy factors.shall be Applied at

.these locations for the purposes of dose calculations.)

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' 3/4.0 APPLICABILITY =

LIMITING CONDITION FOR OPERATION l

.i 3.0.1 Limiting Conditions for Operation and-ACTION requirements-shall be  !

applicable during the specified applicable condition for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of- the specified time interval . completion of the ACTION -

statement is not required.

3.0.3 Entry into specified applicability conditions shall not be made unless the_ conditions of the Limitin1 Condition for Operation are; met without reliance on provisions c ,ntained in the ACTION statements unless otherwise excepted.

SURVEILLANCE REQUIREMENTS

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4.0.1 Surveillance Requirements shall be applicable during the specified ,

applicable conditions for individual Limiting Conditions- for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within'the-

-specified surveillance-interval with a maximum allowable extension-not to exceed 25% of the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall-~ constitute' compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

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L 4.0.4 Entry into a specified applicable condition -.shall not-be made unless the Surveillance Requirement (s) associated with-the Limiting L Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. .

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4 3/4,I ' SPENT FUEL PIT WATER-LEVEL -j LIMITING CONDITION FOR OPERATION 3.1.1 At least 14 feet of water shall be maintained over the top ofL -

Irradiated fuel assemblies seated in the storage _ racks. ,

3.1.2 At least 5 feet of water shall be maintained over the top of' I irradiated fuel assemblies while the fuei: assemblies' are not seated in the storage racks.  ;

APPL!CABILITYi Whenever irradiated fuel assemblies are in the spent fuel pit.

ACTION: _

With the requirements of the specification not satisfied, place-irradiated components in a safe condition and suspend fuel.

handling operations within~the spent-fuel pit and crane-. '

operations with loads over the spent fuel ~ pit. Restore water level to within its limit within 4' hours. ,

SURVEILLANCE REQUIREMEliTS NA -

__.. 92p4t. --.. - . _M 4.1.1 The water level in the spent fuel pit shall; be determined to be' at least its minimum required depth at_least once per 7_ days '

when irradiated fuel assemblies are-in the': spent fuel pit'.

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3/4.2--CRANE TRAVEL - SPENT FUEL PIT LIMITING CONDITION FOR OPERATION 3.2 Loads in excess of-900 pounds shall be prohibited from travel- -

over the spent fuel pit except for the:

a. Spent Fuel Storage Building roof hatches,

b. Spent fuel inspection stand,

c. Fuel handling- equipment, >

d. Spent fuel racks,

e. Temporary gate,

f. Shielding panels,

g. Shipping cask liners,

h. Volume reduction-equipment, _ ,

1. Snipping casks: 35 tons maximum gross weight not for spent fuel . and J. Spent fuel. assembly nondestructive test equipment, ,

APPLICABILITY: With fuel essomblies in the Spent Fuel Pit.

ACTION:

With the requirements of the_above specifications;not satisf'ied, place the crane load in a safe condition. .

SURVEILLANCE REQUIREMENTS 4.2.1 Loads in excess of' 900 pounds shall be prevented -f rom traveling-:

over the spent fuel pit by administrative control.. except ;that : ,

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a. Spent Fuel Sto,' age Building roof-hatches, the'spentifuel inspection stand, the fuel- handl.ing equipment. spent fuel 3 racks,'the' temporary. gate, the shielding panels, the' spent  ;

fuel assembly nondestructive test' equipment, the volume -

reduction' equipment,'the shipping cask liners, and-the shipping casks (35. tons maximum gross weight - not for spent fuel) may travel over. the spent . fuel p'it in accordance with approved- written- procedures:

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3/4.2 CRANE TRAVEL SPENT FUEL P]T SURVEILLANCE REQUIREMENTS (Continued)

b. The spent fuel inspection stand, the temporary gate, the shielding panels, the spent fuel assembly nondestructive test equipment, and the cask hatch cover shall be prevented f rom traveling over fuel assemblies in the spent fuel pit by administrative control. The volume reduction equipment, the shipping cask liners, and the shipping casks shall be prevented from traveling over fuel assembliee in the spent fuel pit by administrative control and by the steel framing _

at the southern edge of the spent fuel pit superstructure roof opening which is also at the southern end of the safe load path; and

c. Fuel handling equipment, when moved for maintenance, shall be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control .

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. ~ j 3/4.3 SPENT FUEL STORAGE AREA ~ RADIATION HONITOR j

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LIMITING CONDITION FOR-0PERATION-

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3.3 Radiation levels-in the spent fuel storage area shall _ be monitored by a' fixed _ radiation monitor with Lan audible alarm set at <5 mr/hr or 2 times background, whichever is greater.-

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< APPLICABILITY: When handling irradiatedLfuel, control' rods:or' sources. 1 ACTION:

With fixed radiation _ monitoring equipment inoperable, place irradiated components in a safe condition and suspend all fael handling operations within the spent fuel pit'and. crane-operations with loads over the spent fuel pit until the monitor-is returned to OPERABLE status.

