Text

Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant
	ML20202D152
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1998
From:	Weiss S; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20202D130	List: ML20202D126; ML20202D152; ML20202D162;
References
	NUDOCS 9902010320
	Download: ML20202D152 (132)
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UNITED STATES 3

4 NUCLEAR REGULATORY COMMISSION

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E WASHINGTON. D.C. 20555-4001 s...../

v CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 1

' CONNECTICUT YANKEE ATOMIC POWER STATION 4

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.193 l

Ucense No. DPR 4 1.

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

The application for amendment filed by the Connecticut Yankee Atomic Power A.

Company (CYAPCO or the licensee) dated May 30,1997, as supplemented on May 7,1998 and June 18,1998, 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;

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B.

The facility will be maintained in conformity with the application, as amended, 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 vill 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 by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.B.(3), 2.C.(1),

2.C.(2), 2.C.(3). 2.C.(4) and 2 '7) of Facility Operating Ucense No. DPR-61 are j

-hereby amended to read as fol.,us:

j B.(3) CYAPCO, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive,

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possess and use at any time any byproduct, source and special nuclear material as

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sealed neutron sources for reactor startup (possession only), sealed sources for reactor instrumentation (possession only), and radiation monitoring equipment calibration, and j

as fission detectors in amounts as required; 9902010320 990630 PDR ADOCK 05000213 u

PDR

2 C.(1)

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

C.(2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.193, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical Specifications.

C.(3)

Deleted by Amendment No. 29 C.(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 10,1990, 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 approval if these changes do not reduce the effectiveness of the fire protection for facilities, systems, and equipment which could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.

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C.(7)

Fuel Movement The movement of special nuclear material used as reactor fuel into the containment is prohibited.

3.

This license amendment is effective as of the date of its issuance and shall be implemented no later than 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: June 30, '1998 1

ATTACHMENT TO LICENSE AMENDMENT NO.193 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 i

The Appendix A Technical Speci.ications have been revised for the Connecticut Yankee Atomic Power Station.' The Index, Sections 1 through 5 and Bases have been extensively revised and the pages retyped. These sections shou!d be replaced in their entirety. The previous Technical Specifications pages should be removed and replaced by the enclosed pages of the Technical Specifications.

REMOVE INSERT index Index Section 1 Section 1 Section 2 Section 2 Section 3/4 Section 3/4 Bases Bases Section 5 Section 5 6-11 6-11 6-12 6-12 5

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INDEX DEFfMfTinut SECTION P.ME J.0 DEFINITIONS ACTION '..............................

1.1 i

1-1 1.2 ANALOG CHANNEL OPERATIONAL TEST...............

1-1 1.3-DELETED 1.4 CHANNEL CALIBRATION................

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

1.6 DELETED 1-1 1.7 DELETED 1.8 CORE ALTERATION.......................... 1-3 1.9 DELETED 1.10 DELETED 1.11 DELETED 1.12 FREQUENCY NOTATION........................

1-3 1.13 DELETED 1.14 DELETED 1.15 MEMBER (S) 0F THE PUBLIC......................

1-4 1.16 DELETED 1.17 OPERABLE - OPERABILITY l

1-4 1.18 OPERATIONAL MODE - MODE....................

1-4 1.19 DELETED i

1.20 DELETED 1.21 DELETED 1.22 DELETED 1.23 RADI0 ACTIVE WASTE TREATMENTS SYSTENS 1-5 1.24 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) 1-5 1.25 DELETED 1.26 REPORTA8tE EVENT.........................

1-5 1.27 RHR LOOP.............................

1-5 l

I HA00AM NECK I

Amendment No. J S, 193 0413

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9 IEEX i

DEFINIT 10NS.

SECTION i

pqg l.28 DELETED SITE 80dNDARY...........................

1.29 1-6 i

1.30 SOURCE CHECK............................

16 1.31 DELETED l.32 DELETED 1.33 DELETED l.34 DELETED l

1.35 DELETED 1.36 DELETED 1.37 DELETED TABLE 1.1 FREQUENCY NOTATION....................

1-8 TABLE 1.2 OPERATIONAL MODES.......................

1-9

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t-HADDAM NECK II Amendment No. JU, JU, JU,193 f

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t IEEX SAFETY LIMITS Als LIMITING SAFETY SYSTEM SETTINGS l

SECTION pg 2.1 DELETED l

2.2 DELETED I

BASES SECTION PM 2.1 DELETED l

2.2 DELETED l

MADDAN NECK III Amendment No. J U, J M, 193 0413

INDEX LINITIM CoWITIONS FOR OPERATION A2 SURVEILLANCE REQUIREM SECTION pg(

3/4.0 APPLICABILITY i

l 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 J

4.0.1 3/4 0-2 4.0.2 3/4 0-2 4.0.3 3/4 0-2 4.0.4 3/4 0-2 4.0.5 DELETED 4.0.6 DELETED 1

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3/4.1 DELETED l

H400AM NECK IV Amendment No. #7, #7, JM,193

. 0413

INDEX LIMITING COMITIONS FOR OPERATION Af6 $URVEILLANCE REQUIREMENT SECTION-EAi[

j 3/4.2 DELETED 3/4.3 INSTRUMENTATION 3/4.3.1 DELETED 3/4.3.2 DELETED i

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HAD04N NECK V

Amendment No. J17. J#, J M.193 0413

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQ SECTION E81E 3/4.3.3 MONITORING INSTRUMENTATION.........................

