ML022610563

Technical Specifications, Incorporate Administrative & Editorial Changes

ML022610563
Person / Time
Site:	Millstone
Issue date:	09/17/2002
From:	NRC/NRR/DLPM
To:	Dominion Nuclear Connecticut
References
TAC MB3394, TAC MB3395, TAC MB3396
Download: ML022610563 (47)

Text

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Unit 1 Reactor Building is located on the site at Millstone Point in Waterford, Connecticut. The nearest site boundary on land is 2063 feet northeast of the reactor building (1627 feet northeast of I the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3. No part of the I site that is closer to the reactor building than 2063 feet shall be sold or leased except to Dominion Nuclear Connecticut, Inc. or its corporate affiliates for use in conjunction with normal utility operations.

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

4.2.2 The Keff of the spent fuel storage pool shall be less than or equal to 0.90. This Keff value is satisfied with fuel assemblies having a maximum k-infinity of 1.24 in the normal reactor configuration at cold conditions, and an average U-235 enrichment of 3.8 weight percent or less.

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

4.0-1 Amendment No. 40§, 4Q9 111 Millstone - Unit I1

- 4.0-1 Amendment No. 40ý6, 4OP 111

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The designated officer shall be responsible for overall operation of the Millstone Station Site and shall delegate, in writing, the succession to this responsibility. The designated manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession of this responsibility.

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

5.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles. Unit-specific titles for the functions and responsibilities associated with these generic titles are identified in the Quality Assurance Program Topical Report.

5.0-1 Amendment No. 406 111 Unit 1 Millstone - Unit Millstone - 1 5.0-1 Amendment No. 4A6- _ll

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

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

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

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

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

(continued)

Amendment No. 40& 111 Millstone - Unit 11 5.0-2 5.0-2 Amendment No. 4E Ill

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

5.3.1.1 The operations manager or assistant operations manager shall be a CERTIFIED FUEL HANDLER.

5.3.1.2 The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977.

5.0-5 Amendment No.406? 111 Millstone - Unit 11

- 5.0-5 Amendment No.40-, 111

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

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

b. Fire Protection Program implementation;

c. Cold Weather Operations;

d. Quality Controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974;

e. Liquid and gaseous radioactive effluent discharges from the unit for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM;

f. Fuel handling operations;

g. All programs specified in Specification 5.6, except for Section L.E, Radiological Environmental Monitoring of REMODCM, which is performed in accordance with Specifications 5.5.6 and 5.5.7.

5.5.2 The designated manager, designated officer, or designated senior officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the SORC. The review per the SORC or Station Qualified Reviewer Program shall be in accordance with the Quality Assurance Program Topical Report.

5.5.3 Procedures listed in Specification 5.5.1, and changes thereto, shall be approved by the designated manager, or designated officer or by cognizant managers or directors who are designated as the Approval Authority by the designated manager, or designated officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.

(continued) 5.0-7 Amendment No. 40&?409 111 Millstone - Unit 1

- 5.0-7 Amendment No. 10,19 111

Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures (continued) 5.5.4 Each procedure of Specification 5.5.1, and changes thereto, shall be reviewed by the SORC and shall be approved by the designated manager or designated officer, or be reviewed and to approved in accordance with the Station Qualified Reviewer Program prior periodically as set implementation. Each procedure of Specification 5.5.1 shall be reviewed forth in administrative procedures.

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

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

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

c. the change is documented, reviewed by the SORC or the Station Qualified Reviewer Program, as applicable, and approved by the designated manager, designated officer, or the Station Qualified Reviewer Program department manager within 14 days of implementation.

5.5.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 5.6.1 shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.

5.5.7 Temporary changes may be made for the Radiological Environmental Monitoring Program provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP within 14 days of implementation.

(continued)*

Amendment No. 406 111 5.0-8 Amendment No. AD6.-il Millstone - Unit 11 Millstone -

5.0-8

Programs and Manuals 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Programs and Manuals 5.6.2 Technical Specifications (TS) Bases Control Program to the Bases of these Technical This program provides a means for processing changes Specifications under appropriate administrative

a. Changes to the Bases of the TS shall be made controls and reviews.

NRC approval provided the

b. Licensees may make changes to Bases without prior changes do not require either of the following:

1. A change in the TS incorporated in the license; or NRC approval pursuant to

2. A change to the updated FSAR or Bases that requires 10CFR50.59.

to ensure that the Bases are

c. The Bases Control Program shall contain provisions maintained consistent with the FSAR.