$URVEILLANCE REQUIREMENTS 4.3.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, perform a CHANNEL CHECK, 4.3.2 At least once per 31 days,_ perform a' CHANNEL FUNCTIONAL TEST.

i 4.3.3 At least once per 18 months, perform a CHANNEL CALIBRATION.-

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3/4.4 LIQUID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside tank that is not surrounded by liners, dikes'or walls capable ~of holding the' tank contents, or that_does not have a tank-overflow.

connected to the liquid radwaste treatment system, shall be limited to less-than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases APPLICABILITY: At all times. 4 ACTION:

With the quantity of radioactive' material in any outside tank-

_ exceeding the above limit, without delay.-take action to'. suspend all additions of radioactive material to.the tank. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank' contents to within the limit and describe the events leading to-this condition in the next Semiannual Radioactive Effluent Release Report,- pursuant to Specification 6.8.2.b, j

SURVEILLANCE REQUIREMENTS 4.4.1 The-quantity of radioactive material contained in any outside.

tank that is not surrounded by liners, dikes, or walls capable of' holding the~ tank contents shall be determined to be within the above limit by analyzing a representative sample _of.the_ tank's  !

contents at least.once per 7 days when radioactive materials are being added to the tank, l

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3/4.5 SEALE0' SOURCE CONTAMINATION LIMITING CONDITION-FOR OPERATION 3.5 Each sealed source containing radioactive material' either= in .

excess of 100 microcuries of beta and/or' gamma emitting material or 5 microcuries of alpha emitting material shall be free of 2 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

Each sealed source with removable contamination in excess of_:the-above limits shall be immediately withdrawn from use and:

Either decontaminated and repaired or 1.

2. Disposed of in'accordance with Commission Regulations.

SURVEILLANCE REQUIREMENTS 4.5.1 Test Requirements Each of the above required sealed sources shall be tested for leakage and/or contamination-by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at leastl  ?

0.005 microcuries per test -sample.

4.5.2 Test Freauencies - Each category of the above required sealed-sources shall be tested at the frequency described below.

a. Sources in use (excluding.startup. sources and fission detectors previously subjected to core flux) - At least once

--per 6 months for all sealed sources containing radioactive-materials:

1. With a. half-life' greater than 30 days-(excluding Hydrogen 3).-and

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2. In any form other than gas.

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3/4.5 SEALED SOURCE CONTAMINATION SURVEILLANCE REQUIREMENTS (Continued)  ;

4.5.2 (Continued)

b. Stored sources not in use - Each sealed source shall be '

tested prior to use or' transfer to another licensee unless:

tested within the previous-.6 months. -

Sealed-sources '

transferred without a certificate indicating the last test date shall be-tested prior .to being placed .into use.

4.5.3 Reports - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.3 annually if sealed source leakage tests reveal' the presence ~ of greater _ than _

0.005 microcuries of removable contamination.

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• i BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-FOR THE-DEFUELED TECHNICAL SPECIFICATIONS NOTE The BASES contained -in the succeeding pages summarize the reasons for the Specifications in Section 3/4, but in accordance with 10 CFR 50.36, are not part of these .

Technical Specifications.

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3/4.0 APPLICABillTY BASES

, The specifications of this sectior provide the general--requirements applicable to each of the Limiting Conditions for Operation and  :

Surveillance Requirements within Section 3/4.  ;

3.0.1 This specification defines the applicability of each specification' in terms of specified Applicability conditions and is provided_to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition of Operation-and associated ACTION requirement, 3.0.3 This specification provides that entry into a specified Applicability condition must be made with'(a) the full complement of required systems, equipment and components OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met-without regard for allowable deviations and out of service provisions contained in the ACTION statements.

The intent of this provision is to ensure that activities are not initiated with either required equipment or systems inoperable or.other_

specified limits being exceeded, 1

4.0.1 This specification establishes the requirement that_surveillances must be performed during the specified applicable conditions for which the requirements of the Limiting Conditions for Operation _ apply Lunless otherwise stated in an individual Surveillance Requirement. The purpose =

of this specification is to ensure that surveillances are' performed toL verify the operational status of systems and components and that parameters are within specified limits to ensure-safe operation'of;the-facility- when the plant is in a specified Applicability condition.

Surveillance Requirements do not_have to1 be performed when the facility is in- a condition for which the requirements of the: associated Limiting

, Condition for Operation do not- apply unless otherwise specified.

4.0.2 This specification establishes the limit for which the specified-time interval for Surveillance Requirements may be extended. .It permits an allowable extension of the normal surveillance -interval to _f acilitate surveillance scheduling and consideration of plant operating conditions that may not- be suitable for conducting the surveillance: e.g.,_

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3/4.0 APPLICABILITY BASES (Continued) as a convenience to extend the surveillance intervals beyond that specified. The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained f rom the specified surveillance interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the -

Limiting Conditions for Operation. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into specified Applicability conditions. The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.

Under terms of this specification, the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.

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3/4.1 SPENT FUEL PIT WATER LEVEL {

BASES

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The restriction of 14 feet of water -cover for irradiated fuel- assemblies seated in storage racks ensures that sufficient water depth is available to remove.98% of the approximately 30% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is-consistent with the assumptions of the accident analysis.

