ML20217K204

Amend 192 to License DPR-61,changing Administrative Controls,Section 6.0 of Ts,To Reflect Permanent Shutdown & Defueled Status of Plant

ML20217K204
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/27/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217K201	List: ML20217K195 ML20217K204 ML20217K210
References
NUDOCS 9804070152
Download: ML20217K204 (24)

Text

Krav 3o 't UNITED STATES NUCLEAR REGULATORY COMMISSION o f WASHINGTON, D.C. 20565-0001

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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.192 License No. DPR-61

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The two separate applications for amendment by the Connecticut Yankee Atomic Power Company (the licensee) both dated May 30,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The f acility 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 the Commission's regulations:

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 Comrnission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications (TS) as indicated in the enclosure to this license amendment. Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

9804070152 980327 7 PDR ADOCK 05000213 W PDR

2 (2) Technical Specifications

,. The technical specifications contained in Appendix A, as revised through Amendment No.192, are hereby incorporated in the license.- The licensee shall operate the facility in accordance with the technical specifications.

3. This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 041h  !-

6,.

Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Project Management Office of Nuclear Reactor Regulation

Enclosures:

Changes to Appendix A, Technical Specifications Date of issuance: March 27, 1998

ENCLOSURE TO LICENSE AMENDMENT NO.192 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix Ai Technical Specifications, with the enclosed i pages. The revised pages are identified by amendment number and contain vertical lines I indicating the areas of change.

Remove ' Insert 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 69 6-9 d-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 )

6-14 6-14 i

6-15 6-15 6-16 6-16 6-17 6-17 6-18 6-18 6 19 6-19 6-20 6-20 6-21 6-21

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIEILITY 6.1.1 The VP Operations and Decommissioning shall be responsible for l overall facility operation and shall delegate, in writing, the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE 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 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 Connecticut Yankee Quality Assurance Program (CYQAP). l

b. The Unit Director shall be responsible for overall unit safe operation and shall have control over those onsite activities and resources necessary for safe operation and maintenance I of the plant.

c. The VP Operations and Decommissioning shall have corporate l 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 Certified Fuel Handlers and the Equipment Operators and those who carry out health physics 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;

b. At least one person qualified to stand watch in the control room (a Certified-Fuel Handler or an Equipment Operator) shall be present in the control room when irradiated fuel is in the spent fuel pool; HADDAN NECK 6-1 Amendment No. JJ), JJJ, JJp, JJJ, -192 oa

ADNINISTRATIVE CONTROLS

c. An individual qualified in radiation protection procedures

• shall be on site during fuel handling operations; l

d. All fuel handling operations shall be observed and directly supervised by a Certified Fuel Handler who has no other concurrent responsibilities during this operation;

e. DELETED

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

The individual qualified in radiation protection procedures 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 position.

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HADOAN NECK 6-2 Amendment No. JJJ, JJJ 17),192 0432

TABLE 6.2-1

. MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS RE0VIRED TO FILL POSITION Certified Fuel Handler 1*

Equipment Operator 1 The shift crews' 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 unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crewdcomposition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

Does not include the Certified Fuel Handler supervising fuel handling operations.

HADDAM NECK 6-3 Amendment No. J7), JJJ,192 0432

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum ,

qualifications of ANSI N18.1-1971 for comparable positions. l 6.3.1.1 The position of Health Physics Manager shall meet the following minimum qualifications:

a. Academic degree in an engineering or science field or equivalent as per Section 6.3.1.1.c.

b. Minimum of five years professional technical experience in the area of radiological safety, three years of which shall be in applied radiation work in a nuclear facility dealing with problems similar to those encountered in a nuclear power reactor.

c. Technical experience in the area of radiological safety beyond the five year minimum may be substituted on a one-for-one basis towards the academic degree requirement (four years of technical experience being equivalent to a four year academic degree).

d. Academic and technical experience must total a minimum of nine years.

6.3.1.2 DELETED l l

HADDAN NECK 6-4 Amendment No. JJJ, JJJ,192 mas

ADMINISTRATIVE C0KTROLS 6.4 TRAINING A retraining and replacement training program for the Certified Fuel Handlers shall be maintained under the direction of the Unit Director. A retraining and replacement training program for the facility staff shall be maintained under the direction of the Unit Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971. The Unit Director has the overall responsibility for the implementation of the Training Program.

