ML20217K322

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Amend 195 to License DPR-61,deleting Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor,Duplicate Regulatory Requirements or Duplicate Info Located in UFSAR
ML20217K322
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 10/19/1999
From: Masnik M
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217K319 List:
References
NUDOCS 9910260101
Download: ML20217K322 (42)
v • d • e


Text

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[ 'k UNITED STATES g j t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001

. . . . . ,o CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT l AMENDMENT TO FACILITY OPERATING LICENSE l

1 Amendment No. 195 I License No. DPR-61

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

A. The application for amendment filed by the Connecticut Yankee Atomic Power Company (CYAPCO or the licensee) dated June 3,1999, as supplemented by letter dated August 24,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; 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 regulations of the Commission and all applicable requirements have been satisfied.

2. Accordingly, the license is amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, and other additions, deletions, .

and revisions to the Technical Specifications, as described in the licensee's application dated June 3,1999, as supplemented by letter dated August 24,1999, and evaluated in the staff's Safety Evaluation dated Oct19,1999, indicated in the attachment to this license amendment. Paragraph 2.C.2 of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications l The Technical Specifications contained in Apper. dix A, as revised through Amendment I No. 195, are hereby incorporated in the license. The licensee shall operate the facility l in accordance with the Technical Specifications.

9910260101 991019 PDR ADOCK 05000213 I W PDR 1 1

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3. Paragraph C.(6) of Facility Operating License No. DPR-61, which refers to the integrated Implementation Schedule, is hereby deleted.
4. Paragraph C.(7) of Facility Operating License No. DPR-61 is hereby amended to read as follows: '

I (6) Fuel Movement l l

The movement of special nuclear matenal used as reactor fuelinto the containment is prohibited

5. Paragraph D. of Facility Operating License No. DPR-61 is hereby amended to read as follows:

D. This license is effective as of the date of issuance and authorizes ownership and possession of this facility until the Commission notifies the licensee in writing that the license is terminated. The licensee shall:

1. Take actions necessary to decommission and decontaminate this facility and continue to maintain this facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition; and
2. Conduct activities in accordance with all other restrictions applicable to this facility in accordance with NRC regulations and the specific provisions of this 10 CFR 50 facility license.
6. This license amendment is effective as of the date of issuance. This a.nendment shall be implemented within 60 days of issuance. implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled documents as identified in the licensee's application dated June 3,1999, as supplemented August 24, 1999, and reviewed in the staff's Safety Evaluation dated October 19, 1999.

FOR THE NUCLEAR REGULATORY COMMISSION

, 7 hY $$ c Michael T. Masnik, Chief Decommissioning Section Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to Technical Specifications and Operating License Date of issuance: October 19, 1999 i

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- ATTACHMENT TO CENSE AMENDMENT NO.195 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50 213 Replace the following pages of Facility Operating License No.' DPR-61 and Appendix A,

Technical Specifications, with the attached revised pages.- The revised pages are identified by.

amendment number and marginallines indicating the areas of change.

Operating License pages:

1 Remove Insert 1 1*

.2 2*

3 3 4 4- l

  • reformatted - no changes j Technical Specification pages: I Remove Insert index pages I through XIX Index pages I through IV Section 1 pages 1-1 through 1-9 Section 1 pages 1-1 and 1-2 Section 3 pages 3/4 31 through 3/411-6 Section 3 pages 3/4 9-1 through 3/4 9-8 Section 3 unnumbered pages Bases Section B3/4 3-2 thrugh B3/411-3 Bases Section B3/4 9-1and B3/4 9-2 Bases Section unnumbered pages-Section 5 pages 5-1 through 5 4 Section 5 pages 5-1 and 5-2 Section 5 unnumbered pages Section 6 pages 6-1 through 6-21 Section 6 pages 6-1 through 6-17

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l I g" tog gb 4 UNITED STATES

.g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001 n\ *****p$

i CONNECTICUT YANKEE ATOMIC POWER COMPANY L DOCKET NO. 50-213 HADDAM NECK PLANT l FACILITY OPERATING LICENSE  ;

License No. DPR-61 l

1. The Atomic Energy Commission (the Commission) having found that:

A. The application for license, as amended, filed by Connecticut Yankee Atomic

_ Power Company (the licensee) cornplies 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 and all required notifications to other agencies or bodies have been duly made; B. Construction of the Haddam Neck Plant (facility) has been substantially completed in conformity with Construction Permit No. CPPR-14 and the application, as amended, the provisions of the Act, and the rules and reguhtions of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; l D. There is reasonable assurance: (i) that the activities authorized by this operating i license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; l

l E. The licensee is technically and financiauy qualified to engage in the activities  ;

authorized by this operating licen-se in accordance with the rules and regulations l of the Commission; l

F. 7 he licensee has satisfied the applicable provisions of 10 CFR Part 140, l

" Financial Protection Requirements and indemnity Agreements," of the Commission's regulations; G. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public; i

Amendment No.195 l l

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t H. After weighing the environmental, economic, technical, and other benefits of the

. facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. DPR 61 is in j- ' accordance with Appendix D to 10 CFR Part 50 of the Commission's regulations and all applicable requiremeats have been satisfied; and I. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30,40 and 70,

2. . Facility Operating License No. DPR-61 is hereby issued to the Connecticut Yankee Atomic Power Company to read as follows:

A. This license applies to the Haddam Neck Plant, a pressurized light-water reactor

and associated equipment (the facility) owned by the Connecticut Yankee Atomic Power Company. The facility is located on Connecticut Yankee's Haddam Neck site on the east bank of the Connecticut River, approximately 21 miles south-southeast of Hartford, in the Town of Haddam, Middlesex County, Connecticut, and is described in the " Facility Description and Safety Analysis l Report" as supplemented and amended (Amendment 10 through l Amendment 25 to the License Application) and the " Environmental Report" (as supplemented by Amendment 1).

. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Connecticut Yankee Atomic Power Company:

1 (1) Pursuant to Section 104b of the Act and 10 CFR Part 50," Licensing of i

, Production and Utilization Facilities," to possess, use, and operate the  !

facility at the designated location in the Town of .Haddam, Middlesex County, j Connecticut, in accordance with the procedures and limitations set forth in 1 this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at )

any time special nuclear material as reactor fuel in accordance with the limitations .for storage and amounts required for reactor operation, as j described in the Facility Description and Safety analysis as supplemented

-and amended; or as described in any amendment to this license; (3) CYAPCO, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, L possess and use at any time any byproduct, source and special nuclear l material as sealed neutron sources for reactor startup (possession only),

l sealed sources for reactor instrumentation (possession only), and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

' i Amendment No.195 L

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_(4) CYAPCO, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus )

or components; and

)

(5) CYAPCO, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but ,

not separate, such byproduct and special nuclear material as may be I produced by the operations of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, I and Section 70.32 of Part 70;is subject to all applicable provisions of the Act l and to the rules, regulations, and orders of the Commission now or hereafter in l effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is not authorized to operate the reactor. Fuel may not be placed in the reactor vessel.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.195, are hereby incorporated in the license. The licensee l shall operate the facility in accordance with the Technical Specifications.  ;

(3) D31eted by Amendment No. 29 (4) Fire Protection The licensee shallimplement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER, dated October 3,1978, and Supplements dated February 6,1981, November 11,1981, November 14, 1984, November 27,1987, January 20,1990, April in,1990, August 14,1990, June 27,1991, October 16,1991, November 21,1991, and February 1,1995, subject to the following provisions.

The licensee may make changes to the fire protection program without NRC approvalif these changes do not reduce the effectiveness of fire protection for facilities, systems, and equipment which could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.

Amendment No. 195

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(5) Physical Protection l

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Haddam Neck

- Plant Physical Security Plan," with revisions submitted through January 24, 1989; "Haddam Neck Plant Guard Training and Qualification Plan," with I revisions submitted through January 27,1983; and "Haddam Neck Plant Safeguards Contingency Plan," with revisions submitted through December 9,1983. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(6) Fuel Movement  !

The movement of special nuclear material used as reactor fuelinto the containment is prohibited.

i D. This license is effective as of the date of issuance and authorizes ownership and possession of this facility until the Commission notifies the licensee in writing that the license is terminated. The licensee shall:

1. Take actions necessary to decommission and decontaminate this facility and continue to maintain this facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition; and i
2. Conduct activities in accordance with all other restrictions applicable to this j facility in accordance with NRC regulations and specific provisions of this 10 CFR 50 facility license.

FOR THE ATOMIC ENERGY COMMISSION i'

A. Giambusso, Deputy Director for Reactor Projects 4 Directorate of Licensing

)

Original Signed by A. Giambusso  !

I

Enclosure:

Appendices A and B - Technical Specifications Date of issuance: December 27,1974 Amendment No.195 ,

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r INDEX DEFINITIONS- .

SECTION PAGE 1 Q -~ DEFINITIONS

-1.1 -ACTI0N..................................................... 11 1.2 CERTIFIED' FUEL HANDLER..................................... 1.1-l 1.3 '

MEMBER (S) 0F THE PUBLIC.................................... 11 1.4 ' 0PERABLE OPERABI LITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 1.5 RADI0 ACTIVE WASTE-TREATMENT SYSTEMS........................ 12 1.6- RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)............................... 1-2 1.7 S ITE B0VNDARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.O DELETED 2.0 BASES DELETED LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3_/.4. O APPLICABILITY

'3.0.1- .........~.............................................. 3/4 0 1 3.0.2 ....................................................... 3/4 0 1 3.0.3 DELETED 3.0.4 ....................................................... 3/4 0 1 4.0.1 ....................................................... 3/4 0 2 14.0.2 ....................................................... 3/4 0-2 4.0.3 ....................................................... 3/4 0 2 4.0.4 .. .................................................... 3/4 0 2 i

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HADDAM NECK I . Amendment No. 125.158.178.138.193. 195 g

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INDEX l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS (continued) I

, SECTION PAGE l

3/4 1 DELETED  ;

3/4.2 DELETED 3/4.3 DELETED l

-1/4.4 DELETEC  ;