-3/4 3-23 3/4.3.3.1 DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 SEISMIC INSTRUMENTATION............................ 3/4 3-27 TABLE 3.3-5 SEISMIC MONITORING INSTRUMENTATION.................

3/4 3-28 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-29 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION.....................

3/4 3-30 TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUMENTATION..........

3/4 3-31 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-32 3/4.3.3.5 DELETED 3/4.3.3.6 DELETED 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................

3/4 3-44 l

TABLE 3.3-9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................

3/4 3-45 TABLE 4.3-7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-47 3/4.3.3.8 RADI0 ACTIVE GASEOUS EFFtUENT MONITORING INSTRUMENTATION....................................

3/4 3-49 HADDAN NECK 0413 VI Amendment No. 177, 177,193

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INDEX LIMITING COMITIONS FOR OPERATION A W SURVEILLANCE REQUIREMEN SECTION gig TABLE 3.3-10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....................................

3/4 3-50 TABLE 4.3-8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-52 3/4.3.3.9 DELETED 3/4.3.4

. DELETED 3/4.4 DELETED i

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NA00AM NECK VII Amendunnt No. JJJ JJJ, JJJ, 193 0413

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THIS PAGE INTENTIONALLY BLANK s.

HADOAM NECK VIII Amendment No. JJJ, JJJ, JJS, o4t J/J, 193

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.__s 4._..

t IEEX LIMITIM C0WITIONS FOR OPERATION AM SURVEILLANCE REQUIR\\

l SECTION EME 3/4.5 DELETED t

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3/4.6 DELETED i

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I 3/4.7 PLANTS SYSTEMS i

3/4.7.1 DELETED i

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HADDAN NECK IX Amendment No. JJJ, JJJ. J7J 193 N13

INDEX LIMITING COISITIONS FOR OPERATION Ale SURVEILLANCE REQUIREMENTS i

SECTION E6G1 3/4.7.2 DELEIED 3/4.7.3 DELETED 3/4.7.4 DELETED t

3/4.7.5 SEALED SOURCE CONTANINATION...............

3/4 7-14 3/4.7.6 DELETED 3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 DELETED 3/4.7.10 DELETED 3/4.7.11 DELETED 3/4.7.12 DELETED 4

3/4.8 DELETED f

1 1

i Amendment No. JJJ, Jg, Jg, J7h', J/J 193 HADDAN NECK X

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INDEX LINITING COMITIONS FOR OPERATION Am SURVEILLANCE REQUIREM i

SECTION l

PAgg i

3/4.9 REFUELING OPERATIONS 1

3/4.9.1 BORON CONCENTRATION....................

l 3/4 9-1 3/4.9.2 INSTRUMENTATION......................

3/4 9-2 3/4.9.3 DECAY TIME........................ 3/4 9-3 FIGURE 3.9-1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE OFFL y

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.............

3/4 9-4 3/4.9.5 COMUNICATIONS...................... 3/4 9-5 3/4.9.6 MANIPULATOR CRANE.....................

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL.....................

3/4 9-8 low WATER LEVEL......................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST, AND PURGE EXHAUST BYPASS ISOLATION SYSTEM..........

3/4 9-10 3/4 9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-11 3/4.9.11 WATER LEVEL-STORAGE POOL................

3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM 3/4 9-13 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL...........

3/4 9-15 3/4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION 3/4 9-16 FIGURE 3.9-2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS

. 3/4 9-17 FOR REGION 2 FIGURE 3.9-3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS

. 3/4 9-18 FOR REGION 3 i

FIGURE 3.9-4 SPENT FUEL POOL RACK REGION LOCATIONS........

3/4 9-19 3/4.9.15 SPENT FUEL. POOL COOLING 3/4 9-20

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HAD0AM NECK XI Amendment No. JJJ, JJ7, JM, J7J, osts JJJ,193

INDEX LIMITING COM ITIONS FOR OPERATION AND SURVEILLANCE REQUIi SECTION i

EAg 3/4.10 DELETED 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION.....................

3/4 11-1 3/4.ll.l.2x DOSE, LIQUIDS.....................

3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.......................

3/4 11-3 3/4.11.2.2 DOSE, NOBLE GASES...................

