ML20045C304

Amend 148 to License Possession Only License DPR-3,revising TS & Pol Re Refueled Status of Plant

ML20045C304
Person / Time
Site:	Yankee Rowe
Issue date:	06/11/1993
From:	Weiss S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045C297	List: ML20045C296 ML20045C304 ML20045C314
References
NUDOCS 9306220338
Download: ML20045C304 (51)

Text

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UNITED STATES '

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g NUCLEAR REGULATORY COMMISSION

• k rg WASHINGTON, D.C. 20Ni5 YANKEE ATOMIC ELECTRIC COMPANY DOCKET N0.50-029

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YANKEE NUCLEAR POWER STATION-AMENDMENT TO POSSESSION ONLY LICENSE Amendment No. 148 License'No. DPR-3 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by Yank'ee Atomic Electric Company (the licensee) dated December 21, 1992, complies.with the standards and requirements of the Atomic: Energy Act of 1954, as amended (the Act), and Commission rules and regulations set forth in 10 CFR Chapter I;

.B.

The facility will operate in conformity with.the application,_the-provisions of the Act, and the rules and regulations of the Commission;.

C.

There is reasonable assurance:

(i) that the activities authorized by this amendment-can be conducted without endangering the health and safety of the public, and (ii)-that such activities will be conducted in compliance with Commission regulations ~ set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to'the common defense and security or to the health and ' safety of the public; and E.

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

2.

Accordingly, the license is amended by' changes to the Technical Specifications as indicated in the attachment to this license amendment.

Paragraphs 2.C.(2) and 2.C.(3) of Possession Only License No.'DPR-3 are hereby amended to read as follows:

9306220338 930611 PDR ADDCK 05000029 P.

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, (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

148, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.

(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revision to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled, " Yankee Nuclear Power Station Defueled Security Plan,"

Revision 0, dated October 13, 1992, and " Yankee Nuclear Power Station Defueled Security Training and Qualification Plan,"

Revision 0, dated October 13, 1992. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

Paragraphs 2.C.(6), 2.C.(7) and 2.C.(8) are deleted.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Seym ur H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 11, 1993 i

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ATTACHMENT T0 LICENSE AMENDMENT NO.148 POSSESSION ONLY LICENSE NO. DPR-3 DOCKET NO.50-029 Replace all of the pages of the Appendix A Technical Specifications with the attached pages. This is a complete revision to the Technical Specifications.

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INDEX.

DEFINITIONS SECTION PAGE

-l 1.0 DEFINITIONS ACT10N...................................................

1-1 CHANNEL CALIBRATION......................................

1-1 CHANNEL CHECK............................................

1-1 CH AN N E L FUNCTI ON A L T EST..................................

1-1 MEMBER (S) 0F THE PUBLIC..................................

1-1 0FF-SITE DOSE CALCULATION MANUAL (0DCM).................

'l-2 OPERABLE - OPERABILITY...................................

1-2 PROCESS CONTROL PROGRAM (PCP)............................

1-2 REPORTABLE EVENT.........................................

1-2 SITE B0VHDARY............................................

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INDEX c.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCES SECTION PAGE 3/4.0 APPLICABILITY..........................................

3/4-1 3/4.1 SPENT FUEL PIT WATER LEVEL.............................

'3/4-2 3/4.2 C RAN E TRAV E L - S P ENT FU E L P IT..........................

3/4-3 3/4.3 SPENT FUEL STORAGE AREA RADIATION MONITOR..............

3/4-5 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..........................................

B3/4-1 3/4.1 SPENT FUEL PIT WATER LEVEL............................

B3/4-3 3/4.2 CRANE TRAVEL - SPENT FUEL PIT..........................

B3/4 4 3/4.3 SPENT FUEL STORAGE AREA RADIATION MONITOR..............

B3/4-5 3/4.4 LIQUID HOLD-UP TANKS...................................

B3/4-6 3/4.5 SEALED SOURCE CONTAMINATION............................

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INDEX DESIGN FEATURES

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SECTION PAGE-5.1

-SITE Exclusion Area...........................................

5-1 5.2 FUEL STORAGE Criticality..............................................

5 - l' Drainage.................................................