5.6.2b above shall be

d. Proposed changes that meet the criteria of Specification Changes to the Bases reviewed and approved by the NRC prior to implementation.

to the NRC on a frequency implemented without prior NRC approval shall be provided consistent with 1 OCFR50.71 (e).

(continued) 5.0-11 Amendment No. 40& 111 Millstone - Unit 1

High Radiation Area 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 High Radiation Area 5.8 High Radiation Area Part 5.8.1 Pursuant to 10CFR Part 20.1601(c), in lieu of the requirements of 10CFR CFR Part 20 shall be 20.1601(a), each high radiation area as defined in 10 thereto barricaded and conspicuously posted as a high radiation area, and entrance equivalent.

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

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

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

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

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device. This individual is responsible for providing positive radiation protection control over the activities within the area and the shall perform periodic radiation surveillance at the frequency specified in radiation protection procedures or the applicable RWP.

(continued) 5.0-18 Amendment No. 4O 111 Millstone - Unit 1

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

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

in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from 5.0-19 Amendment No.406 111 Millstone - Unit 1

INDEX DESIGN FEATUTRES SECTION PAGE 5.1 SITE LOCATION ................ .......................... .. 5-1 5.2 DELETED 5.3 REACTOR CORE Fuel Assemblies .............. ......................... ... 5-4 Control Element Assemblies ........ .................... ... 5-4 5.4 DELETED 5.5 DELETED 5.6 FUEL STORAGE Criticality .................. ........................... 5-5 Drainage ................... ............................. 5-5 Capacity ................... ............................. 5-5 5.7 DELETED 5.8 DELETED 5.9 DELETED MILLSTONE 0748

- UNIT 2 XV Amendment No. lo, jo, 270

INDEX ADMINISTRATIVE CONTROLS PAGE SECTION 6.9 REPORTING REQUIREMENTS 6-16 6.9.1 ROUTINE REPORTS . ...

6-16 STARTUP REPORTS

• S. . . .. . 6-17 ANNUAL REPORTS . . . . . . . . . . . . . . . . . .

S. . . .. . 6-18 ANNUAL RADIOLOGICAL REPORTS ............

S. . . .. . 6-18 MONTHLY OPERATING REPORT .............

S. . . .. . 6-18 CORE OPERATING LIMITS REPORT ...........

S. . . .. . 6-19 6.9.2 SPECIAL REPORTS .................

6.10 DELETED S. . . .. . 6-22 6.11 RADIATION PROTECTION PROGRAM ............

S. . . . . 6-22 6.12 HIGH RADIATION AREA ................

. . .. . 6-23 6.13 SYSTEMS INTEGRITY ........ ..................

. . .. . 6-23 6.14 IODINE MONITORING ........ ..................

6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE . . .. . 6-24 CALCULATION MANUAL (REMODCM). . .........

. . .. . 6-24 6.16 RADIOACTIVE WASTE TREATMENT ............

6.17 SECONDARY WATER CHEMISTRY ............ . . . .. . 6-25 6.18 DELETED

. . . . 6-26 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM .....

S. . . . .. . 6-26 6.20 RADIOACTIVE EFFLUENT CONTROLS PROGRAM ..........

S. . . . .. . 6-27 6.21 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . .

S. . . . .. . 6-28 6.22 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM

. . . .. . 6-28 6.23 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM I MILLSTONE - UNIT 2 XVII Amendment No. 79, 7, P, *f, 70, 0877 Yoo 111, f7 79,77,M 1 R 77f 270o7

PLANT SYSTEMS SUIRVEI LLANCE REOU IREMENTS SURVEILLANCE REQUIREMENTS 4.7.5.1.1 The water level shall be determined to be below plant grade at least once per hour when the eye of a hurricane is within 150 miles of the facility.

4.7.5.1.2 The above specified meteorological conditions shall be deter mined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when a hurricane eye is within 150 miles of the facility. The meteorological conditions shall be determined from weather service forecasts and/or from the site meteorological I instrumentation.