3/4 11-4 3/4,11.2.3 DOSE, RADI0 ACTIVE NATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES.....

3/4 11-5 3/4.11.3 TOTAL DOSE......................

3/4 11-6 J

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HADDAM NECK XII Amendment No. JJJ J7J, J,pp,193

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INDEX SASES SECTION a

ggg 3/4.0 APPLICABILITY 3.0.1 B 3/4 0-1 3.0.2 B 3/4 0-2 3.0.3 DELETED' i

3.0.4 B 3/4 0-3 4.0.1 8 3/4 0 4 4.0.2 g 3/4 0 4 4.0.3 B 3/4 0-4 4.0.4 8 3/4 0 5 4.0.5 DELETED 4.0.6 DELETED References DELETED i

~3/4.1 DELETED 3/4.2 DELETED 3/4.3 INSTRUMENTATION 3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3 MONITORING INSTRUNENTATION 3/4.3.3.1 DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 SEISNIC INSTRLMENTATION B 3/4 3-2 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION B 3/4 3-2 3/4.3.3.5 DELETED i

3/4.3.3.6 DELETED 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUNENRATION B 3/4 3-3 3/4.3.3.8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTION B 3/4 3-3 3/4.3.3.9 DELETED 3/4.3.4-DELETED 3/4.4 DELETED HADDAN NECK XIII Amendment No. JJJ, JJJ, 193 0413

INDEX BASES SECTIDN f36E 4

3/4.5 D LETED 3/4.6 DELETED' 3/4.7 PLANT SYSTEMS 3/4.7.1 DELETED 3/4.7.2 DELETED 3/4.7.3 DELETED 3/4.7.4 DELETED 3/4.7.5 1

SEALED SDURCE CDNTAMINATIDN..........................

B 3/4 7-4 3/4.7.6 DELETED 3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 DELETED 3/4.7.10 DELETED 3/4.7.11 DELETED 3/4.7.12 DELETED I

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i NADOAM NECK XIV Amendment No. JJJ, JJF, J7J "J77.177,193 0413

INDEX 3ASES t

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SECTION PAGI 3/4.8 DELETED 3/4.9 REFUELING OPERATIONS 4

3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUNENTATION B 3/4 9-I 3/4.9.3 DECAY TINE B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......... B 3/4 9-1 3/4.9.5 COPMUNICATIONS B 3/4 9-1 3/4.9.6

' MANIPULATOR CRANE

................. B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING j

B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REN0 VAL AND COOLANT CIRCULATION B 3/4 9-2 3/4.9.9 CONTAINNENT PURGE SUPPLY, PURGE EXHAUST, AND PURGE EXHAUST BYPASS ISOLATION SYSTEM B 3/4 9-2 3/4.9.10 & 3/4.9.11 WATER LEVE$

REACTOR VESSEL AND STORAGE POOL......................... 8 3/4 9-3 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM B 3/4 9-3 3/4.9.13 MOVENENT OF FUEL IN THE SPENT FUEL POOL j

B 3/4 9-3 3/4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION B 3/4 9-3 3/4.9.15 SPENT FUEL POOL COOLING

............... B 3/4 9-3 3/4.10 DELETED 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS l

3/4.11.1.1 CONCENTRATION

................ B 3/4 11-1 3/4.11.1.2 DOSE, LIQUIDS

................ B 3/4 11-1 l

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE'

................ B 3/4 11-2 3/4.11.2.2 DOSE, NOBLE GASES

................ B 3/4 11-2 3/4.11.2.3 DOSE, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBEL CASES....... B 3/4 11-3 3/3.11.3 TOTAL DOSE

................ B 3/4 11-3 l

NADDAN NECK XV Amendment No. 7 4, J77, / M,

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l DESIGN FEATURES SECTION PAGE 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.......................

5-1 5.1.2 LOW POPULATION ZONE 5-1 FIGURE 5.1-1 EXCLUSION AREA BOUNDARY AND SITE BOUNDARY FOR LIQUID AND GASEOUS EFFLUENTS..............

5-2 FIGURE 5.1-2 LOW POPULATION ZONE x

5-3 5.2 DELETED 5.3 DELETED l

5.4 DELETED i

5.5 METEOROLOGICAL TOWER LOCATION................

5-1l 5.6 SPENT FUEL STORAGE 5.6.1 CRITICALITY.........................

5-4 5.6.2 DRAINAGE..........................

5-4 5.6.3 CAPACITY..........................

5-4 5.7 DELETED l

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HA00AM NECK XVI Amendment No. JJJ. 177. 1,77 193 M13 l

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TNIS PAGE INTENTIONALLY BLANK HADDAM NECK XVII Amendment No. ygg, ypp 193 l

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IllDil ADMINISTRATIVE CONTROLS ECTION PAE 6.0

' ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY...................

6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS..........