55 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Unit Director on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PORC shall be composed of at least seven members. Members shall l collectively have experience and expertise in the following areas:

Plant Operations, Decommissioning,*

Engineering, Maintenance, Health Physics, Chemistry / Radiochemistry, Quality Assurance, and Security.*

The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the Unit Director, who is the PORC Chairperson. The alternate Chairpersons of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit Director.

• These areas are exempt from the 5-year experience requiremsnt.

HADDAM NECX 6-5 Amendment No. J17,77J.JJJ.JJ7.

om 179,1H,1H,192

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ADNINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a. temporary basis; however, no more than two I alternates shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY

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6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson or his/her designated alternate. J EE2l 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or his/her  ;

designated alternate and four members including alternates.  ;

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for: I

a. Review of: (1) all procedures required by Specification 6.8 and l changes thereto, and 2) any other proposed procedures or changes '

thereto as detennined by the Unit Director to affect nuclear safety; l

b. Review of all proposed tests and experiments that affect nuclear safety;  :

c. Review of all proposed changes to the Technical Specifications;

d. Review of all troposed changes or modifications to plant systems or equipment taat affect nuclear safety;

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and reconnendations to prevent recurrence, to the '

VP Operations and Decommissioning and to the Nuclear Safety l Assessmant Board;

f. Review of all REPORTABLE EVENTS;

g. Review of facility operations to detect potential safety hazards;

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Nuclear Safety Assessment Board I or the Unit Director.

HADOAM NECX 6-6 Amendment No. JJJ. JpJ, Jpp,171, Jpy,192 042n

ADNINISTRATIVE CONTROLS

i. Not used.

J. Not used.

k. Review of the Fire Protection Program and Implementing Procedures. l AUTHORITY 6.5.1.7 The PORC shall:

a. Report to and be advisory to the Unit Director on those areas of responsibility specified in Section 6.5.1.6(a) through (k);

b. Render determinations in writing to the Unit Director if any item considered under Specification 6.5.1.6a. through d. , above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safety question or requires a significant hazards consideration determination.

c. Provide written notification, meeting minutes may be used for this purpose, to the VP Operations and Decommissioning and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Unit Director: however. the VP -

Operations and Decommissioning shall have responsibility for I resolution of such disagreements pursuant to Specification 6.1.1.

l RECORDS j 1

6.5.1.8 The PORC shall maintain written minutes of each meeting that, at a j minimum, document the results of all PORC activities performed under the l responsibility and authority provisions of these Technical Specifications.

A Copy shall be provided to the Nuclear Safety Assessment Board. l 6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)

FUNCTION 6.5.2.1 The minimum qualifications of NSAB members are as follows:

a. The Chairperson and NSAB members shall have:

1. An academic degree in an engineering or physical science field, or hold a senior management position, and

2. A minimum of five years technical experience in their respective field of expertise.

HADDAN NECK 6-7 Amendment No. Jg), JJJ, JJJ, 177, esse 191,199e 191',192

ADMINISTRATIVE CONTROLS

b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:

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Plant Operations, Decommissioning, Engineering, Radiological Safety, Chemistry / Radiochemistry Quality Assurance, and Environmental Protection.

The NSAB serves to advise the VP - Operations and Decommissioning on matters related to nuclear safety and notify the VP Operations and Decommissioning within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant issue and/or a safety significant disagreement between the NSAB and the organization or function being reviewed.

COMPOSITION 6.5.2.2 The VP Operations and Decommissioning shall appoint, in writing, a minimum of five members to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in Specification 6.5.2.1.

ALTERNATES 6.5.2.3 All alternate members shall be appointed, in writing, by the VP -

Operations and Decommissioning: however. no more than two alternates shall participate as members in NSAB activities at any one time.

NEETING FRE00ENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.

DUORUM 6.5.2.5 The quorum of the NSA8 shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Haddam Neck Plant. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.

MADDAM NECK 6-8 Amendment No. JJJ, JJJ, 177, III.

mas JJJ,192

ADMINISTRATIVE CONTROLS REVIEW RESPONSIBILITIES 6.5.2.6 The NSA8 shall be responsible for the review of:

a. Th.e safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;

b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59;

c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;

d. Proposed changes to Technical Specifications and the Operating License;

e. Violations of applicable codes, regulations, orders, licente requirements, or internal procedures having nuclear safety significance;

f. All Licensee Event Reports required by 10 CFR 50.73;

g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety;

h. Significant accidental, unplanned, or uncontrolled radioactive i releases, including corrective actions to prevent recurrence; 6

1. Significant operating abnomalities or deviations from normal and expected performance of equipment that could affect nuclear safety;

j. The performance of the corrective action program; and

k. Audits and the Annual Audit Plan. l Reports or records of these reviews shall be forwarded to the VP -

Operations and Decommissioning within 30 days following completion of the review.