5-1 Capacity.................................................

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INDEX i

ADMINISTRATIVE CONTROLS-SECTION PAGE 1

6.1 RESPONSIBILITY...........................................

6-1 6.2 ORGANIZATION On-Site and Off-Site Organization..........................

6-1 Facility Staff...........................................

6-2 6.3 FACILITY STAFF 00ALIFICATIONS............................

6-5 6.4 TRAINING.................................................

6 6.5 REVIEW AND AUDIT Plant Operation Review Committee Function...........................................

6-5 Composition........................................

6-5 Alternates.........................................

6-5 Meeting Frequency..................................

6-6 0uorum.............................................

6-6 Responsibilities...................................

6-6 Authority..........................................

6 1 Records............................................

6-7 Nuclear Safety Audit and Review Committee Function...........................................

6-8 Composition........................................

6-8 Qualification...................................... 8 Alternates......................................... 9 Consultants............................'............

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..s INDEX ADMINISTRATIVE CONTROLS (continued)

SECTION PAGE 6.5 REVIEW AND AUDIT (continued)

P Nuclear Safety Audit and Review Committee (continued) f Meeting Frequency..................................

6-9 j

0uorum.............................................

6-9 Review.............................................

6-10 Audits....................

6-11 Authority..........................................

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Records............................................

6-12

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6.7 PROCEDURES AND PR0 GRAMS..................................

6-13 6.8 REPORTING REQUIREMENTS t

An n u a l R e p o r t............................................

6-16 Unique Reporting Requirements............................

6-17 Special Reports..........................................

6-17' 6.9 RECORD RETENT10N.........................................

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.c 6.10 RADIATION PROTECTION PR0 GRAM.............................

6 1 6.11 HIGH RADIATION AREA......................................

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6.12 PROCESS CONTROL PROGRAM (PCP)............................ 21 6.13 0FF-SITE DOSE C ALCULATION MANUAL (0DCM)..................

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1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.

ACTION 1.1 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

CHANNEL CALIBRATION 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 CALIBRATION 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 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.

HEMBER(S) 0F THE PUBLIC 1.5 HEMBER(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) 0FF-SITE DOSE CALCULATION MANUAL (0DCM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (0DCM) contains 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 / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.7, 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 - OPERABILITY 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 this definition 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, sampling, analyses, test (s), and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to ass'ure compliance with 10 CFR Parts 20, 61, and 71, state regulations, burial ground requirements, and other requirements, governing the disposal of solid radioactive waste.

REPORTABLE EVENT 1.9 A REPORTABLE EVENT shall be any of 'those conditions specified in 10 CFR 50.73.

SITE BOUNDARY 1.10 The SITE B0UNDARY shall be that line beyond which the land is not l

owned, leased, or otherwise controlled by the licensee. Any area j

within the SITE B0UNDARY used for residential quarters or YANKEE-ROWE l-2

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1. 0 - DEFINITIONS (Continued) recreational purposes shall be considered to be beyond the SITE BOUNDARY for purposes of meeting gaseous 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 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 Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements unless otherwise excepted.

SURVEILLANCE RE0VIREMENTS 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.

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

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3/4.1 SPENT FUEL PIT WATER LEVEL LIMITING CONDITION FOR OPERATION 3.1.1 At least 14 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

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

APPLICABILITY:

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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 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, i.

Shipping casks: 35 tons maximum gross weight - not for spent fuel, and J.

Spent fuel assembly nondestructive test equipment.

APPLICABILITY:

With fuel assemblies in the Spent Fuel Pit.

ACTION:

With the requirements of the above _specificatiot.s not satisfied, place the crane load in a safe condition.

SURVEILLANCE REQUIREMENTS 4.2.1 Loads in excess of 900 pounds shall be prevented from traveling over the spent fuel pit by administrative control, except that the:

Spent Fuel Storage Building roof hatches, the spent fuel a.

inspection stand, the fuel handling equipment, spent fuel 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 pit in accordance with approved written procedures:

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3/4.2 CRANE TRAVEL - SPENT FUEL PIT 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 from 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 assemblies 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 Fuel handling equipment, when moved for maintenance, shall c.

be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control.