6-1 6.2.2 FACILITY STAFF...................

6-1 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION........... 6-3 6.3 FACILITY STAFF OUALIFICATIONS 6-4 6.4 TRAINING......................

6-5 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW CO M ITTEE (PORC)......

6-5 Function......................

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

6-6 Meeting Frequency j

6-6 i

Quorum.......................

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

6-6 Authority 6-7 i

Records 6-7 6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB).......

6-7 Function......................

6-7 Composition 6-8 Alternates.................'....

6-8 Meeting Frequency 6-8 Quorum.......................

6-8

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Review Responsibilities 6-9 HADDAN NECK XVIII Amendment No. 177, 177. IU 193 0413

INDEX ADMINISTRATIVE CONTROLS SECTION fAfti

. Audits Program Responsibilities 6-9 Records......................

6-10 6.6 REPORTABLE EVENT ACTION 6-10 6.7 DELETED 6.8 PROCEDURES AND PROGRAMS 6-11 6.9 REPORTING REOUIREMENTS 6.9.1 Routine Reports..................

6-13 DELETED Annual Reports...................

6-13 Annual Radiological Environmental Operating Report.

6-14 Annual Radioactive Effluent Report.........

6-15 DELETED DELETED Special Reports 6-17 6.10 RECORD RETENTION 6-17 6.11 RADIATION PROTECTION PROGRAM............6-18 6.12 HIGH RADIATION AREA 6-19 6.13__

RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)............

6-20 6.14 RADI0 ACTIVE WASTE TREATMENT............

6-20 6.15 DELETED 6.16 DELETED M400AM NECK XIX Amendment No. JJJ JJJ. J77, 177.

en 787. 143

9 SECTION I.0 DEFINITIONS l

HADDAM NECK 0414

1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are 3

applicable throughout these Technical Specifications.

ACTION 4

1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST 1.2 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERASILITY of alarm, interlock and/or trip functions.

CHANNEL OPERATIONAL' TEST shall include adjustments, as necessary, of the The ANALOG alarm, interlock and the required range a/or Trip Setpoints such that the Setpoints are within nd accuracy.

1.3 DELETED l

CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.

The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions, and may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel-behavior during operation by observation.

where possible, comparison of the channel indication and/or status withThis de other indications and measuring the same pa/or status derived from independent instrument channels rameter.

HADDAN NECK 1-1 Amendment No. JgJ, 193 0414

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DEFINITIONS e

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1.7-DELETED 1

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1 NADDAN NECK 1-2 Amendment No. Jgy, Jpp, jpg,193 un 6

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DEFINITIONS

-CORE ALTERATION 1.8 within the reactor vessel, with the vessel head removed and vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe position.

i 1.9 DELETED 1.10 DELETED 1.11 DELETED FREQUENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

1.13 DELETED l

4 HADDAM NECK 1-3 Amendment No. J/7 Jf7 193 0414

DEFINITIONS 2

i 1.14 DELETED i

MEMBERIS) 0F THE PUBLIC tionally asso(ciated with the plant. MEMBER'S') 0F THE PUBL 1.15 i

ees of the licensee its contractors, or vendors.This category does not include emp i

category are persons, who enter the site to service equipment or to mak deliveries.

for recreational, occupational, or other purposes not ass

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plant.

f 1.16 DELETED OPERABLE - OPERABILITY l

i 1.17 have OPERABILITY when it is capable of perform and when all necessary attendant instrumentation, controls, electrical i

are required for the systempower, cooling or seal water, lubrication or other i

subsystem, train, component or device to perform its function (s) are,also capable of performing their related suppo function (s).

OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE sive combination of core re(activity condition, power level, an i

reactor coolant temperature specified in Table 1.2.

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1.19 DELETED 1.20 DELETED i

NADDAN NECK 0414 1-4 Amendment No. 177.193 1

DEFINITIONS i

1.21 DELETED 1.22 DELETED RADIOACTIVE WASTE TREATMENT SYSTENS 1

l l.'23 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 LCO's set forth in those specifications.

RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATIO MANUAL (REMODCM) i 1.24 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall containing the site and environmental sampling and analysis programs for l

and for those radionuclides which lead to the highest potential r exposures to individuals from station operation.

An 0FFSITE DOSE CALCULA-TION MANUAL (ODCM) shall be a manual containing the methodology and param-eters to be used in the calculation of offsite doses due to radioactive effluent monitoring instrumentation Alarm / Trip Setpoints. gaseous Requirements of the REMODCM are provided in Specification 6.13.

1.25 DELETED REPORTABLE EVENT 1.26 A REPOP. TABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

RHR LOO _P l.27 An RHR LOOP consists of a Residual Heat Removal (RHR) pump, A dedi-cated RHR heat exchanger either from the same train or from the opposite train and all other necessary piping and components required to receive and cool reactor coolant.