3.1.5 DELETED 3/4.6 DELETED 3/4.7 DELETED l

3/4.8 DELETED 3/4,9 SPENT FUEL BUILDING OPERATIONS 3/4.9.1 DELETED 3/4.9.2 DELETED 3/4.9.3 DELETED 3/4.9.4 DELETED 3/4.9.5 DELETED 3/4.9.6 DELETED 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING ....... ........... 3/4 9 1 3/4.9.8 DELETED 3/4.9.9 DELETED 3/4 9.10 DELETED 3/4.9.11 WATER LEVEL. SPENT FUEL P00L........................... 3/4 9 2 3/4.9.12 DELETED 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L.................... 3/4 9 3 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION................. 3/4 9 4 FIGURE 3.9 2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2........................................... 3/4 9 5 FIGURE 3.9 3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3........................................... 3/4 9 6 FIGURE 3.9 4 SPENT FUEL POOL RACK REGION LOCATIONS.................. 3/4 9 7 3/4.9.15 DELETED 3/4.9.16 SPENT FUEL P0OL COOLING . DEFUELED..................... 3/4 9 8 3/4.10 DELETED 3/4 11 DELETED HADDAM NECK II Amendment No.125.148,158.179.180.195 M3 l

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BASES j i SECTION PAGE 3/4.0- APPLICABILITY 3.0.1 ......................................................B 3/4 0 1 3.0.2 ......................................................B 3/4 0 2 3.0.3 DELETED.

3.0.4- ......................................................B 3/4 0 3 4.0.1 ......................................................B 3/4 0 4

4. 0. 2 . ......................................................B 3/4 0 4 l 4.0.3 ......................................................B 3/4 0 4 I 4.0.4 ......................................................B 3/4 0 5 3/4.1 DELETED 3/4.2 DELETED 3/4.3 DELETED l

.3/4.4 DELETED 3/4.5 DELETED 3/4.6 DELETED 3/4.7 DELETED l 3/4.8 DELETED 3/4.9 SPENT FUEL BUILDING OPERATIONS 3/4.9.1 DELETED 3/4.9.2 DELETED 3/4.9.3 DELETED 3/4.9.4 DELETED 3/4.9.5 DELETED 3/4.9.6 DELETED 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING....................B 3/4 9 1 3/4.9.8 DELETED 3/4.9.9 DELETED 3/4.9.10 DELETED 3/4.9.11 WATER LEVEL . SPENT FUEL PD0L.........................B 3/4 9 1

-3/4.9.12 DELETED 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L...................B 3/4 9 1 3/4.9.14 SPENT FUEL P0OL REACTIVITY CONDITION................B 3/4 9 1

-3/4.9.15 DELETED 3/4.9.16_ SPENT FUEL PDOL COOLING DEFUELED....................B 3/4 9 2 3/4.10 DELETED 3/4 11 DELETED HADDAM NECK III Amenument No.125.127.158.175.188.

493,195

U INDEX DESIGN FEATURES SECTION A P_A_GE L1 111E....................................................... 51

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SPENT FUEL STORAGE 5.2.1 CRITICALITY................................................ 51 5.2.2 DRAINAGE................................................... 5 2 l 5.2.3 CAPACITY................................................... 5 2

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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY............................................. 61 6.2 ORGANIZATION

6. 2.1. General Organizational Requirements. . . . . . . . . . . . . . . . . . . . . . . . 6 2 l 6.2.2- Facility Staff............................................. 6 3 l TABLE 6.2 1 MINIMUM SHIFT CREW COMPOSITION............................. 6 4 6.3 FACILITY STAFF QUALIFICATIONS.............................. 6 5 6.4: TRAINING................................................... 66 6.5 PROCEDURES'AND PROGRAMS 67 l 6.6 PROGRAMS AND MANUALS l 6.6.1 Radiation Protection Program............................... 68 6.6.2 Process Control Program (PCP).............................. 68 6.6.3 Radiological Effluent Monitoring and Offsite Dose Calcul ation Manual (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 i 6.6.4 Radiological Effluent Control s Program. . . . . . . . . . . . . . . . . . . . 6 10 l

.6.6.5 Radioactive Environmental Monitoring Program. . . . . . . . . . . . . . 6 12 6.6.6- Spent' Fuel Pool Cooling and Makeup Monitoring Program. .. .. 612 j 6.6.7 Technical Specification (TS) Bases Control Program........ 6 13 j

'6.7 REPORTING REQUIREMENTS-6.7.1 Occupational Radiation Exposure Report. . . . . . . . . . . . . . . . . . . . 6 14 i 6.7.2 Annual Radiological Environmental Operating Report. . . . . . . . 6 14 l 6.7.3 . Annual Radiological Effluent Release Report. . . . . . . . . . . . . . . 6 15 i'

6.8 HIGH RADIATION AREA............................ .......... 6 16 l l

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i HADDAM NECK IV Amendment No.125.155.158.170.181. j

-143,195 l

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L 1.0 DEFINITIONS

................................... NOTE - - -

The defined terms of this section appear in capitalized t9e and are applicable throughout these Technical Specifications. l

.............................................................................. l ACTION 1 1

1.1 ACTION shall be' that part of a Technical Specification which prescribes  ;

remedial measures required under designated conditions.  ;

CERTIFIED; FUEL HANDLER 1.2 A CERTIFIED FUEL HANDLER is'an individual who complies with provisions l of the CERTIFIED FUEL HANDLER training program required by Specification 6.4.1.

MEMBER (S) 0F THE PUBLIC 1,3 MEMBER (S) 0F THE PUBLIC shall include all pcrsons who are not l occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors, Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of.the site for recreational, occupational, or other purposes not associated with the plant.