AUDIT PROGRAM RESPONSIBILITIES 6.5.2.7 The NSAB audit program Onr i be the responsibility of the Nuclear Oversight organization. NSAB audits shall be perfomed at least once per 24 l months in accordance with appropriate administrative procedures and shall l encompass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; i

NADDAN NECK 6-9 Amendment No. JJJ, JJJ. JJJ, JJJ,192 une

l anMINISTRATIVE CONTROLS l l

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b. The training and qualifications of the unit staff; 1

c. The implementation of programs required by Specification 6.8;

d. The Fire Protection Program and implementing procedures;  !

e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant. J l

f. Actions taken . to correct deficiencies occurring in . equipment, I structures, systems, components, or method of operation that affect I nuclear safety; and 9 Other activities and documents as requested by the VP - Operations and Decommissioning.

J EE.CD.BD1 6.5.2.8 Written records of reviews and audits shall be maintained. As a 1 minimum, these records-shall include results of the activities conducted under the provisions of Section 6.5.2.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Comission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and j

b. Each REPORTABLE EVENT shall be reviewed by the PORC and the j results of this review shall be submitted to the NSAB and the VP -  !

Operations and Decommissioning.

6.7 DELETED

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HADDAN NECK 6-10 Amendment No. JJ), JJJ, JJJ, JJJ 192 was

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l ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 3

I 6.8.1 Written. procedures and/or administrative policies shall be established, j implemented, and maintained covering the activities referenced below: i I

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MAM NECK 6-11 Amendment No. JJJ, JJ), JJJ JJJ,192

ADMINISTRATIVE CONTROLS

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;

b. The requirements and recommendations of Sections 5.1 and 5.3 of

' ANSI N 18.7-1976.

c. Fire Protection Program implementation.

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

e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) implementation except for Section I.E, Radiological Environmental Monitoring.

f. Process Control Program implementation. l 6.8.2 Each procedure of. Specification 6.8.1, and changes thereto, shall be reviewed by the PORC and shall be approved by the Unit Director prior to implementation and reviewed periodically as set forth in each document or in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made -

provided:  ;

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

b. The change is approved by a member of the plant management staff j and a Certified Fuel Handler; and j l

c. The change is documented, reviewed by the PORC and approved by the )

Unit Director 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 REM 00CM.

6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 6.8.4 above shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is.not altered and the change is documented and reviewed by e , dividual (other than the author) from the Radiological Assessment Bruch ne the POSL, within 14 days of implementation.

HADDAM NECK 6-12 Amendment No. JJ), Jpp, Jpp, Jpf,192 0434

ADMINISTRATIVE CONTROLS 6.9 REPORTING RE0VIREMENTS 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 appropriate Regional Office of the NRC, and one copy to the appropriate NRC Resident Inspector, unless otherwise noted.

6.9.1.1 DELETED 6.9.1.2 DELETED 6.9.1.3 DELETED ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the facility as i described below for the previous calendar year shall be submitted prior to (

March 1 of each year. l HADDAM NECK 6-13 Amendment No. JJJ JJJ. 192 0429

ADMINISTRATIVE CONTROLS 6.9.1.5 Repori.s 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 mres/yr and their associated man-rem exposure according to work and job functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Sciall 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. DELETED

c. DELETED ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine Annual Radiological Environmental Operating Reports covering the operation of the facility during the previous calendar year shall be submitted prior to May 1 of each year.

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

This tabulation supplements the requirements of Section 20.2206 of l 10 CFR Part 20.

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i NADOAN NECK 6-14 Amendment No. JJ), JJJ,192 o4m

ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 A routine Annual Radioactive Effluent Report covering the operation of the facility during the previous calendar year of operation shall be submitted by May 1 of each year.

The report shall include that information delineated in the REM 00CM.

Any changes to the REM 00CM shall be submitted in the Annual Radioactive Effluent Release Report.