1.28 DELETED 1

P HADDAM NECK 1-5 Amendment No. J M, 193 0414

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SECTIONS 3.7.] THROUGH 3.7.4-'

SECTIONS 4.7.1 THROUGH 4.7.4; TABLES 3.7-I THROUGH 3.7 TABLES 4.7-1 THROUGH 4.7-2; ND PAGES 3/4 7-1 THROUGH 3/4 7-13 i

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i' HADDAM NECK PLANT use

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i PLANT SYSTEMS 3/4.7.5 SEAIJD U m_CE CONTANINATION 1

LIMITING C0WITION FOR OPERATION 3.7.5 Each' sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

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

l 1.

Decontaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

{

b.

DELETED SURVEILLANCE REQUIREMENTS 4.7.5.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or F

b.

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

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.

j 4.7.5.2 Test Frecuencies - Each category of sealed sources (excluding startu ) sources anc fission detectors previously subjected to core flux) shall >e tested at the frequency described below, a.

Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:

1 I)

With a half-life greater than 30 days (excluding Hydrogen 3), and 2)

In any form other than gas.

i HADDAM NECK 3/4 7-14 Amendment No. W. 193 0419

l DEFINITIONS SITE BOUNDARY 1.29 The SITE. BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel activity. response when the channel sensor is exposed to a source of increased radio-1.31 DELETED 1.32 DELETED 1.33 DELETED 1.34 DELETED 1.35 DELETED 1.36 DELETED i

HADOAM NECK 1-6 Amendment No. JJJ, D 193

4 t

DEFINITI0lts l

)

i l.37 DELETED.

4 a

4 e

a 1

I a

i

)

1 4

3 I

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f k

HECK 1-7 Amendment No. JJJ, J/J, JJF.193

l

\\

TABLE 1.1 2

FREQUENCY NOTATION NOTATION FREQUENCV S

4 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W i

At least once per 7 days.

B 1

At least once per 14 days.

N At least once per 31 days.

SW At least once per 42 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

P Prior to each release.

'A' Not applicable.

I HADDAN NECK 0414 1-8 Amendment No. 177 193

2 TABLE 1.2 E

M OPERATIONAL MODES R

REACTIVITY

% RATED MODE AVERAGE COOLANT CONDITION.

K_.,

THERMAL POWER

TEMPERATURE

1. DELETED

2. DELETED

3. DELETED

4. DELETED t

5. DELETED

6. REFUELING **

less than or equal 0

to 0.94 less than or equal to 140*F I

e a,

.I i

D?

w t

8

Excluding decay heat.

t

- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

l

~ -

A SECTION 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

e 4A'-=*

F-,we m

,ii-gw L

a m.-.eR-s A.-,4-

--L----444---Jhl AJ k

4.5J.-h--a

..h2 sh---e 4m.a 4+

e-4---

4

-44 eam.-*L-*A s-a#.m.E..-p..-.-

A.2-.L mmm-..m

_am m

8 e

SECTION 2.0 AW BASES FOR SECTION 2.0 SAFETY LIMITS Af5 LIMITING SAFETY SYSTEM SETTINGS DELETED IN THEIR ENTIRETY HADDAM NECK PLANT

- is

3/4 LIMITING C0fEITIONS FOR OPERATION AM SURVEILLANCE REOU 3/4.0 APPLICABILITY 1IMITTMc rhamfTfnN FAR ADFRATfnN f

3.0.1 the succeedingCompliance with the Limiting Conditions for Operation contained in l

conditions; exc. specifications is required during the spe'cified applicable Operation, the associated ACTION requirements shall be met.ept that u 3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are t

not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

l 3.0.3 DELETED I

3.0.4 Entry into a specified applicable condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. Exceptions to these requirements are stated in the individual specifications.

i i

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HADDAM NECK 3/4 0-1 Amendment No. M.193 we

\\

l

1 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the specified otherwise stated in an individual Surveillance Requirement.

i 4.0.2 Each' Surveillance Requirement shall be performed within the 4

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

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERASILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

4 The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

l

[

4.0.4 the Surveillance Requirement (s) associated with the Limiting Operation have been performed within the stated surveillance interval or as otherwise specified.

l l

4 i

4 2

t HADDAN NECK one 3/4 0-2 Amendment No. JU.193 a

t 7

i

+

t i

t r

i I

I SECTIONS 4.0.5, 4.0.6; TABLES 4.0-1, 4.0-2; i

FIGURE 4.0-1; AND PAGES 3/4 0-3 THROUGH 3/4 0-8 DELETED 4

i n

HADDAM NECK we

..nk.> A x,

a sesens

- ~

2-.sa s

.w A---.

niw.--,4+-.A aa 4,e-s+,,ao 4Au v.m a-4 * - a

,e so-Jsu s w a es u.*

fman.,+nad44

.- w u, nm+we.ma--s.w,-s.a.2--r+4 m..a--

a w+...,-+as-n asu

+

e SECTIONS 3.1 AND 4.1 REACTIVITY CONTROL SYSTEMS DELETED IN THEIR ENTIRETY u

I 2

4

)

i

(

l NA00AM NECK use

i:

l

1..