OPERABLE OPERABILITY 1.4 A system, subsystem. train, component, or device shall be OPERABLE or l have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls.

electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component

, or device to perform its function (s) are also capable of performing i

their related support function (s),

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.HADDAM NECK' '11 Amendment No.125,193,195

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-1.0L DEFINITIONS (continue') d

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~RADI0 ACTIVE WASTE TREATMENT SYSTEMS z

1).5 : RADI0 ACTIVE WASTE. TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material in order to meet the requirements set forth in the REM 0DCM.

RADIOLOGICAL EFFLUENT MONITORING and 0FFSITE DOSE CALCULATION MANUAL (REMODCM)

- 1.6 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall be a manual l containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall be a manual containing the methodology and-parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid ' effluent monitoring instrumentation Alarm / Trip Setpoints. Requirements of the REMODCM are provided in Specification 6.6.3.  !

SITE BOUNDARY 1.7- The SITE BOUNDARY shall be that line beyond which the land is neither l

owned, nor leased,' nor otherwise controlled by the licensee.

MADDAM NECK 12 Amendment No.125.193,195 l

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I SPENT FUEL BUILDING OPERATIONS l 3/4'.9.7 CRANEiTRAVEL SPENT FUEL BUILDING l

I ~ LIMITING CONDITION FOR OPERATION l  !

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' 3.9.7 Loads > 1800 pounds shall be prohibited from travel over fuel j assemblies in the spent fuel pool.

l APPLICABILITY: With fuel assemblies in the spent fuel pool.

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l ACTION- '

With the requirements of the.above specification not satisfied.

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place the crane load in a safe condition.  ;

l SURVEILLANCERE00IREMENTS

~4.9.7 Administrative controls that' prevent the travel of loads > 1800

- pounds over fuel' assemblies shall be in place prior f.o lifting a load > 1800 pounds.

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' HADDAM NECK 3/4 9 1 Amendment No. 125.158.195 l L

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1 SPENT FUEL BUILDING OPERATIONS l 3/4.9.11' WATER LEVEL SPERT FUEL P0OL l f lfLIMITINGCONDITIONFOROPERATION 3.9.11. l> 20' feet.of. water shall be maintained over the top of fuel l assemblies seated in-the spent fuel pool racks.

APPLICABILITY: .Whenever fuel assemblies are in the spent fuel pool. l ACTION:

With the requirements of the above specification not satisfied, 1 a. suspend all movements of fuel assemblies and crane i- operations with loads over storage racks containing fuel, and

b. restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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SURVEILLANCE REQUIREMENTS 1

4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required level at least once per 7 days when fuel assemblies are in the spent fuel pool.

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'HADDAM NECK- 3/4 9 2 Amendment No.14 ,195 l

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- SPENT! FUEL BUIIIDING OPERATIONS- l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L-

' LIMITING CONDITION FOR' OPERATION-3.9.13 Prior to movement of a fuel assembly in the spent fuel pool, the

' boron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of _t 800 ppm.

l APPLICABILITY: Whenever a fuel assembly is moved in the spent fuel- pool. I ACTION:

1 With the boron conceiltration < 800 ppm. suspend the movement of l 4 all. fuel in the spent fuel pool.

SURVEILLANCE REQUIREMENT 4.9~13 Verify that the boron. concentration is 3 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to any movement of a fuel assembly in the spent fuel pool and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter during fuel movement.

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i HADDAM NECK 3/4 9-3 Amendment No.4 % 195 l 4

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SPENT FUEL BUILDING' OPERATIONS l 3/4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION l LIMITING CONDITI'ON FOR OPERATION 3.9.14. The reactivity. condition of the spent fuel pool shall be such that K,tr'is _< 0.95 at all times.  :

-APPLICABILITY: Whenever fuel is in the spent. fuel pool. l ACTION:

Immediately initiate actions to correct the loading error if the placement of fuel assemblies does not meet the requirements of Figure 3.9 2, Figure 3.9 3, and Figure 3.9 4.

SURVEILLANCE REQUIREMENT 4.9.14- Ensure that all fuel assemblies to be placed in the spent fuel pool are within the enrichment and burn up limits of Figure 3.9 2 (Region 2) and Figure 3.9 3 (Region 3) by checking the assembly's design.and burn up documentation. Region locations are shown in Figure-3.9 4.

HADDAM NECK 3/4 9 4 Amendment No. E MS,195 l l

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5 3.0 -35 4.0 4.5 5.0 AVERAGE ASSEMBLY INITIAL NOWINAL ENRICHWENT (WT I - U235)

FIGURE 3,9 2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2

_ HADDAM. NECK 3/4 9 5 Amendment No.175.1SS,195 l l'

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l. FIGURE 3.9 3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3

_HADDAM NECK 3/4 9 6 Amendment No.115.lBS.195 l j'

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l SPENT' FUEL BUILDING OPERATIONS l 1

l ,,,,E I I l l 1  ! ! l , . ll l l kb k d 1 I 8

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I t 4-- N FIGURE 3,9 4 SPENT FUEL P0OL RACK REGION LOCATIONS HADDAM NECK 3/4 9 7 Amendment No.175,188,195 l

i lSPENTFUELBUILDINGOPERATIONS l L 3/4 '. 9.16 SPENT FUEL' POOL COOLING DEFUELED LIMITING CONDITION FOR OPERATION' L3.9.16i The spent fuel pool coolant ' temperature shall be' maintained at 5 150 'F. l l 1

APPLICABILITY: ' Whenever fuel . assemblies are stored in the spent fuel pool.