The restriction of 5 feet of water cover for irradiated-fuel assemblies not seated in the storage racks ensures that the exposure to personnel in the spent fuel pit area during fuel movements will be maintained ALARA.

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3/4.2 CRANE TRAVEL-- SPENT:FVEL PIT BASES' The restriction on movement of loads -in excess of the nominal weight of a fuel assembly over fuel assemblies' in the spent fuel pit ensures that in the event this load is dropped (1) the ' activity release'will. be-limited to _that contained in a single fuel assembly, and (2) any possible distortion of the fuel in the storage racks will not result-in a critical array. This assumption is consistent with the activity.

release assumed-in the_ accident analysis.

Handling of the present Spent Fuel Storage Building roof. hatches under.

administrative control will assure safe handling of the roof -hatches.

The restriction of' movement of the spent fuel inspection stand,-the temporary gate, the shielding panels the spent fuel assembly nondestructive test equipment, the cask hatch cover, the volume reduction equipment,-the shipping cask liners, and the shipping casks over spent = fuel ensures.that these items cannot be dropped on spent fuel. Dropping any one of these items'from its maximum height will not:

result-in loss of integrity of the spent fuel pit-floor. Handling of-the fuel handling equipment for infrequent maintenance under administrative control will ensure the safe handling of any. fuel handling. components, r

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I 3/4.3- SPENT FUEL STORAGE AREA RADIATION MONITOR:

BASES-Operability requirements for the Spent Fuel Storage Area Radiation. .

Monitor-satisfy 10 CFR 70.24.

• Criticality- Accident Requirements," which -

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mandates the need for a Radiation Monitoring System in'any area containing'special nuclear material in excess of certain specified amounts. Using radiation detection equipment that can activate tn audible alarm signal in the' spent fuel storage area ensures early .

notification of excessively high radiation is.provided to_ individuals.

• involved in fuel handling-operations or other _ activities in the Spent Fuel Storage Building.

The intent of Specification 3/4.3 is to protect plant-personne1' and!

ensure public health and safety' by requiring a Radiation Monitoring System to be OPERABLE when irradiated fuel -assemblies, control rods, and sources in the Spent Fuel Pit are moved. Inoperable fixed radiation monitoring equipment requires action to restore fixed radiation-monitoring' equipment to OPERABLE status.

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y 3/4.4 L10VID' HOLD-UP TANKS BASES Restricting the quantity of radioactive material 1 contained in the outdoor tanks provides assurance that in the event of an uncontrolled

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release of the tank's contents, the resulting concentration at_the.

nearest potable water supply and the nearest' surf ace water supply in. an-unrestricted ' area would be less than the limits of 10 CFR 20, <

Appendix B. Table -II, Column 2. The limit applies to each tank.

individually.

Tanks included in this Specification are those outdoor tanks that contain radioactive liquid, are not surrounded by liners, dikes, or -.

walls capable of holding'the tank contents, or do not have tank overflows and surrounding area. drains connected to a liquid radwaste treatment. system.

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T 3/4.5- SEALED SOURCE CONTAMINATION BASES-The limitation on removable contamination for sources requiring' leak' testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure.that . leakage from by-product, source, and_special nuclear material sources will not exceed .

allowable intake values. Sealed sources are classified into three groups according to their use with surveillance requirements commensurate with the probabilitylof damage.to a source in that group.

Those sources which'are frequently handled are required to be t'ested more often than those which are-not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e.,-sealed sources:

within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the-shielded mechanism.

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5.0 DESIGN FEATURES  ;

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5.1 SITE ,

EXCLUSION AREA i 5.1.1 The exclusion area shall be as shown in Figure 5.1-1. [

5,P FUEL STORAGE CRITICAL.iTY  ;

i 5.2.1 The-spent fuel storage racks are designed and shall be -

maintained with a center to center distance between fuel _.

assemblies placed in the storage racks to ensure.a keff equivalent to 0.95 with the spent fuel storage areas-flooded with unborated water. The k of 0.95 includes a t conservativeallowanceof3%'kk/kforuncertainties.

DRAINAGE 5.2.2 The spent fuel pit is designed and shall be maintained to i prevent inadvertent draining of_the pit.

CAPACITY 5.2.3 The spent fuel pit is designed and shall be maintained with a .

storage capacity limited to no more than 721 fuel assemblies.

I y

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6.0 ADMINISTRATIVE CONTROLS Administrative controls are the written rules, orders, instructions, procedures, policies, practices. and the designation of-authorities and responsibilities by the management to obtain assurance of safety and quality of maintenance of a nuclear facility. These controls shall be adhered to.