MILLSTONE - UNIT 2 3/4 7-14 Amendment No. 270 0749

5.0 DESIGN FEATURES 5.1 SITE LOCATION The Unit 2 Containment Building is located on the site at Millstone Point in Waterford, Connecticut. The nearest site boundary on land is 2034 of the feet northeast of the containment building wall (1627 feet northeast of the boundary elevated stack), which is the minimum distance to the in 10 CFR 100.3. No part of the site that is exclusion area as described Dominion Nuclear closer than these distances shall be sold or leased except to with affiliates for use in conjunction Connecticut, Inc. or its corporate normal utility operations.

5.2 DELETED MILLSTONE - UNIT 2 5-1 Amendment No. $JP, 270 0878

THIS PAGE INTENTIONALLY LEFT BLANK 5-2 Amendment No. 709, 270 MILLSTONE - UNIT 2 0751

THIS PAGE INTENTIONALLY LEFT BLANK 5-3 Amendment No. 270 MILLSTONE - UNIT 2 0751

DESIGN FEATURES DESIGN FEATURES I

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing 176 rods. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.5 weight percent of U-235.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies. The control element assemblies shall be designed and maintained in accordance with the design provisions contained in Section 3.0 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.4 DELETED I MILLSTONE - UNIT 2 5-4 Amendment No. 7, 7f7, , 7#, 270 0751

DESIGN FEATURES 5.5 DELETED 5.6 FUEL STORAGE CRITICALITY 5.6.1 a) The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a keff _< .95. The maximum nominal fuel enrichment to be stored in these racks is 4.50 weight percent of U-235.

b) Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a Keff < .95 with the storage pool filled with unborated water. Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design burnup has been sustained.

c) Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center-to-center distance between storage locations to ensure Kff * .95 with a storage pool filled with unborated water. Fuel assemblies stored in this region may have a maximum nominal enrichment of 4.5 weight percent U-235. Fuel assemblies stored in this region are placed in a 3 out of 4 STORAGE PATTERN for reactivity control.

d) Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations to ensure a K*f < .95 with the storage pool filled with unborated water.

Fuel assemblies stored in this region must comply with Figures 3.9-1a or 3.9-1b to ensure that the design burn-up has been sustained. Additionally, fuel assemblies utilizing Figure 3.9-1b require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes. The poison pins are solid 0.87 inch O.D.

borated stainless steel, with a boron content of 2 weight percent boron.

e) Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel and ensure a Kflf

• 0.95. The contents of consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3.

MILLSTONE - UNIT 2 5-5 Amendment No. 19, p, J*,

0751 777, OF,

77, 797, IM27o

DESIGN FEATURES 5.7 DELETED 5.8 DELETED 5.9 DELETED MILLSTONE - UNIT 2 5-6 Amendment No. Y, 79, 177, 77I, 270 0752

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The designated officer shall be responsible for overall operation of the Millstone Station Site and shall delegate in writing the succession to this responsibility. The designated manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession to this responsibility.

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

6.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles. Unit specific titles for the functions and responsibilities associated with these generic titles are identified in the Quality Assurance Program Topical Report.

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the higher management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Program Topical Report.

b. The designated manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The designated officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF

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

MILLSTONE - UNIT 2 6-1 Amendment No. M, 9, 79, Y7, 0753 97, x7f, 779, W, 070

ADMINISTRATIVE CONTROLS FACILITY STAFF (CONTINUED) is

d. A radiation protection technician shall be on site when fuel in the reactor. (Table 6.2-1) be

e. ALL CORE ALTERATIONS after the initial fuel loading shall directly supervised by either a licensed Senior Reactor Opera has tor or Senior Reactor Operator Limited to Fuel Handling who no other concurrent responsibilities during this operation.

to

f. Administrative procedures shall be developed and implemented limit the working hours of unit staff who perform safety related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971* for comparable positions, except for:

a. If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 2, then the operations manager shall have held a senior reactor operator license at a Pressurized Water Reactor and an individual serving in the capacity of the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 2.

b. The Shift Technical Advisor (STA) who shall meet the requirements of Specification 6.3.1.b.1 or 6.3.1.b.2.

1. Dual-role individual: Must hold a senior reactor operator's license at Millstone Unit No. 2, meet the STA training criteria of NUREG-0737, Item I.A.1.1, and meet one of the following educational alternatives:

a. Bachelor's degree in engineering from an accredited institution;

b. Professional Engineer's license obtained by the successful completion of the PE examination; reactor As of November 1, 2001, applicants for reactor operator and senior operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.