ACTIQ 3:

With the spent fuel pool coolant temperature not within limit:

a. Immediately initiate action to. restore the spent fuel pool coolant-temperature to within limit, and
b. Immediately verify that a spent fuel pool makeup water source is available, and

-c. Within 7 days. restore the spent fuel pool coolant temperature to within the limit.

SURVEILLANCE REQUIREMENTS

'4.9.16 At 1. east once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. verify that the spent fuel pool coolant temperature is 5 150 *F . l HADDAM NECK 3/4 9 8 Amendment No.M 3.i95 l

Q l l

r' J/4.9SPENTFUELBUILDINGOPERATIONS l BASES _

3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING l The restriction on movement of loads in excess of the. weight of a fuel and . l control rod asse-T.aly and associated handling tool over other fuel assemblies

~

in the spent fuel pool ensures that in the. event ~ this load is dropped: (1) the activity release will be limited oc that contained in a single fuel assembly.

- and (2) any-possible distortion of fuel in the spent fuel pool racks will not result in a critical array, -This is consistent with the activity release l assumed in the safety analysis.

The restriction also ensures that the effects of any load drop on the spent fuel pool structural integrity is enveloped by the load drop analysis (Holtec Report HI 941225, Rev. 0, " Accident Analysis Report for CY Spent Fuel Racks,"

Dr. Yu Wang. Item 11. Holtec Project 40264) performed for License Amendment 188.

3/4.9.11 _WATER LEVEL SPENT FUEL POOL The restrictions on minimum water level ensure that sufficient water inventory is available, so that in the event of a complete loss of forced cooling, the time to boil is-> 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (as of December 1997), based on an initial spent

' fuel pool temperature of 150 *F and no evaporative cooling.

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P0OL The limitations of this specification ensure that, in the event of any fuel handling accident in the spent fuel poc', K,,, will remain s 0.95. l l

3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION i 1

The. limitations described by Figures 3.9 2, 3.9 3, and Figure 3,9-4 ensure  !

that the~ reactivity of fuel assemblies. introduced into the spent fuel pool racks. 'with no credit taken for soluble boron in the spent fuel pool, are conservatively within the, assumptions of the safety analysis.

HADDAM NECK B3/4 9 1- Amendment No.125,158,175,188,193, 195 l

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l; ~ SPENT FUEL BUILDING OPERATI'ONS' ,

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' BASES' ~

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l L E 3/4'. 9.16 -- 1 SPENT FUEL POOL COOLING' DEFUELED' y

a ;The primary basis for 150l*F is -to limit the'rmal stresses on the spent fuel

" pooliconcrete_ structures due'to the' differential _ temperature across the L interna 1 Land exterio'r surfaces of the walls and floor. The basis is further

. discussed in License Amendment-No. 188.

?As of. May 1998,"the spent fuel heateload was calculated' to be

-< 2.3E+06 BTU /hr. Each heat exchanger has the capability of removing this

.hsatiload. -One spent fuelLpool heat exchanger and one spent . fuel pool cooling pump that can be. operated' intermittently,'istsufficient.to remove the decay heat load; LAssuming no forced or evaporative cooling, the calculated Ma(1998 heatup rate t-Lis .approximately 1.2 *F/hr. Thus, in the event.of; complete loss of forced Lcooling and assuming an initial spent fuel-pool temperature of 150 *F, the time"to boil, assuming'no evaporative cooling, is > 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Therefore, sufficient stime. exists to either reestablish forced _ cooling or to provide

~ ~

-makeup. to maintain the spent fuel pool inventory.

l;_

i p i 4

HADDAM NECK- 83/4 9 2 -Amendment No. 125,175.188.193. 195 L i h l L

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1.

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5.0. DESIGN' FEATURES l l 5.1 Site s =The. plant ' site, consisting of approximately 525 acres, is located in the l

Town of Haddam, Middlesex County, Connecticut, on the east bank of the Connecticut River.

2

-5.2 Spent Fuel Storage l 1

-5.2.1 Criticality.

l The spent fuel storage racks are made up of 3 regions which are designed and shall be maintained with:

l

a. For Region-1, a .;ominal 10.98 inch (East / West) and a nominal 10.142 inch (North / South) center to center distance including neutron absorber surrounding each assembly to ensure a K,rr 5 95 when flooded with unborated water. Fuel'with a maximum nominal enrichment of 5 weight percent U 235, without regard for fuel burnup, may be stored in this region. The location of Region 1  !

within the Spent Fuel Pool is shown in Figure 3.9-4. '!

b. For Region 2 a nominal 9.00. inch center to center distance l including neutron abscriier surrounding each essembly to ensure a

~

K,,, 5 .95 when flooded with unborated water. Storage of fuel in Region 2 must be in accordance with the requirements of Speci fication. 3.9.14. The location of Region 2 within the Spent ,

. Fuel Pool is shown in Figure 3.9 4.

c. For Region 3, a nominal 10.75 inch center to center distance to
ensure a K,,,5 95 when flooded with unborated water. No credit is

.taken-for the neutron absorber contained within the racks of this region. . Storage of fuel in Region 3 must be in accordance with ,

the requirements of Specification 3.9.14. The location of Region 3 within the Spent Fuel Pool is shown in Figure 3.9 4.

i HADDAM NECK 51 Amendment No. 125.112.175.188.