1 i

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F SECfl0NS3.2AND4.2 i

POWER DISTRIBUTION LIMITS DELETED IN THEIR ENTIRETY i

i 1.

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HADDAM NECK osse i

I.

1 SECTIONS 3.3.I'THROUGH 3.3.3.2; SECTIONS 4.3.1 THROUGH 4.3.3.2; TABLES 3.3-1 THROUGH 3.3-4; TABLES 4.3-1 THROUGH 4.3-3; AND PAGES 3/4 3-1 THROUGH 3/4 3-26 DELETED r

i e

HADDAM NECK use

1 IllSTR1RIENTATION SElallIC INSTERRENTATION i 1M171bMt PaasntT1ng gna naggarf ag 3.3.3.3 shall be OPERABLE.The seismic monitoring system instrumentation shown in Table 3.

APPLICABILITY: At all times.

ACTION:

Nith the seismic monitoring system inoperable for more than 30 a.

days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the system to OPERABLE status.

i j

b.

DELETED l

)

SURVEILLANCE REQUIRDIENTS 4.3.3.3.1 The above seismic monitoring system shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL' CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3.4.

4.3.3.3.2 seismic event shall be restored to OPERABLE status within 24 h CHANNEL CALIBRATION performed within 10 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

If it is determined that the magnitude of the event exceeded the Operating Basis Earthquake, then a Special Report shall be prepared and submitted to the Comeission pursuant to Specification 6.g.2 within 14 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

t 1

I HADDAN NECK 3/4 3-27 Amendment No. 177, 193

TABLE 3.3-5 SEISNIC NONITORING INSTRUNENTATIQH h!NIMLM INSTRIMENTS A_@ SEMM LOCATIONS INSTRUNDffS NEASURENENT P'_TE

-OPERABLE

1. Triaxial Servo Accelerometer 0 to 0.59 1

(SSA-302) Basemat-Cable Vault

2. Digital Cassette Accelerograph (DCA-300)**

5 Volts 1

3. Response Spectrum Analyzer (RSA-50)**

5 Volts 1

4. Playback System

+ 5 Volts 1

(SMR-102)**

5. Seismic Warning Panel (SWP-300)**

N.A.

1

(

- All located in the Control Room HADOAM NECK 0417 3/4 3-28 Amendment No. /M.193

TABLE _4.3-4 SEISNIC NONITORING INSTRitlENTATION SURVEILUJ6CE REQUIREn

~

AMLOG CHAISIEL CHA>81EL CHAMEL OPERATIONAL INSTRtMENTS A2 SENSOR LOCATIONS QiLCK Q11BRATION TEST 1.

Triaxial Servo Accelerometer M

R SA (SSA-302) Basemat-Cable Vault 2.

Digital Cassette Accelerograph M

R SA (DCA-300)**

3.

Response Spectrum Analyzer M

R SA (RSA-50)**

4.

Playback System M

R SA (SMR-102)**

5.

Seismic Warning Panel M

R SA (SWP-300)**

- All located in the Control Room HADOAM NECK M17 3/4 3-29 Amendment No. f/(,193

~

l INSTRMENTATION METEOROLOGICAL INSTRMENTATION LIMITING COM ITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE.

i APPLICABILITY: At all times.

ACTION:

a.

With one or more required meteorological monitoring channels

)

I inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status, b.

DELETED l

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4 3-5.

I 1

MADDAN NECK 3/4 3-30 Amendment No. JU.193 M17

i l

TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUNENTATION MININim INSTRikDtT/ LOCATION OPERABLE 1.

Wind Speed a.

Baseline Elev.

33' I

b.

Nominal Elev. 200' 1

2.

Wind Direction a.

Baseline Elev.

33' I

b.

Nominal Elev. 196' 1

3.

Air Temperature a.

Baseline Elev.

33' 1

4.

Delta T*

a.

Nominal Elev. 120' I

b.

Nominal Elev. 200' I

Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation.

t HADOAN NECK 3/4 3-31 AmendmentNo.ff(193 M17

TABLE 4.3-5 METEOROLOGICAL N0NITORING INSTRUNENTATION SURVEILLANCE REQUIRENENTS INSTRUNENT/ LOCATION CHAMEL CHECK CHAMEL CALIBRATION 1.

Wind Speed a.

Baseline Elev. 33' D

SA b.

Nominal Elev. 200' D

SA 2.

Wind Direction l

a.

Baseline Elev. 33' D

SA b.

Nominal Elev.196' D

SA 3.