MILLSTONE - UNIT 2 6-2 Amendment No. j7p, 747, 79, T79, 0879 P9 W, 7, 270

ADMINISTRATIVE CONTROLS

c. Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences;

d. Bachelor's degree in a physical science from an accredited institution, including course work in the physical, mathematical, or engineering sciences;

e. Successful completion of the Memphis State University (MSU) STA program. (Note: This alternative is only acceptable for individuals who have completed the program prior to December 31, 1986); or

f. Successful completion of the Thames Valley State Technical College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled in the program by October 1, 1987.

2. Dedicated STA: Must meet the STA training criteria of NUREG-0737, Item I.A.1.1, and have received specific training in plant design, and response and analysis of the plant for transients and accidents.

c. The radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977.

MILLSTONE 0754

- UNIT 2 6-3 Amendment No. W97, 7*, 779, 270

TABLE 6.2-1I')

2 MINIMUM SHIFT-CREW COMPOSITION1 1 APPLICABLE MODES LICENSE CATEGORY 1, 2, 3 & 4 5 &6 2 1(0)

Senior Reactor Operator Reactor Operator 2 1 Non-Licensed Operator 2 1 Shift Technical Advisor 1k'M None Required (1) Does not include the licensed Senior Reactor or Senior Reactor Operator Limited to Fuel Handling individual supervision CORE ALTERATIONS after the initial fuel loading.

(2) The above shift crew composition and the qualified radiation protection I technician of Section 6.2.2 may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided expeditious actions are taken to fill the required position.

(3) Requirements for minimum number of licensed operators on shift during operation in modes other than cold shutdown or refueling are contained in IOCFR50.54(m).

(4) The Shift Technical Advisor position can be filled by either of the two Senior Reactor Operators (a dual-role individual), if he meets the requirements of Specification 6.3.1.b.1.

MILLSTONE - UNIT 2 6-4 No. , P, 0753 Amendment 17f 7P7, 79,jyj,Y?,270

ADMINISTRATIVE CONTROLS

f. Fire Protection Program implementation.

g. Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev. 1, June 1974.

h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation, except for Section I.E.,

Radiological Environmental Monitoring.

6.8.2 a. The designated manager or designated officer or designated senior officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Quality Assurance Program Topical Report.

b. Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the designated manager or designated officer or by cognizant managers or directors who are designated as the Approval Authority by the designated manager or designated officer, as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.

c. Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved in accordance with the Quality Assurance Program Topical Report, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 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 holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed and approved in accordance with the Quality Assurance Program Topical Report within 14 days of implementation.

6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.

MILLSTONE - UNIT 2 6-15 Amendment Nos. 77, *, *, 177, 0755 77,17f, 7f, log, p 7yf, JXF, 270

ADMINISTRATIVE CONTROLS 6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of 6.8.4 above shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP within 14 days of implementation.

6.9 REPORTING REQUIREMENTS Routine Reports 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, unless otherwise noted.

,Startup Report 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifica tions that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

MILLSTONE - UNIT 2 6-16 Amendment No. 7Y, 7P, If, #X, Y7, 0755 79, 777, P7, W 270

ADMINISTRATIVE CONTROLS ADMINISTRATIVE CONTROLS ANNUAL REPORTS' 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

6.9.1.5 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 2 e.g., reactor exposure according to work and job functions, operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. 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 total whole body dose received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.1.5.b).

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2 This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

MILLSTONE - UNIT 2 6-17 Amendment No. Y, 777, 779, , 270 0755

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm signal" required by paragraph 20.203(c),

each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation.Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., radiation protection technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

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

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 levels in the area have been established and personnel have been made knowledgeable of them; or

c. An individual 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 shall perform periodic radiation surveillance at the frequency specified by the radiation protection manager in the RWP.

MILLSTONE - UNIT 2 6-22 Amendment Nos. 7, *, 79, 0756 77, 7*, 7f , 7, 270

ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA (CONT.)

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or radiation protection supervision. Doors shall remain locked except during period of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed-circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would, or could, contain highly radioactive fluids during a serious transient, or accident, to as low as practical levels. This program shall include the following:

1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

MILLSTONE - UNIT 2 6-23 Amendment No. $, J*, J*,

0756777, J, , 270

ADMINISTRATIVE CONTROLS

b. 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

c. Participation in a 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.