6.1 RESPONSIBILITY 6.1.1 The Plant-Superintendent shall be responsible for overall facility operation and.shall delegate in writing the succession to this responsibility during his absence.- _

6.1.2 in all matters relating to the operation of the plant and to these Technical- Specifications, the Plant Superintendent - '

shall report to and be directly resoonsible to the Manager of Operations in the Yankee Atomic Elis tric Company. j 6.2 ORGAHlZATION 6.2.1 An on-site and an off site organization shall be established for plant operation and corporate management.. The on site and off site organization shall include the positions for activities affecting the safety of the facility, i

a. Lines of authority, responsibility and communication  !

shall be established and defined from the highest management levels through intermediate levels to and- .:

including all operating organization positions.- Those relationships shall be documented and updated, as appropriate, in the form of organizational charts. .These organizational charts shall be documented in the FSAR. ,

b. A single corporate of ficer shall have overall responsibility for plant nuclear safety. This individual a shall take any measures-needed to ensure acceptable-  !

performance of the staff in operating maintaining and providing technical support in the plant so that continued nuclear safety is assured.

c. 'There shall be-an individual management position in the' on-site organization having-overall responsibility-for e safe operation of the plant: he/she shall have' control.-

over those on site resources necessary for safe' operation  :

and. maintenance-of the plant, YANKEE-ROWE 6-1 UNO

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, = .- . .

6.0 ADMINISTRATIVE CONTROLS (Continued)-

d. Although the individuals who train the operating staff and those who carry out.the quality assurance functions may report to the appropriate manager they shall have sufficient organizational freedom to be independent from operating pressures,

e. Although radiation protection personnel may report to the appropriate manager on site, for matters relating to radiological health and safety of employees and the public, the radiation protection manager shall have' direct access to that on site individual _having overall responsibility for safe operation of the plant, Radiation protection personnel shall have.the authority to cease any work activity when worker radiological safety is jeopardized or in the event of' unnecessary-personnel radiation exposures.

6.2.2 The Facility organization shall be subject'to the followings

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

b. At least one individual qualified to: stand watch in the control room (an Equipment Operator or Certified fuel Handler) shall be in-the control room when fuel is in the spent f uel pit.

c, A qualified Radiation Protection individual shall:be:on-site during fuel handling operations,

d. An individual-qualified in radiation protection procedures shall be on site when; fuel is in the spent.

fuel pit. _0perating crew personnel _ trained in radiation protection procedures ~ fill this requirement.

e. All fuel handling operations shall be directly' supervised-by a Certified Fuel Handler who has no other concurrent.<

responsibilities during this' operation.

f. -Administrative _ procedures shall.be developed and-implemented to limit -the working hours of the unit staff who_ perform safety related functions e.g., the Minimum Shif t Crew required by Table .6.2-1. ' Mechanical, Electrical ~and Instrumentation.Technicidns and Radiation Protection Technicians.

4 YANKEE ROWE. 6+2 mm C-. . . _ . . . , _ . _ _ -. _ -.-._ _,--, u -.- - - ..,u.

. Al. .. .l

'I 6.0 ADMINISTRATIVE CONTROLS (Continued) ,

i Adequate shift coverage shall be maintained without I coutine heavy use of overtime. The objective shall be to ,

have operating personnel work, on the average, an  !

approximate 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week. However, in the event that l unforeseen problems require substantial amounts-of  ;

overtime to be used, or during major maintenance or major [

plant modifications, on a temporary basis, the following. ,'

guidelines shall be followed:

(1) An individual should not be permitted to work more

• than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time, ,

(2) An individual should not be permitted to work more-than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> _ period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period,-nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all. excluding shift turnover time. [

(3) A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods. including shif t turnover time.

(4) The use of overtime should be considered on'an-individual basis and not for the entire staff on

• shift.

Any deviation f rom the above guidelines shall be authorized by the Plant Superintendent or-his delegated-representative, or higher levels of management. in accordance with-established procedures and with .

s documentation of the basis for granting the deviation.  ;

Controls shall be reviewed monthly by the Plant-Superintendent or his delegated representative to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

b YANKEE ROWE 6-3 R72iBQ

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6.0 ADMINISTRATIVE CONTROLS (Continued)

TABLE 6.2 1 HINIMUM SHIFT CREW COMPOSITION #

POSITION NUMBER Of INDIVIDUALS REQUIRED TO flLL POSITIONS-CERTIFIED FUEL HANDLER 1* ~

EQUIPMENT OPERATOR 1

• Does not include the Certified Fuel Handler supervising-fuel handling.

1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2' hours in-order to accommodate unexpected absence of duty shift crew members provided immediate action is taken to. restore the shift crew composition to within-the minimum requirements of Table 6.2 1.

I YANKEE ROWE 64.

R7t\90

_...__.__.-._;.__._m..__. . - _ . _

e ~4 4 'e-l J

l 6.0 ADHlHISTRATIVE CONTROLS (Continued).

6.3 FACILITY STAFF OVAllFlCAT!0fi f j 6.3.1 Each member of the facility management / supervisory staff I shall meet or exceed the minimum qualifications of f ANS! 18.1 1971 for comparable positions, except for the l Radiation Protection Manager who shall also meet the minimum .;

qualifications of Regulatory Guide 1.8, Revision 1. ,

6.4 TRAINING 6.4.1 A retraining and replacement training program for the l i

facility Certified fuel Handlers shall be conducted in accordance with an NRC approved training program.- A. training program for the unit staff shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI-H18.1 1971. ,

6.5 REVIEW AND AUD!T ,

6.5.1 PLANT OPERATION REVIEW COMMi' TEE l FUNCTION t

6.5.1.1 The Plant Operation Review Committee (PORC) shall function to advise the Plant Superintendent on all matters related:to nuclear l safety.