M3.195 l

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fi- 5.2 Spent Fuel. Storage -(continued) 5.2.2 Drainaae The spent fuel storage pool is designed and'shall be maintained to prevent inadvertent draining of the pool below elevation 27.0 feet MSL.

5.2.3 - Caoacity The spent fuel storage pool is designed and Shall be maintained with a storage capacity limited to no more than 224 storage locations in Region: 1, 560 storage locations in Region 2, and 696 storage locations

, -in Region 3 for a total of 1480 st'orage locations.

i HADDAM NECK. 52 Amendment No. 125.142.175.188.

-lW 195 I

L 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility _

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

6.1.2 The Unit Director or his designee, in accordance with approved

. administrative procedures, shall approve each proposed _ test or experiment, and each set of fuel movements or load movements over the spent. fuel _ pool, prior to implementation and shall approve modification to systems, structures, or components that affect the safe storage of irradiated fuel.

6.1.3- The Shift Manager (SM) shall be responsible for the operational command function.

l 4

HADDAM NECK 61 Amendment No. 125,155.158,191, t 493,195

l p 6.0 ADMINISTRATIVE CONTROLS 1 I

i '642 Organization I

6.2.1 General Oroanizational Reauirements Unit organizations shall be established for unit operation and corporate management, respectively. These organizations shall include positions for activities affecting the safe storage of irradiated fuel.

a. Lines of authority, responsibility, and communication shall be I 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, I as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, i and job descriptions for key personnel positions, or in equivalent < l forms of documentation. These requirements shall be documented in i the Connecticut Yankee Quality Assurance Program (CYQAP).
b. The Unit Director shall have overall responsibility for the unit, and shall have control over those onsite activities necessary for maintenance and storage of irradiated fuel in a safe condition.
c. The VP Operations and Decommissioning shall have corporate  !

responsibility for overall plant nuclear safety and shall take any l measures needed to ensure acceptable performance of the-staff in 1 operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the CERTIFIED FUEL HANDLERS and 2 Equipment Operators, and those who carry out health physics and  !

quality assurance functions, may report to the appropriate onsite I manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.

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i HADDAM NECK 62 Amendment No. 125.155.191.

493,195

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i I 6.2- Organization (continued) ,

I i

6.2.2 Facility Staff

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown'in Table 6.21.

l

b. At least one person qualified to stand watch in the control room (a CERTIFIED FUEL HANDLER or an Equipment Operator) shall be l present in the control roon when irradiated fuel is in the spent fuel pool .
c. An individual qualified in radiation protection procedures
  • shall be on site during fuel handling operations.
d. All fuel handling operations or movement of loads over storage racks containing fuel shall be observed and directly supervised by i a CERTIFIED FUEL HANDLER who has no other concurrent  !

responsibilities during this operation.  ;

e. Administrative procedures shall be developed and implemented to l limit the working hours of facility staff who perform functions  !

important to the safe storage and handling of irradiated fuel. l l

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

i

  • The individual qualified in radiation protection procedures may be less than the ,ninimum 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.

l HADDAM NECK 63 Amendment No. 125.179.192,195

1 l

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TABLE 6.2 1 (page 1 of 1) l MINIMUM SHIFT CREW COMPOSITION l l

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION j Shift Manager 1* l 1

Equipment Operator 1 The shift crew's composition may be one less than the minimum requirements of l Table 6.21 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 i accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew's composition to within l the minimum requirements'of Table 6.21. 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 -l operations, i

HADDAM NECK- 64 Amendment No. -125.192,195

g 7 6.5 ADMINISTRATIVE CONTROLS' ,

6.3 Facility Staff Qualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications' of ANSI N18.1 1971 for comparable positions.

6.3.1.1 The position of Health Physics Manager shall meet the following

~

1 minimum qualifications: I

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 technicil experience must total a minimum of nine years.

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l HADDAM NECK 65 Amendment No. 125,155.192.195

i I

6.0 . ADMINISTRATIVE CONTROLS l 6.4 Training l l

t <

6.4.1 An 11RC approved retraining and _ replacement training program for l the CERTIFIED FUEL HANDLERS shall be maintained under the

direction of the Unit Director.

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i HADDAM NECK 66 Amendment No. 125.135,155,192.195

6.0 %DMINISTRATIVE CONTROLS

~6.5 Procedures and Programs 6.5.1 Written procedures shall .be established., implemented, and maintained covering the activities referenced below:

a. The procedures applicable to the safe storage of spent fuel recommended in Regulatory Guide 1.33. Appendix A, (Revision 2 February 1978).
b. All programs specified in Specification 6.6.
c. Fire Protection Program implementation.
d. Quality controls for effluent monitoring. using the guidance in Regulatory Guide 1.21 Rev.1. June 1974.
e. The use or operation of RADWASTE TREATMENT SYSTEMS utilizing the guidance provided in the REMODCM.

6.5.2 Each procedure of Specification 6.5.1 and program of Specification 6.6 and changes thereto, shall be independently reviewed in accordance with administrative procedures and approved by the Unit Director or designee prior to implementation.

6.5.3 Temporary changes to procedures of Specification 6.5.1 may be made provided: l

a. The intent of the existing procedure is not altered: l
b. .The change is approved by a member of the plant management staff and a CERTIFIED FUEL HANDLER: and
c. The change is documented, reviewed and approved by the Unit l Director or designee within 14 days of implementation.