6.22 Reactor Coolant Pump Flywheel Inspection Report This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius, or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels at least once every 10 years.

6.23 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

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

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

1. A change in the TS incorporated in the license or

2. A change in the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

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

d. Proposed changes that meet the criteria of Specification 6.23.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

MILLSTONE - UNIT 2 6-28 Amendment No. P, ?P, 270 0880

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION ................ .......................... ..5-1 5.2 DELETED 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES ............ ....................... .. 5-5 5.3.2 CONTROL ROD ASSEMBLIES ............. ................... 5-5 5.4 DELETED I 5.5 DELETED 5.6 FUEL STORAGE 5.6.1 CRITICALITY .............. ......................... .. 5-6 5.6.2 DRAINAGE ................. .......................... ..5-6 5.6.3 CAPACITY ................. .......................... ..5-6 5.7 DELETED I MILLSTONE - UNIT 3 xvi i Amendment NO. 212 0822

INDEX ADMINISTRATIVE CONTROLS PAGE SECTION

...................... ... 6-14 6.8 PROCEDURES AND PROGRAMS ..... .....

....................... 6-17 6.9 REPORTING REQUIREMENTS .............

. . . . . .6 1 6.9.1 ROUTINE REPORTS . . . . . . . . . . . . . . . . . .

RUTNERPOTS....................................6-17 6..1

...... .. 6-17 Startup Report .... ........ ..................

6-18 Annual Reports .... .......... ..........................

.. 6-19 Annual Radiological Environmental Operating Report .........

.. 6-19 Annual Radioactive Effluent Release Report .... ..........

................... .. 6-19 Monthly Operating Reports ........

................ ... 6-19a Core Operating Limits Report .......

6-21 6.9.2 SPECIAL REPORTS.......... ....... ........................

6.10 DELETED 6-22 6.11 RADIATION PROTECTION PROGRAM ..........

........................ .. 6-23 6.12 HIGH RADIATION AREA ...........

6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM). ...... ................... 6-24

.................... .. 6-24 6.14 RADIOACTIVE WASTE TREATMENT .........

............... .. 6-25 6.15 RADIOACTIVE EFFLUENT CONTROLS PROGRAM .....

.. 6-26 6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..............

PROGRAM. ...... ...... . 6-26 6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION BASES CONTROL PROGRAM ........... .. 6-26 I 6.18 TECHNICAL SPECIFICATIONS (TS) I

................ .. 6-27 6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT ......

xix Amendment No. 99, 9, 77, MILLSTONE - UNIT 3 0;, 20*ý 0943

5.0 DESIGN FEATURES 5.1 SITE LOCATION The Unit 3 Containment Building is located on the site at Millstone Point in Waterford, Connecticut. The nearest site boundary on land is 1719 feet northeast of the containment building wall (1627 feet northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3. No part of the site that is closer than these distances shall be sold or leased except to Dominion Nuclear Connecticut, Inc. or its corporate affiliates for use in conjunction with normal utility operations.

5.2 DELETED MILLSTONE - UNIT 3 5-1 Amendment No. 212 0944

THIS PAGE INTENTIONALLY LEFT BLANK 5-2 Amendment No. 212 MILLSTONE - UNIT 3 0824

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 5-3 Amendment No.- 212 0824

THIS PAGE INTENTIONALLY LEFT BLANK 5-4 Amendment No. 212 MILLSTONE - UNIT 3 0824

DfESIGiN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies. Each fuel assembly shall consist of 264 zircaloy-4 or ZIRLO clad fuel rods with an initial composition of natural uranium dioxide or a maximum nominal enrichment of 5.0 weight percent U-235 as fuel material. Limited substitutions of zircaloy-4, ZIRLO or stainless steel filler rods for fuel rods, in accordance Fuel with NRC-approved applications of fuel rod configurations, may be used.

assembly configurations shall be limited to those fuel designs that have been by analyzed with applicable NRC staff-approved codes and methods, and shown test or cycle-specific reload analyses to comply with all fuel safety design bases. Each fuel rod shall have a nominal active fuel length of 144 inches.

A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

CONTROL ROD ASSEMBLIES The 5.3.2 The core shall contain 61 full-length control rod assemblies. of full-length control rod assemblies shall contain a nominal 142 inches absorber material. The nominal values of absorber material shall be 95.3%

hafnium and 4.5% natural zirconium or 80% silver, 15% indium, and 5% cadmium.