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3/4.3 SPENT FUEL STORAGE AREA RADIATION MONITOR LIMITING CONDITION FOR OPERATION 3,3 Radiation levels in the spent fuel storage area shall be monitored by a fixed radiation monitor with an audible alarm set at <5 mr/hr or 2 times background, whichever is greater.

APPLICABILITY: When handling irradiated fuel, control rods or sources.

ACTION:

With fixed radiation monitoring equipment inoperable, place irradiated components in a safe condition and suspend all fuel 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.

SURVEILLANCE 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.

4.3.3 At least once per 18 months, perform a CHANNEL CAllBRATION.

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t 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 Jiquid 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.

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.

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.

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3/4,5 SEALED 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:

1.

Either decontaminated and repaired, or 2.

Disposed of in accordance with Commission Regulations.

SURVEILLANCE REQUIREMENTS 4.5.1 Test Reauirements - 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 least 0.005 microcuries per test sample.

4.5.2 Test Freauencies - Each category of the above required sealed suurces 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 i

materials:

1.

With a half-life greater than 30 days (excluding Hydrogen 3), and 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 with'out a certificate indicating the last test l

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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L BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS FOR THE DEFUELED TECHNICAL SPECIFICATIONS i

NOTE i

The BASES contained in the succeeding pages summarize the reasons for the Specifications in Section 3/4, but 4

i in accordance with 10 CFR 50.36, are.not part of these Technical Specifications.

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3/4.0 APPLICABILITY BASES The specifications of this section 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.

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 unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to 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 to 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 facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities.

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BASES (Continued) t i

as a convenience to extend the surveillance intervals beyond that specified. The limitation of Specification 4.0.2.is basedDon 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 l

activities is not significantly degraded beyond that obtained from 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 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 fue'l 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 FUEL PIT BASES The restriction on movement of loads in excess of the nominal weight of

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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 assambly nondestructive test equipment, the cask hatch cover, the volume reduction equipment, the shipping cask liners, and the shipping casks over = pent 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.

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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 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 an 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 personnel 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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3/4.4 L10010 HOLD-UP TANKS BASES i

Restricting the quantity of radioactive material contained in the outdoor tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentration at the nearest potable water supply and the nearest surface 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.

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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, r

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1 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 probability of damage to a source in that group.

Those sources which are frequently handled are required to be tested 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 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.

5.2 FUEL STORAGE CRITICALITY 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 k,,, flooded equivalent to 0.95 with the spent fuel storage areas with unborated water. The k of 0.95 includes a conservativeallowanceof3%'fdk/kforuncertainties.

DRAINAGE 5.2.2 The spent fuel pit is designed and shall be maintained to 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 540 fuel assemblies.

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4

6.0 ADMINISTRATIVE CONTROLS 9

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 j

shall report to and be'directly responsible to the Manager of Operations in the Yankee Atomic Electric Company.

6.2 ORGANIZATION 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.

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 officer shall have overall responsibility for plant nuclear safety.

This individual 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 safe operation of the plant; he/she shall have control a

over those on-site resources necessary for safe operation and maintenance of the plant.

YANKEE-ROWE 6-1 87h00

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 following:

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 fuel pit.

A qualified Radiation Protection individual-shall be on c.

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. Operating crew personnel trained in radiation protection procedures fill this requirement.

All fuel handling operations shall be directly supervised e.

by a Certified Fuel Handler who has no other concurrent responsibilities' during this operation.

f.

Administrative procedures shall be developed and i

implemented to limit the working hours of the unit staff-who perform safety-related functions; e.g.. the Minimum Shift Crew required by Table 6.2-1. Mechanical, l

Electrical and Instrumentation Technicians and Radiation Protection Technicians.

YANKEE-ROW 6 6-2 R7B SO 1

6.0 ADMINISTRATIVE CONTROLS (Continued)

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall-be to have operating personnel _ work, on the average, an t

approximate 40-hour week.

However, in the event that 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 shift turnover time.

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

Any deviation from 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 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.