=

HADDAM NECK 67 Amendment No. 125.155.158.181.

191,192.192. 195

h

,e 6.0 ADMINISTRATIVE CONTROLS i I

6.6 Progrsin. and Manuais 6.6.1 Radiation Protection Procram  !

A' program for_ personnel radiation protection shall be prepared

consistent with the requirement of 10 CFR 20 and shall be approved, maintained, and adhered to for all operations involving personnel' radiation exposure.

6.6.2 Process Control Procram (PCPF The PCP shall contain the current formulas, sampling, analyses, tests,  ;

and determinations to be made to ensure that processing and packaging of l solid radioactive wastes will be accomplished to ensure compliance with l 10 CFR Parts 20 61, and 71: state regulations; burial ground '

requirements: and other requirements governing the disposal of solid radioactive waste.- l ChangesLto the PCP:

a. Shall be documented and records of reviews shall be retained. '

This documentation shall contain:

1. sufficient information to support each change, together with '

.the appropriate analyses or evaluations to justify the change; and

2. a determination that each change. maintains the overall conformance.of the solidified waste product to existing requirements of_. Federal. State. -or other applicable regulations; and
b. ~ Shall become effective after the change is independently reviewed in accordance with administrative procedures end approved by the Unit Director or designee.

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HADDAM NECK 68 Amendment No. 125.155.158.191,195

T l

r 6.6 Programs and Manuals (continued) 6.6.3 Radiolooical Effluent Monitorina and Offsite Dose Calculation Mpnual (REMODCM)

The REMODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program.

The REMODCM shall also contain the Radioactive Effluent Controls and "

Radiological Environmental Monitoring Program required by Specifications 6.6.4 and 6.o.5, respectively, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required under Specifications 6.7.2 and 6.7.3.

Changes to the REM 0DCM:

a. Shall De documented and records of review shal' be retained. This documentation shall contain:
1. sufficient information to support each change together with the appropriate analyses or evaluations to justify the change: and
2. a determination that each change maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR 50 Appendix I, and that the change will not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations:
b. Shall become effective after the change is independently reviewed in accordance with adnunistrative procedures and approved by the l Unit Director or designee; and
c. Shall be submitted to the NRC in the form of a complete legible copy of the entire REMODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change was made to the REMODCM.

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

MADDAM NECK 69 Amendment No. 125,155,158,170 Mh492,195 I

f l

g 6.6 Programs and Manuals (continued) 6.6.4_ Radioactive Effluent Controls Proaram This program conforms to 10 CFR 50.36a for the control of radioactive ,

l effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from l j radioactive effluents as low as reasonably achievable. The program l shall be contained in the REMODCH, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program '

limits are exceeded. The program shall include the following elements:

l

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests J l and setpoint determinations, in accordance with the methodology

! described in the REMODCH:

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to the pre 1994 concentration values in 10 CFR Part 20, Appendix B (to 20.1 to 20.602), Table II, Column 2:

L

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters described in the REMODCH:
d. Limitations on the annual and quarterly doses or dose commitment

, to a MEMBER OF THE PUBLIC from radioactive materials in liquid i

effluents released from the facility to unrestricted areas, ccnforming to 10 CFR Part 50, Appendix I; ,

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters described in the REMODCH (performed at least every 92 days);
f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR Part 50 Appendix I:

HADDAM NECK 6 10 Amendment No.195 I

l

. . 1

- 6.6 Programs and Manuals (continued.'

l l 6.6.4 Radioactive Effluent Controls Prooram (continued) l 1

l

g._ Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond ,

the SITE BOUNDARY shall be as follows: .

i

1. for noble gases: 5 a dose rate of 500 mrem /yr to the total body and 5 a dose of 3000 mrem /yr to the skin: and
2. for t'ritium and all radionuclides in particulate form with half lives > 8 ' days: 's to a dose rate of 1500 mrem /yr to any organ:
h. Limitations on the annt!al and quarterly air doses from noble gases released in gaseous effluents from the unit to areas beyond the l SITE B0UNDARY, conforming to 10 CFR Part 50, Appendix I:
1. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each facility to areas beyond the SITE BOUNDARY, conforming to 10 CFR j Part 50, Appendix I; and i
j. . Limitations on the annual dose or dose commitment to any MEMBER OF I THE PUBLIC at points beyond the SITE B0UNDARY due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190. -

4 I

HADDAM NECK- 6 11 Amendment No.195

~ 6.6 Programs and Manuals (continued) 6.6.5'Radioloaical Environmental Monitorina Proaram This program monitors'the radiation and radionuclides in the environs of the facility. The_ program shall provide representative measurements of radioactive materials in the highest potential exposure pathways,

verification of the accuracy of the effluent monitoring program, and modeling of environmental exposure pathways. The program shall be contained in the REMODCM and shall include the following:
a. Monitoring, sampling. analysis, and reporting of radiation and radionuclides'in the environment in accordance with the methodology and parameters described in the REMODCH: and j a
b. Participation in an Interlaboratory Comparison Program to ensure

-that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program

.for environmental monitoring.

6.6.6 Soent Fuel Pool Coolina and Makeuo Monitorina Proaram This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool water makeup

. capability be monitored and maintained. Thi_s program shall provide j

. reasonable assurance that'the equipment, components, systems and water sources, including spent fuel pool water chemistry, used for spent fuel l poo.1 cooling and for maintaining spent fuel pool water level are capable of fulfilling.their intended functions and are protected against ,

-freezing. '

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HADDAM NECK 6 12 Amendment No. 193,195 '

f L.  !