All control rods shall be clad with stainless steel.

5.4 DELETED 5.5 DELETED MILLSTONE - UNIT 3 5-5 Amendment No. 77, 77, 91, 212 0824

DESIGN FEATURES CAPACITY locations, 673 5.6.3 The spent fuel storage pool contains 350 Region I storage locations, for a Region 2 storage locations and 756 Region 3 storage locations. An additional total of 1779 total available fuel storage spent fuel Region 2 rack with 81 storage locations may be placed in the the Region 2 pool, if needed. With this additional rack installed, for a total of 1860 total storage capacity is 754 storage locations, available fuel storage locations.

5.7 DELETED I MILLSTONE - UNIT 3 5-6a Amendment No. ;i7,-sF, MYX,212 0825

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 5-7 Amendment No. 212 0826

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The designated officer shall be responsible for overall operation of the Millstone Station Site and shall delegate in writing the succession to this responsibility. The designated manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession to this responsibility.

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

6.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles. Unit specific titles for the functions and responsibilities associated with these generic titles are identified in the Quality Assurance Program Topical Report.

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Program Topical Report.

b. The designated manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The designated officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; MILLSTONE 0827

- UNIT 3 6-1 Amendment No. 7P, , y, 70, 777, 212

ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued)

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;

c. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.

d. A radiation protection technician* shall be on site when fuel is in the reactor;

e. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

f. Deleted

g. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No.

82-12).

• The radiation protection technician composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

MILLSTONE UNIT 3 6-2 Amendment No. 7f *, *, 2122 0827 2

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, or 4 MODE 5 or 6 SM 1 1 SRO I None RO 2 1 PEO 2 1 STA I* None SM - Shift Manager with a Senior Operator license on Unit 3 SRO - Individual with a Senior Operator license on Unit 3 RO - Individual with an Operator license on Unit 3 PEO - Plant Equipment Operator (Non-licensed)

STA - Shift Technical Advisor The shift crew composition may be one less than the minimum requirements of Table 6.2-1 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 is unexpected absence of on-duty shift crew members provided immediate action taken to restore the shift crew composition to within the minimum requirements to be of Table 6.2-1. This provision does not permit any shift crew position shift crewmember being late or unmanned upon shift change due to an oncoming absent.

During any absence of the Shift Manager from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of the Shift Manager from the control room while the or unit is in MODE 5 or 6, an individual with a valid Senior Operator license Operator license shall be designated to assume the control room command function.

• The STA position may be filled by an on-shift Senior Reactor Operator only if that Senior Reactor Operator meets the Shift Technical Advisor qualifica tions of the Commission Policy Statement on Engineering Expertise on Shift.

MILLSTONE - UNIT 3 6-3 Amendment No. P, 212 0827

AmIMNSTRATIVF CONTROL S 6.2.3 Deleted.

6.2.4 SHIFT TECHNICAL ADVISOR support to 6.2.4.1 The Shift Technical Advisor shall provide advisory technical and reactor engineering, the Shift Manager in the areas of thermal hydraulics, Shift of the unit. The plant analysis with regard to the safe operation in a scientific Technical Advisor shall have a bachelor's degree or equivalent specific training in the or engineering discipline and shall have received unit accidents, and in response and analysis of the unit for transients and in and controls design and layout, including the capabilities of instrumentation the control room.

MTISI'-Tnml - "IMIT 3 6-4 Amendment No. ZI, *,

g

• w ...........

1*, J7*, 212 0827

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum for:

qualifications of ANSI N18.1-1971* for comparable positions, except

a. If the operations manager does not hold a senior reactor operator shall have license for Millstone Unit No. 3, then the operations manager reactor, held a senior reactor operator license at a pressurized water and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3. of

b. The radiation protection manager shall meet or exceed the qualifications Regulatory Guide 1.8, Revision 1, May 1977.

6.4 TRAINING facility staff 6.4.1 A retraining and replacement training program for theof Section 5.5 of that meets or exceeds the requirements and recommendations ANSI N18.1-1971* and 10 CFR Part 55.59 shall be maintained.

6.4.2 Deleted.

6.5 Deleted.

• As of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.

MILLSTONE - UNIT 3 6-5 Amendment No. 7f, f, *9, 9, Y, 0945 170, 212, 779, 777, 777, 79, 212

ADMINISTRATIVE CONTROLS

f. Not used.

g. Fire Protection Program implementation;

h. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974; and

i. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E, Radiological Environmental Monitoring.