O 9

YANKEE-ROWE 6-3 R7t\\80

6.0 ADMINISTRATIVE CONTROLS (Continued)

TABLE 6.2-1 i

MINIMUM SHIFT CREW COMPOSITION #

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITIONS CERTIFIED FUEL HANDLER 1*

EQUIPMENT OPERATOR 1

Does not include the Certified Fuel Handler supervising fuel handling.

Shift crew composition may be less than the minimum l

requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of duty shift crew s

members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

1 I

k YANKEE-ROWE 6-4 R77480 I

2

. ~.

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility management / supervisory staff shall meet or exceed the minimum qualifications of ANSI 18.1-1971 for comparable positions. except for the 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 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 N18.1-1971.

6Property "ANSI code" (as page type) with input value "ANSI N18.1-1971.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5 REVIEW AND AUDIT 6.5.1 PLANT OPERATION REVIEW COMMITTEE FUNCTION 6.5.1.1 The Plant Operation Review Committee (PORC) shall function to advise the Plant Superintendent on all matters related to nuclear safety.

COMPOSITION i

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

ALTERNATES 6.5.1.3 All alternate members sha,ll be appointed in writing by the Plant 4

Superintendent to serve en a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time for the purpose of establishing a quorum.

1 YANKEE-ROWE 6-5 anno i

c_

6.0 ADMINISTRATIVE CONTROLS (Continued)

MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.

i 000 RUM 6.5.1.5 A quorum of the P' ORC shall consist of a majority of the members in Specification 6.5.1.2, including the Chairman.

RESPONSIBILITIES F

6.5.1.6 The PORC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.7 i

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.

d.

Review of all proposed changes or modifications to platd-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 l

prevent recurrence to the Manager of Operations and to the Chairman of the Nuclear Safety Audit and Review Committee.

I f.

Review of all REPORTABLE 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.

Review of the Plant Defueled Security Plan and i

implementing procedures and changes thereto.

~

YANKEE-ROWE 6-6 I

uneo

• u w

6.0 ADMINISTRATIVE C6;:TROLS (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.

AUTHORITY 6.5.1.7 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 Manager of Operations of disagreement between the PORC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the, Manager of Operations and cheirman of the Nuclear Safety Audit and Review Committee.

YANKEE-ROWE 6-7 t

R72\\80 1

+i 6.0 ADMINISTRATIVE CONTROLS (Continued)

~ !: i I

I I

6.5.2 NUCLEAR SAFETY AUDIT AND REVIEW COMMITTEE FUNCTION l

6.5.2.1 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 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.

NSAR Committee members shall not be members of the plant staff.

QUALIFICATION 6.5.2.3 Membership to the NSAR Committee requires that an individual meet one of the below academic and/or experience requirements:

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

experience in the below listed disciplines.

b.

Nine (9) years total experience in the below listed disciplines:

(a)

Nuclear Power Plant Technology (b)

Facility Operations (c)

Power Plant Design (d)

Engineering / Nuclear Engineering (e)

Radiation Safety (f)

Safety Analysis (g)

Instrumentation and Control (h)

Quality Assurance 1

l YANKEE-ROWE 6-8 ansio 1

s.

t 6.0 ADMINISTRATIVE CONTROLS (Continued)

ALTERNATES 6.5.2.4 All NSAR Committee alternate members shall be appointed in writing by the Manager of Operations to serve on a temporary basis:

however, no more than one alternate shall participate in NSAR 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.

MEETING FRE0VENCY 6.5.2.6 Tbt NSAR Committee shall meet at least once pe*,* 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.

l l

YANKEE-ROWE 6-9 i

artsoo

J 6.0 ADMINISTRATIVE CONTROLS (Continued)

REVIEW 6.5.2.8 The NSAR Committee shall review:

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 defined in 10 CFR 50.59.

d.

Proposed changes to Technical Specifications or the License.

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.

i.

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

i YANKEE-ROWE 6-10

?

R7t\\80 l

6.0 ADMINISTRATIVE CONTROLS (Continued)

AUDITS 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NSAR Committee. 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' 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 actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, +25%.

d.

The perforuance 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,

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

i.

The 0FF-SITE DOS'E CALCULATION 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%.

k.

The performance of activities affecting quality as required by effluent and environmental monitoring procedures at least once per 12 months, +25%.