Air Temperature a.

Baseline Elev. 33' D

SA 4.

Delta T*

a.

Nominal Elev. 120' D

SA b.

Nominal Elev. 200' D

SA Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation.

T HADDAN NECK 3/4 3-32 AmendmentNo./f(,193 M17

... ~,

1 4

i SECTIONS 3.3.3.5, 4.3.3.5; TABLES 3.3-7, 3.3-8; 4.3-6; AND PAGES 3/4 3-33 THROUGH 3/4 3-43 DELETED l

i

/

. HADDAM NECK M17.

INSTRMENTATION RADI0 ACTIVE LIOUID EFFLUDIT NONITORING INiintatniATION LINITING COMITION FOR OPERATION 3.3.3.7 The radioactive liquid effluent monitoring ihstrumentation Setpoints set to ensure that ~the limits of Specificatio exceeded.

The Alarm / Trip Se'. points shall be determined in accordance with methodology and parameters described in the OFFSITE DOSE CALCULATION (00CM).

APPLICABILITY:

At all times *.

ACTION:

With a radioactive liquid effluent monitoring instrumentation a.

channel Alare/ Trip Setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTTON shown in Table 3.3-9.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days, and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

DELETED l

l SURVEILLANCE REQUIRENENTS 4.3.3.7.1 Each radioactive liquid effluent monitoring instrumentation SOURCE CHECK, CHANNEL CALIBRATION, and ANALOi operations at the frequencies shown in Table 4.3-7.

At all times means that channel shall be OPERABLE and in service on a permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the pur and performance of requwed tests, checks, calibrations or sampling.

HADDAM NECK one 3/4 3-44 Amendment No. J/7 179.193

2-TABLE 3.3-9

~

g RADI0 ACTIVE LIOUID EFFLUENT NONITORING INSTRUNENTATION NiR INSTRUMENT NININUN #

OPERABLE ACTION 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.

Waste and Recycle Test Tank Discharge Line 1

46 b.

DELETED l

2.

GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE R

a.

Service Water Effluent Line 1

48 i

h 3.

FLOW RATE MEASUREMENT a.

Waste and Recycle Test Tank Discharge Line 1

49 b.

DELETED I

g c.

Discharge Canal

=

N.h.

k e"

F l

g Discharge canal flow is determined by the use of pump curves.

y E.

(4

9

{

TABLE 3.3-9 (Continued 1 i

ACTION STATEMENTS i

ACTION 46 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that best efforts are made to repair-the instrument and that prior to initiating a release:

a.

At least two independent samples of the tank to be discharged are analyzed in accordance with Specification i

4.11.1.1.1, and; b.

The original release rate calculations and discharge valving are independently verified by a second individual.

s ACTION 47 DELETED 4

l ACTION 48 With the number of channels OPERABLE less than required by i

the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples of the service water effluent are collected and 4

analyzed for gross radioactivity (bet limit of detection of at least 3 x 10~9 or gamma) at a lower microcuries/al.

ACTION 49 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump

)

performance curves generated insitu may be used to estimate 1

l i

flow.

I i

2 J

4 l

i HA00AM NECK 3/4 3-46 Amendment No. JJJ.193 osse

TABLE 4.3-7 RAD 10 ACTIVE LIGUID EFFilFMT E9-ITORING INSTIH,pHTATION SukirEILLAME RFolll 2

3 nvii$

~

CMMEL INSTRUNENT CMNNEL SOURCE CMNNEL FUNCTIONAL CHECK StlECK CALIBRATION TEST 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Waste and Recycle Test Tank Discharge Line 0(1)

P R(2)

Q(3) b.

DELETED 2.

GROSS RADI0 ACTIVITY MONITORS PROVIDING l

ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.

Service Water Effluent Line O(1)

M R(2)

Q(3) 3.

FLOW RATE MEASUREMENT a.

Waste and Recycle Test Tank '

Discharge Line 0(1)

N.A.

R N.A.

b.

DELETED

{

I c.

Discharge Canal 0(4)

N.A.

s a

.f

?

W

?

t5 I

w

TABLE 4.3-7 (Continued)

{

TABLE NOTATION (1)

CHANNEL CHECK need only be performed daily when discharges are made from this pathway.

is in process.

The CHANNEL CHECK should be done when the discharge (2)

CHANNEL CALIBRATION shall be performed using a known radioactive liquid or solid. source whose strength is determined by a detector which has been calibrated to an NBS source.

known, reproducible geometry.

The radioactive source shall be in a (3)

The ANALOG CHANNEL OPERATIONAL TEST shall also demonstr room alarm annunciation occurs if any of the following conditions exist:

j j

1.

Instrument indicates measured levels above the alarm / trip setpoint.*

2.

Instrument indicates a downscale failure or circuit failure.

3.

Instrument controls not set in operate mode.