6.8.2 a. The designated manager or designated officer or designated senior officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Quality Assurance Program Topical.Report.

b. Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the designated manager or designated officer or by cognizant managers or directors who are designated as the Approval Authority by designated manager or designated officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.

c. Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved in accordance with the Quality Assurance Program Topical Report, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 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 holds a Senior Operator license on the unit affected; and

c. The change is documented, reviewed and approved in accordance with the Quality Assurance Program Topical Report within 14 days of implementation.

MILLSTONE - UNIT 3 6-15 Amendment No. P, 9, 7*, J7, J*

0828 177, J77, 212

ADMINISTRATIVE CONTROLS ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.5 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.

6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 6.8.5 above shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

MILLSTONE - UNIT 3 6-17a Amendment No. fJ, 79f,212 0829

MTNTmSTRATIVF CANTRnis 6.12 HIGH RADIATION AREA of the 6.12.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu "control device" or "alarm signal" required by paragraph 20.203(c),each high of radia radiation area, as defined in 10 CFR Part 20, in which the intensity the radiation (18 in.) from tion is equal to or less than 1000 mR/h at 45 cm be barricaded source or from any surface which the radiation penetrates shall shall entrance thereto and conspicuously posted as a high radiation area and (RWP).

be controlled by requiring issuance of a Radiation Work Permit radiation Individuals qualified in radiation protection procedures (e.g., individuals by such protection technician) or personnel continuously escorted performance of may be exempt from the RWP issuance requirement during the equal to or their assigned duties in high radiation areas with exposure rates plant radiation less than 1000 mR/h, provided they are otherwise following Any protection procedures for entry into such high radiation areas. areas shall be individual or group of individuals permitted to enter such provided with or accompanied by one or more of the following:

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

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

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

areas 6.12.2 In addition to the requirements of Specification 6.12.1, mR/h at 45 cm accessible to personnel with radiation levels greater than 1000 the radiation (18 in.) from the radiation source or from any surface which entry, penetrates shall be provided with locked doors to prevent unauthorized control of the Shift and the keys shall be maintained under the administrative shall remain Manager on duty and/or radiation protection supervision. Doors RWP locked except during periods of access by personnel under an approved and the work areas which shall specify the dose rate levels in the immediate lieu of-the stay maximum allowable stay time for individuals in that area. In as closed circuit TV time specification of the RWP, direct or remote (such in cameras) continuous surveillance may be made by personnel qualified control over the radiation protection procedures to provide positive exposure activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within largeof areas, such as PWR containment, where no enclosure exists for purposesthe locking, and where no enclosure can be reasonably constructed around individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

MILLSTONE - UNIT 3 6-23 Amendment No. *, 212 0830

ADMINISTRATIVE CONTROLS

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

6.16 -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM in the environs A program shall be provided to monitor the radiation and radionuclides measurements of of the plant. The program shall provided (1) representative radioactivity in the highest potential exposure pathways, and (2) verification of the exposure accuracy of the effluent monitoring program and modeling of environmental to the pathways. The program shall (1) be contained in the REMODCM, (2) conform guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the REMODCM.

b. 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

c. Participation in a 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.

6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECfION PROGRAM This program shall provide for the inspection of each reactor coolant pump bore flywheel by from the inner of the either qualified in-place UT examination over the volume (magnetic flywheel to the circle of one-half the outer radius or a surface examination volume partical testing and/or penetrant testing) of exposed surfaces defined by the of the disassembled flywheels at least once every 10 years.

6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM these Technical This program provides a means for processing changes to the Bases of Specifications:

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

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

1. A change in the TS incorporated in the license or

2. A change to updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

MILLSTONE - UNIT 3 6-26 Amendment No. 79, 79, 212 0946

AflM1IJTTDAT11JF rANTRAI '

/'*1./l'l JLI1 L *.;I I*r%I & w L-AnMTMTCTDATTvr rnNTPni,ý t.*ull I IIwL-*

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

d. Proposed changes that meet the criteria of Specification 6.18.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT This program provides controls to track the FSAR, Section 3.9N, cyclic and transient occurrences to ensure that components are maintained within the design limits.

MILLSTONE - UNIT 3 6-27 Amendment No. 212 0946