' .l COMPOSITION 6.5.1.2 The PORC shall.be composed of a Chairman and a minimum ofs four management / supervisory staff members who are appointed, in writing, by the Plant Superintendent. ,

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by .the- Plant -

Superintendent to serve on a temporary basis; however, no more t than two alternates shall participate in PORC_. activities'at any--

one time for the purpose of establishing a quorum.

(

?

YANKEE-ROWE 6-5 F

1. 7t\90 1

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i 6.0 ADMINISTRATIVE CONTROLS (Continued) l HEET!NG FRE0VENCY 6.S.1.4 The PORC shall meet at least once per calendar month and as f convened by the PORC Chairman.  !

000 RUM 6.5.1.5 A quorum of the PORC shall consist of a majority of the members in Specification 6.5.1.2, including the Chairman.

RESPONS!Bil1 TIES -

6.5.1.6 The PORC shall be responsible for: [

a. Review of 1) all procedures required by Specification 6.7 and changes thereto, and 2) any other proposed procedures ,

or changes thereto as determined by the. Plant Superintendent to affect nuclear safety,

b. Review of all proposed tests and experiments that affect +

nuclear safety,

c. Review of all proposed changes to the Technical Specifications or License. t

d. Review of all proposed changes or modifications to plant p systems or equipment that affect nuclear safety.  ;

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to ,

prevent recurrence to the. Manager of 0perations and to .

the Chairman of the Nuclear Safety Audit-and Review  ;

Committee. -

f. Review of all REPORTAB'EL EVENTS.  ;

g. Review of facility operations to detect potential-nuclear  !

. safety hazards. .

h. Performance of special reviews, investigations of .

analysis and reports thereon as requested by the Chairman.

of the Nuclear Safety Audit and Review Committee .

i. Reviev of the Plant Defueled Security Plan and implementing procedures and changes' thereto. .;

'7 YANKEE-ROWE' 6-6 R7D80

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l I

6.0 ADMINISTRATIVE CONTROLS (Continued)

j. Review of the Defueled Emergency Plan and. implementing procedures-and changes thereto,

k. Review of every unplanned on site release of radioactive-  :

material to the environs including preparation of reports  !

covering evaluation, recommendations and disposition of -!

the corrective action to prevent recurrence and the-forwarding of-these reports to the Plant Superintendent and to the Nuclear Audit and Review Committee.

1. Review of changes'to the PROCESS CONTROL _ PROGRAM and-the 0FF SITE DOSE CALCULATION MANUAL.

m. Review of changes to the Fire Protection Program, j AUTHORITY 6.6.1.7 The PORC shall:

a. Recommend to the Plant Superintendent, written approval or disapproval of items considered under 6.5.1.6(a).

through (d) above,

b. Render determinations in writing with regard'to whether-or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the --i Manager of Operations of disagreement between the PORC and the Plant Superintendent: however, the Plant-Superintendent shall have responsibility forf resolution of such disagreements-pursuant to16.1.1 above.-

RECORDS i 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies.

shall be provided to the Manager of Operations and chairman of.the' '

Nuclear Safety Audit and-Review' Committee.

5 i

t YANKEE-ROWE 67 0 47t\90 --

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6.0 ADMINISTRATIVE CONTROLS (Continued) t 6.5.2 NUCLEAR SAFETY AUDIT AND REVIEW COMMITTEE t FUNCTION 6.6.2.1 The Nuclear Safety Audit and Review (NSAR) Committee shall {

function to provide independent review and audit of all aspects of plant safety. Adequacy of this review and audit is assured by-the cross section of disciplines required of the Committee membership I

as described in Section 6.5.2.3.

COMPOSITION 6.5.2.2 The NSAR Committee shall be composed of a Chairman and a minimum of four members who are appointed by the Manager of Operations. 1' NSAR Committee members shall not be members of the plant staff.

OUAllFICATION 6.5.2.3 Membership to the NSAR Committee requires that-an individual meet ,

one of the below academic and/or experience requirements: '

a. Bachelor Degree or equivalent, plus five (5) years total ~

experience-in the below listed disciplines. l

b. Nine (9) years total experience in the below listed discipline.: q (a) Nuclear Pcwer Plant Technology (b) Facility Operations (c) Power Plant = Design ,i (d) Engineering / Nuclear Engineering (e) Radiation Safety (f) Safety Analysis-(g) instrumentation and Control (h) Quality Assurance i

+

YANKEE-ROWE 68

. RF2tto - e

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. . . . , - ~ . - , , ~ . - , , - . . , -

6.0 - ADMINISTRATIVE CONTROLS (Continued) m_. .

ALTERNATES 6.5.2.4 All NSAR Committee alternate members shall be appointed in writing.

by the Hanager of Operations to serve on a temporary basis however no more than one alternate'shall participate in HSAR Committee activities at any one time for the purpose of establishing a quorum.

CONSULTANTS 6.5.2.5 Consultants may be utilized as determined by the NSAR Committee Chairman to provide expert advice, when needed, to the NSAR Committee.