4 YANKEE-ROWE 6-11 a m eo i

~

k 6.0 ADMINISTRATIVE CONTROLS (Continued) 1.

Any other area of facility operation 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 Operations on those areas of responsibility specified in i

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 by 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.

t O

YANKEE-ROWE 6-12 RTuto

p;-

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.

e' 6.7 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 PROGRAM implementation, c.

OFF-SITE DOSE CALCULATION MANUAL implementation.

d.

Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21..

I Revision 1 June'1974 and Regulatory JGuide 4.1 Revision 1.. April 1975.

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 in 6.5.2.3.

The procedures shall be approved by the Manager of Operations.

YANKEE-ROWE 6-13 ameo e

gv; e-6.0 ADMINISTRATIVE CONTROLS (Continued) 6.7. 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 impl ementation.

6.7.5 The following programs shall be established, implemented, and maintained:

a.

Radioactive Effluent Controls Procram 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 effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall-be implemented by operating procedures, and (3)- shall include remedial actions to be taken whenever the program limits 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 10 CFR, Part 20.

Appendix B, Table II, Column 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 quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents r.eleased YANKEE-ROWE 6-14 emeo

e 6.0 ADMINISTRATIVE CONTROLS (Continued) from each unit to UNRESTRICTED AREAS conforming to Appendix I 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 I to 10 CFR, Part 50.

7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR. Part 20.

Appendix B, Table II. 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 SITE BOUNDARY-conforming to Appendix I to 10 CFR.

i Part 50:

9)

Limitations on the annual and quarterly doses to a HEMBER OF THE PUBLIC from Iodine-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 BOUNDARY conforming to Appendix I 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.

Radiolooical Environmental Monitorinc Program A program shall be provided to monitor the radiation and ~

~

radionuclides in the environs of the plant. The program YANKEE-ROWE 6-15 R7t\\80

g.

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 modeling of environmental exposure pathways. The program shall (1) be contained in the ODCH: (2) conform to the guidance of Appendix I 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 in the

ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, 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 exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions. (a) e.g., operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), and waste processing.

YANKEE-ROWE 6-16 R7t\\80

u-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 than 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 Uniaue Reportina 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 ODCM, and (2) Sections IV.B.2. IV.B,3, and IV.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 after January 1 and July 1 of each year. The report shall include a summary of'the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM 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 repprts shall be submitted pursuant to 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

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Tu 6.0 ADMINISTRATIVE CONTROLS (Continued) a.

Sealed Source leakage in excess of limits, Specification 3.5.

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

a.

Records hnd logs of facility operation covering time interval at each power level.

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.

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

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.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of facility radiation and contamination surveys.

d.

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

j 4

e.

Records of gaseous and liquid radioactive material j

released to the environs, j

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nu:

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.9.2 (continued) f.

Records of transient or operational cycles for the Reactor Pressure Vessel.

g.

Records of training ar,d 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 made to 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.

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 0FF-SITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.10 RADIATION PROTEC'/ ION PROGRAM 6.10.1 Procedures fo personnel radiation protection shall be prepared consistent witn requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposures.

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R12\\80

7u-t 6.0 ADMINISTRATIVE CONTROLS (Continued) 4 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 radiation area, and entrance thereto shall be controlled by requiring. issuance of a Radiation Work Permit (RWP).

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

a.

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

A radiation monitoring device which continuously integrates the radiation dose rate in the area, and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been 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 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 tFe provided to prevent unauthorized entry into such areas and the key shall be maintained under the administrative control of the Shift 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.

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N 3

6.0 ^ ADMINISTRATIVE CONTROLS (Continued) 6.12 PROCESS CONTROL PROGRAM (PCP) 6.12.1 Changes to the PCP:

1 a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.o.

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 overall conformance of the solidified waste product to existing requirements of federal, state, or other applicable regulations.

b.

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

-s A

s 4

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u7 a

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.13 0FF-SITE DOSE CALCULATION MANUAL (ODCM) 6.13.1 Changes to the ODCH:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.o.

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 CFR 190, 10 CFR 50.36a, and Appendix I 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 Plant 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 con:urrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the'0DCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the'page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

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