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l- 6.6 Programs and Manuals (continued) l I

6.6.7 Technical Specifications (TS) Bases Control Proaram l

This program provides a means for processing changes to the Bases of i these -Technical Specifications. l a.. Changes to the Bases of the.TS 'shali be made under appropriate administrative controls and reviews.  !

b. -Changes may be made to Bases without prior NRC approval, provided )
the changes do not involve either of the following:
1. a change in the TS incorporated in the license: or
2. a change to the updated FSAR or Bases that involves an

, .unreviewed safety question as defined in 10 CFR 50.59.

c. The Bases Control Program shall'contain provisions to ensure that

.the Bases are maintained in a manner that is consistent with the FSAR.

-d. Proposed changes that do not meet the criteria of Specification 6.6.7.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 that is consistent with 10 CFR 50.71(e).

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-HADDAM NECK 6 13 Amendment No. 195 I

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L 1 6 0i l ADMINISTRATIVE. CONTROLS' r  !

I Reporting Requirements L6.7:

iThe following . reports shall. be submitted in accordance with 10 CFR 50.4.

l

6;7.1 Occuoational Radiation Exoosure Report AnL0ccupational Radiation Exposure Report covering the activities of the 1

facility during the previous calendar year shall be submitted by May 1 of each year. A' tabulation on an annual-basis of. the number of station, utility, and other personnel (including contractors) receiving exposures

  1. 100 mrem /yr and their associated' person rem exposure according to work-andijob functions:(e.g.,. decontamination and decommissioning, fsurveillance, routine maintenance, special maintenance (describe maintenance), waste processing and spent Tuel movement). This tabulation' supplements' the requirements of 10 CFR' 20.2206. The dose assignments to various duty functions may be estimated based on self reading dosimeter.-thermoluminescent dosimoter (TLD), or film badge measurements. Small ' exposures totaling < 20% of the individual total do'se need not be accounted for. In the aggregate, at least 80% of.the'

- total lwhole body dose received from external sources should be assigned

~to specific major work functions.  !

6., 2 Annual Radioloaical Environmental Ooeratina Reoort The Annual Radiological Environmental Operating Report covering the  ;

activities of the facility during the previous calendar year shall be l

. submitted prior to May'1 of each year. The Report shall include

~ summaries, interpretations and analyses of trends of the results of the i Radiological' Environmental Monitoring Program for. the reporting period.

The material provided shall be consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation-Manual (REMODCM)'.

hhe Annual Radiological Environmental Operating Report shall include the results of. analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables-and figures in the REMODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that.some individual results are not available for inclusion with the report, the submitted report shall note and -explain the reasons for. the missing results. The missing data shall be submitted in a supplementary report.

6 14 Amendment No. 125.155,192,195 L MADDAM NECK t 1

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7 6.7 Reporting Requirements (continued)  !

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6.7.2 Annual Radioloaical Environmental Ooeratina ReDort (continuedl  ;

! -The Annual Radiological Environmental Operating Report shall include licensee . initiated changes to the' REM 0DCM during the period of the L report as ' described in Specification 6.6.3, or these changes shall be ,

submitted concurrently.

6.7.3 Annual Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the ,

facility shall be submitted in accordance with Iv CFR 50.36a. The j Report shall include a summary of the quantities of radioactive liquid '

and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the REM 0DCM and Process Control Program.

The Radioactive Effluent Release Report covering the activities during the previous calendar year shall be submitted by May 1 of each year.

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! HADDAM NECK 6 15 Amendment No. 125.155.158.170.

493,195 l

h 6.0 ADMINISTRATIVE CONTROLS 6.8 High Radiation Area l

6.8.1 Pursuant to 10 CFR 20.1601(c), in lieu of the " control device" or " alarm signal" required by 10 CFR 20.1601, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is > 100 mrem /h but 5 1000 mrem /h at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and l conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

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I*ndividuals qualified in radiation protection procedures (e.g., Health

_ Physics 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 5 1000 mrem /h, provided they are otherwise following l plant radiation protection procedures for entry into such areas.

l 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 j 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.

l c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device and 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.

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l HADDAM NECK 6 16 Amendment No. 125,155,192. 195

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6.8 Hioh Radiation Area ~(continued) 6.8.2 In addition to the requirements of! Specification 6.8.1, areas accessible to personnel with radiation { levels > 1000 mrem /h at 30 cm (12 in.) from the radiation source or from any surface which the radiation' penetrates shall be provided with locked doors to prevent unauthorized entry, and J the keys shall be maintained under the administrative control of the 1 Shift Manager on duty and/or health physics supervision. Doors shall l-remain locked.except during periods. of access by personnel under an approved RWP that specifies the dose rate levels in the.immediate work areas and the maximum allowable' stay time for individuals in those areas. In lieu of t'ie stay time specification of the RWP, direct or 4 remote (such .n 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.

. 6.8.3. For individual high radiation areas accessible to personnel with

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radiation levels of greater than 1000 mrem /h that are located within large areas, such as PWR containment..where no enclosures exists for  !

purposes of locking, and where no enclosure can be reasonably j 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 17 Amendment No. 125.155.158,193.195 a

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