HEETING FREQUENCY 6.5.2.6 The NSAR Committee shall meet at -least once per six months. +25%.

Special meetings may be held when_ deemed necessary by_ Company management or by the Chairman of the NSAR Committee.

OV0 RUM 6.5.2.7 A NSAR Committee quorum shall consist of a majority of the members in Specification 6.5.2.2. including the Chairman.

YANKEE-ROWE 6-9 nirin

6.0 ADMlHISTRATIVE CON 1ROLS_ (Continued) s ---

REVIEW 6.5.2.8 The NSAR Committee shall reviews

a. The safety evaluations for 1) changes to equipment or systems, and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to equipment-or systems which involve an unreviewed safety question as defined in 10 CFR:50.59. -

c. Proposed tests or experiments which involve an unreviewed safety question as def'ined in 10 CFR 50.59,

d. Proposed _ changes to Technical Specifications or the License 4

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

f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety, defined as Plant Information Reports,

g. All REPORTABLE EVENTS.

h. Reports and meeting = minutes of the PORC.-

1. Perform special reviews and investigations and render-reports thereon as requested by the Manager of Operations.

YANKEE-ROWE 6-10' 27t\t0

r

. -a: , .

i 6.0 ADMINISTRATIVE CONTROLS (Continued) ,

AUDIT 1 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NSAR Committee. These audits shall encompass: 3

a. The conformance of facility operation to provisions f contained within the Technicel Specifications and applicable license conditions at least once per 12 months, +25%.

b. The performance, training and qualifications of' those ,

members of the facility staff who have a-direct relationship to operation, maintenance or technical aspects of the plant, at least once per'12 months. +25%. +

c. The results of actidns taken to correct deficiencies I occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at-least.

once per 6 months, +25%.

d. The performance of activities required by the Operctional Quality Assurance Program to meet the criteria of Appendix 'B",10 CFR 50, at _least once per 24 months,

+25%.

+

e. The Facility Defueled Emergency Plan and implementing procedures at least once per 12 months. +25%.

f, The facility Defueled Security Plan and implementing procedures at least once'per 12 months, +25%.

g. The facility Fire _ Protection Program and implementing procedures at least once per 24 months._-+25%.

h. The radiological monitoring program and the results1  !

thereof at least once per 12 months, +25%,

i, The OFF-SITE DOSE CALCVLATION MANUAL' and implementing procedures at least once-per 24 months, +25%. -

j. .The PROCESS CONTROL PROGRAM'and implementing procedures ,

for-processing:and packaging of radioactive waste at least once per 24 months. +25%.

• l k. The performance of activities affecting quality as required by effluent.and-environmental monitoring.: .

procedures at least onceiper 12 months, +25%.

YANKEE-ROWE 6-11 RFbt0 1

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6.0 ADMlHISTRATIVE CONTROLS-(Continued)

1. Any other area of facility operatior considered appropriate by the NSAR Committee or the-Manager of Operations.

AUTHORITY 6.5.2.10 The NSAR Committee shall report to and advise the Manager of Oper6tions on those areas of responsibility specified in Section 6.5.2.8 and 6.5.2.9.

RECORDS -

6.5.2.11 Minutes of each NSAR Committee meeting shall be prepared and forwarded to the Manager of Operations and each member of the Committee-for review within 20 working days following each-meeting. The meeting minutes shall-include, where applicable, reports of reviews encompassed to' Section 6.5.2.8: and reports of audits encompassed by-Section 6.5.2.9. The review of the minutes shall be completed within 60 days of the date-of their distribution.

m YANKEE-ROWE 6-12~

' 91F\t0

6.0 ADMINISTRATIVE CONTROLS (Continued) 6,6 REPORTABLE EVENT ACTION-6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73, and.

b. Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSAR-Committee and the Manager of Operations.

fi 7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of Sections 5.2 through 5.2.9 and 5.3 of ANSI N18.7 1972 and Appendix 'A' of Regulatory Guide 1.33 Revision 2. except as provided in 6.7.2 and 6.7.3 below. The written procedures shall also cover the activities' relating-to:

a. Fire Protection Program implementation,

b. PROCESS CONTROL PROGFAM implementation.

c. 0FF-SITE DOSE CALCULATION MANUAL _ implementation.

d. Quality Assurance Program for effluent and environmental monitoring, using_the guidance in Regulatory Guide 1.21.

Revision 1, June 1974 and Regulatory Guide 4.1=,  ;

Revision 1, April 1975. u 6.7.2 Each procedure and administrative policy of 6.7.1 above, and changes thereto, shall be reviewed'by the Plant. Operations Review Committee and approved by_the Plant Superintendent prior to implementation and' reviewed periodically as set =

forth in administrative procedures.

6.7.3 Procedures-that have been developed as a result of changes defined in 10 CFR 50.59(a)(2) shall be independently' reviewed-to. verify that.the implementing actions do not constitute an-unreviewed safety question. Those-reviews shall be performed by Nuclear Service Division _ personnel having qualifications at least equivalent to those specified for NSAR Committee-membership 10.6.5.2.3. The' procedures shall be approved by the Manager of Operations.