6.9.1.8 DELETED 6.9.1.9. DELETED I

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HADOAM NECK 6-15 Amendment No. JJJ. JJ7 177.

osse J)).177 177 192

THIS PAGE INTENTIONALLY BLANK MADDAN NECK 6-16 Amendment No. J1), JM , 157, one 1H,1H,1H,192

ADMINISTRATIVE CONTROLS SPECIAL REPORTS I 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Com-mission, Document Control Desk, Washington, D.C. 20555, with one copy to the appropriate Regional Office of the NRC, and one copy to the eppropriate NRC '

Resident Inspector, within the time period specified for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable reco-d retention requirements of Title 10,' Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of facility operation; l

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety;

c. All REPORTABLE EVENTS;

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

e. Records of tests and experiments; l

f. Records of changes made to the procedures required by Specifica-tion 6.8.1;

g. Records of radioactive shipments;

h. Records of sealed source and fission detector leak tests and results;

i. Records of annual physical inventory of all sealed source material of record; and HADDAN NECK 6-17 AmendmentNo.JJJ,JJJ,JJJ,/%%,192 om

ADNINISTRATIVE CONTROLS 6.10 RECORD RETENTION (Cont) 6.10.3 .The~following records shall be retained for the duration of the facility Operating License:

a. Record 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 i assembly burnup histories;

c. Records of facility radiation and contamination surveys;

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

e. ' Records of gaseous and liquid radioactive material released to the environs; i

f. Records of transient or operational cycles of the reactor vessel; l

g. Records of training and qualification for current members of the facility staff;

h. Recordsofinserviceinspectionsperformedunderpreviousamendmentsl to these Technical Specifications;

i. Records of quality assurance activities required by the Quality i Assurance Manual not listed in Specification 6.10.2; I

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR Part 50.59;

k. Records of meetings of the PORC and the NSAB; )

1. Records for Environmental Qualification.

m. Records of reviews performed for changes made to the RADIOLOGICAL

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EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) and the Process Control Program.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirement of'10 CFR Part 20 and shall be approved,

- maintained, and adhered to for all operations involving personnel radiation exposure.

.HA00AM NECK 6-18 Amendment No. JJJ, JJ), JJ), JpJ 192 osas

ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.1601fc of 10 CFR Part 20, in lieu of the

" control device" or " alarm signal" require)d by paragraph 20.1601, each high radiation area, as defined in 10 CFR Part 20 in which the intensity of radiation is greater than 100 mR/h but equal,to or less than 1000 mR/h at 30 cm (12 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 Pemit (RWP). Individuals qualified in radiation protection procedures e.g., Health Physics Technician) or personnel continuously escorted b(y 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 j

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 Health Physics Manager in the RWP.

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 30 cm (12 in.) from the radiation source or from any surface which the radia-tion penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by >ersonnel under an approved RWP which shall specify the dose rate levels in tie 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 circuitTVcameras)continuoussurveillancemaybemadeby(suchasclosedpersonnel 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 of greater than 1000 mR/h that are located within large areas, such as PWR containment, 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 or continually guarded.

HADDAM NECK 6-19 Amendment No. JJJ, JJJ,192 0429

ADMINISTRATIVE CONTROLS 6.13 RADIJCGI:A E::.UENT MONITORING AND OFFSITE DOSE CALCULATIDI 1ANJA .( I MODCM)

Section I, RADIOLOGICAL EFFLUENTS MONITORING MANUAL (REM), shall outline l the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of facility o>eration. It shall also specify operating guidelines for RADIDACTIVE WASTE TREATMENT SYSTEMS and report content.

Section II, the OFFSITE DOSE CALCULATION MANUAL l methodology and parameters to be used in the calc ulatnon (00CM?,ofshall describe offsite dosesthe due to radioactive gaseous and liquid effluents and in the calculations of 1 gaseous and liquid effluent monitoring instrumentation AlarsVTrip Setpoints j consistent with the applicable LCO's contained in these Technical l Specifications. J Changes to the REM 00CM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.m. This documentation shall contain:

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

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by PORC and the approval of the Unit Director,

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REM or 00CM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the >eriod .

of the report in which any change was made. Each change shall >e i identified by markings in the margin of the affected pages clearly '

indicating the area of the the date (e.g., month / year)page the change was that was changed, and shall indicatej implemented.

6.14 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved operations involving offsite releases,of maintained radioactive and adhered to effluents. for all These i procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT SYSTEMS utilizing the guidance provided in the REM 00CM.

The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet l shipping and burial ground requirements.

HADDAM NECK 6-20 Amendment No. JJ), JJ), JJp, esse 119, 191, 192 1

ADMINISTRATIVE CONTROLS 6.15 DELETED 6.16 DELETED-HADDAM NECK 6-21 Amendment No. JJJ. JJJ. JJJ.192 me