YANKEE ROWE 6-13 A7t\80 e

.: 4- . .

6.0 ADMINISTRATIVE CONTROLS (Continued) 0.7.4 Temporary changes to procedures of 6.7.1 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 PORC and approved by the Plant Superintendent within 14' days of '

implementation, 6.7.5 The following programs shall be established, implemented, and- _

maintained:

a. Radioactive Effluent Controls Prooram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive ef fluents as low as reasonably achievable.

The program (1-) shall be contained in the ODCM,1(2) shall be implemented by operating procedures, and (3):shall include remedial actions to be taken whenever the program limit.s are exceeded. The program shall include the following elements;

1) Limitations on the operability of radioactive liquid and gaseous monitoring -instrumentation,.  ;

including surveillance tests and setpoint- '

determination in accordance with the methodology-in the ODCM;

2) Limitations on the. concentrations of radioactive-material released in-liquid effluents to UNRESTRICTED AREAS conforming-to ICLCFR,--Part 20

- Appendix B,- Table ll, . Column f 2:

~

3) Monitoring sampling, and analysis of radioactive" liquid, and gaseous effluents-in accordance with; 10 CFR 20.106 and with the methodology and-

-parameters in the ODCM; 4). Limitations on the annual and quarte'rly doses or dose-commitment to a MEMBER-0F-THE-PUBLIC from radioactive materials in liquid effluents released YANKEE ROWE 6-14 Rittt0

. ._ _. --s.

l, . . .

6.0 ADMINISTRATIVE CONTROLS (Continued) from each unit to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50:

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

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to -

ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2% of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR, Part 50.

7) Limitations on the dose rate resulting from radioactive material released in gaseous ef fluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR, Part 20 Appendix B. Table 11. Column 1;

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the 511E BOUNDARY conforming to Appendix 1 to 10 CFR, Part 50;

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine-131, Iodine-133.

tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from each unit to areas beyond the SITE B0UNDARY conforming to Appendix 1 to 10 CFR, Part 50;

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR, Part 190.

b. Radioloalcal Environmental Monitoring Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program YANKEE-ROWE 6-15 R?t\90

6.0 ADMINISTRATIVE CONTROLS (Continued) shall provide (1) representative measurements of-radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the Effluent Monitoring Program and rodeling of environmental exposure pathways. The program shall (1) be contained in the_ODCH: (2) confor2. to the guidance of Appendix 1 to 10 CFR, Part 50; and (3) include the following:

1) Monitoring, sampling, analysis .and reporting of radiation and radionuclides in the environment in-accordance with the methodology and parameters i_n-the ODCM,

2) A Land Use Census to ensure that changes in.the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials _in environmental sample matrices are-performed as part of the Quality Assurance Program'for environmental monitoring.

6.8 REPORTING REQUIREMENTS The- following identified reports shall be submitted pursuant to-10 CFR 50.4. The reporting requirements of 6.8.1, 6.8.2 and 6.8.3 are in accordance with Revision 4 of Regulatory-Guide 1 16, .

" Reporting of Operating Information - Appendix A Technical Specifications.'

6.8.1 Annual-Report ' Annual reports covering the-activities of the unit as described below for the previous year shall be.

submitted prior to March 1 of each year.

Reports required on an annual basis-shall include:

a. A tabulation on an annual basis of the number of- station.-

utility and other personnel (including contractors) receiving 1 exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job f unctions. (a ) .e.g.. operations and surveillance.

inservice. inspection;_ routine maintenance, special maintenance (describe maintenance). and waste processing.-

. YANKEE *ROWE 6-16

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i 6.0 ADMINISTRATIVE CONTROLS (Continued) ,

The dose assignment to various duty functions may be estimates based on pocket-dosimeter, TLD, or film badge measurements. Small exposures totalling less then 20% of .

the individual total dose need not be accounted for, in the aggregate, at least 80% of the whole body dose

~

received from external sources shall- be assigned to  :

specific major work functions.

b. Any other unit unique reports- required on an annual basis.

6.8.2 Uniave Reportino Reauirements a.- Environmental Radiological Monitoring The Annual Radiological- Environmental Operating Report covering the operation of the unit during.the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1)-the'0DCM, and (2) Sections IV.B.2, IV,B,3, and !V.C of Appendix I to 10 CFR 50,

b. Semiannual Radioactive Effluent Release Report The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the' previous-six months of operation shall be submitted-within 60 days af ter January 1 and July 1 of each year. The report shall include a summary of-the-quantities of radioactiv~e liquid and gaseous effluents'and solid waste released from the unit. .The material provided shallEbe1(1)-

consistent with the objectives outlined in the.0DCM and.

PCP. and (2) in conformance with 10 CFR 50.36a and-Section IV.B.1 of Appendix I to 10 CFR-50.

6.8.3 Special Reports Special reports shall-be' submitted. pursuant ~

to 10 CFR 50.4 within the time' period specified for each.

report. These-reports shell be submitted covering the activities _identif_ied below pursuant _to the requirements.of' the applicable reference specification:

YANKEE-ROWE 6 17 R12\to

~ 4;. .-

i t

6.0 ADHINISTRATIVE CONTROLS (Continued) r

a. Sealed Source leakage in excess of limits, _

l Specification 3.5.

6.9 RECORD RETENTION 6.9.1 The following records shall be retained for at least 5 years:

a. Records and logs of facility operation covering time interval at each power level. >

r

b. Records and logs of principal maintenance activities.-

inspection, repair and replacement of principal items of equipment related to nuclear safety.  ;

c. All REPORTABLE EVENT reports submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

i

e. Records of reactor tests and experiments.

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments, v

h. Records of sealed source leak tests and results.

i Records of. annual physical inventory of all sealed source material of record.

6.9.2 The.following records shall be retained for the duration of the Possession Only License: ,

a. Records ~and drawing changes reflecting facility design -

modifications made to systems and equipment described in the FSAR. ,

r

b. Records of new and irradiated fuel' inventory. fuel.

transfers and assembly'burnup histories.

c. Records of facility radiation and contamination surveys. I

d. Records'of radiation exposure for all individuals entering radiation control areas.

Records of gaseous and liquid radioactive material e.

released to the environs . .

YANKEE-ROWE 6-18

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6.0 ADMINISTRATIVE CONTROLS (Continued) -l

-r 6.9.2 (continued)

f. Records of transient or operational cycles for_the  ;

Reactor Pressure Vessel.-  ;

g. Records of training and qualification for-current members

• of the plant staff.

h. Records of inservice inspections performed pursuant to Technical Specifications,

i. Records of Quality Assurance _ activities required by the ,

OA manual.

j. Records of reviews performed for changes mcde to i procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PORC and NSAR Committee'._

l. Records for Environmental Qualification,

m. Records of analysis required by the Radiological.

Environmental Monitoring Program. f

n. Records of the service lives of all snubbers, including .

the date at- which the service life commences and associated installation and maintenance records.

o. Records of reviews performed for changes made to the OFF--

SITE DOSE CALCULATION MANUAL and the PROCESS CONTROL. j PROGRAM. 1 6.10 RADIATION PROTECTION PROGRAM 6.10,1 Procedures for personnel radiation protect' ion shall be prepared consistent with requirementslof 10 CFR Part 20 and shall1be. _

f, approved, maintained 'and adhered to for'all operations involvingf  ;

personnel radiation exposures, ik b

YANKEE ROWE- 6 19

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6.0 ADMINISTRATIVE CONTROLS.(Continued) 6.11 HIGH RADIATION AREA 6.11.1 Paragraph 20.203 ' Caution Signs, Labels, Signals, and Controls.*

In lieu of the

• control device

• or

• alarm signal' required by Paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be. barricaded and conspicuously posted as a high radiction area, and-entrance thereto shall be controlled by requiring issuance of a Radiation  ;

Work Permit (RWP).

• r An individual or group of individuals permitted to enter such I areas shall be provided with one or more of the following- l l

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

l,

b. A radiation monitoring device which continuously . l integrates the radiation dose rate in the area,-and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may.be made  !

after the dose rate level in-the area has been - l established and personnel have been made knowledgeable of them.

c. A Radiation Protection qualified individual (i.e.,

qualified in radiation protection procedures), with a  ;

radiation dose rate monitoring device, who is responsible i for providing positive control over the> activities within '

the area and who will perform radiation surveillance at the frequency specified in the RWP. The surveillance frequency will be established by the Radiation Protection Manager.

The above procedure shall also apply to each.high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In. addition, locked doors shall be provided to _

prevent unauthorized entry into such areas and the keyLshall .i

be maintained under the administrative control of ~ the Shif t  !

- Supervisor on duty and/or the Radiation-Protection Manager.

Radiation Protection. personnel shall be exempt from the RWP. _

issuance requirement during the performance of.their assigned radiation protection duties. providing they are following plant  ;

radiation protection. procedures;for entry into high radiation areas, ,

YANKEE ROWE- 6-20 Uhto '

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6.0 ADMllilSTRATIVE C0ti1ROLS (Continued)

, _ ~ .

6.12 PPOCLS$ C0tiTP0t PROGRAM (PCP) 6.12,1 Changes to the PCP:

a. Shall be documented and records of reviews performed shall be ru. tined as required by Specification 6.9.2.0.

This documentution shall contain:

1) Suffa ~e ' kfOrmatton to support the change togethe with the appropriate analyses or eve sation justifying the change (s), and -

2) ni iation that the change will maintain the it conformance of the solidified waste iuct to existing requirements of federal, tate, or other applicable regulations,

b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Superintendent.

VAliKEE ROWE 6-21 vueo

A ., en 6.0 AhMllil5TRATIVE C0t11 ROLL (Continued) m- . =

6,13_. Orr-SITE 00$[ CAL (UlAT10ti MAtJUAL (ODCM) 6.13.1 Change'. to the ODCH:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.0.

This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s), and

2) A determination that the change will maintain the level of the radioactive effluent control required by 10 CFR 20.106, 40 Cf R 190,10 CFR 50.30a, and Appendix 1 to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PORC and the approval of the Plart Superintendent,

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

Y alike E - ROW E 6 22 vnn

___ _ _