(4)

Pump status should be checked at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the purpose of determining flow rate.

Automatic isolation shall also be demonstrated annually for the test tank discharge monitor line.

l HADDAM NECK 3/4 3-48 Amendment No. J#,193 0418

INSTRUNENTATION 1

RADIDACTIVE GASEOUS EFFillmT NONITORING INSTRUNENTATION i

LIMITING CO M ITION FOR OPERATION i

3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with applicable Alarm Setpoints set ~to ensure that the limits of Specification 3.11.2.1 are not l

exceeded.

The setpoints shall be determined in accordance with the j

methodology and parameters as described in the 00CH.

}

APPLICABILIJJ: At all times *.

)

l ACTION:

4 With a radioactive gaseous effluent monitoring instrumentation a.

i channel Alarm Setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive j

gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the Alann Setpoint so it is acceptably l conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-10.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

DELETED l

SURVEILLANCE REQUIREMENT 4.3.3.8.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.

i At all times means that the channel shall be OPERABLE and in service on a continuous basis, except that outages of monitoring channels are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the purpose of l

maintenance and performance of required tests, checks, calibrations.

HADDAN NECK 3/4 3-49 Amendment No. 125. T78.1m om

TABLE 3.3-10 RADIDACTIVE GASE0US EFFttimT NOMITORING IMsinisaniATION NININUN INSTRUNENT CHANNELS OPERABLE ACTION 1.

MAIN STACK L

a.

Noble Gas Activity Monitor Providing Alam 1

50 b.

DEL'ETED i

c.

Particulate Sampler 1

51 d.

Stack Flow Rate Monitor 1

52 e.

Sampler Flow Rate Monitor 1

52 5

=

W W

I t

TABLE 3.3-10 (Continued)

ACTION STATEMENTS i

1 ACTION 50 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via the Waste Gas Holdup System may continue provided that best

. efforts are made to repair the instrument and that prior to initiating the release:

i (a) For the tank to be discharged, at least two independent

> samples of the tank's contents are analyzed; and, (b) The release rate calculations and discharge valve lineups are independently verified by a second individual.

4 Othentise, suspend releases from the Waste Gas Holdup System.

'i Releases from all pathways other than the Waste Gas Holdup System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION S1 With the number of channels OPERABLE less than required by i

the Minimum Channels OPERABLE requirement, effluent releases i

via this pathway may continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for i

periods of seven (7) days and analyzed for principal gamma i

emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period. Auxiliary sampling shall be established within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of declaring the channel j

INOPERABLE.

ACTION 52 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i i

-f

.MADOAM NECK 3/4 3-51 Amendment No.'MI,193

.4 m

TABLE 4.3-8 M

RADIDACTIVE GASE0US EFFLUENT NONITORING INSTRUNDtTATIO R

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK _

CALIBRATION

_ TEST 1.

MAIN STACK a.

Noble Gas Activity Monitor D(1)

N R(2)

Q(3) b.

DELETED I

c.

Particulate Sampler W

N.A.

t

,s*

d.

Stack Flow Rate Monitor D(1)

N.A.

R N.A.

E e.

Sampler Flow Rate Monitor D

N.A.

R N.A.

I f

l a

E t

7 w.

O.

r la

= -

TABLE 4.3-8 (Continued)

TABLE NOTATION

)

(1)

CHANNEL CHECK daily when releases exist via this pathway.

(2)

Calibration shall be performed using a known source whose strength is determined by a detector which has been calibrated to an NBS source.

These sources shall be in a known, reproducible geometry.

(3)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that c alarm annunciation occurs if any of the following conditions exist:

Instrument indicates measured levels above the Alarm Setpoint.

a.

l b.

Instrument indicates a downscale failure or circuit failure.

Instrument controls not set in operate mode.

c.

i HADDAM NECK 041s 3/4 3-53 AmendmentNo.Jg),193

~ _. _ _ _ _. _... _. _ _. _ _. _. _. _ _. _. _... _. - _. _ _.. _

t I

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SECTIONS 3.3.3.9, 3.3.4, 4.3.3.9.1, 4.3.4; i

i TABLE 3.3-11; AND PAGES 3/4 3-54 THROUGH 3/4 3-57 1

t DELETED t

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4

)

HAODAN NECK use

~. - -

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l SECTIONS 3.4 AND 4.4 REACTOR COOLANT SYSTEM DELETED IN THEIR ENTIRETY 1

i l

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HADDAN NECK 0418

i 1

1 i

i b

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1

)

SECTIONS 3.5 AND 4.5 4

l EMERGENCY CORE COOLING SYSTEMS i

4 a

DELETED IN THEIR ENTIRETY

)

1 1

t 4

NADRAN NECK use

e t

SECTIONS 3.6 AND 4.6 CONTAINMENT SYSTEMS DELETED IN THEIR ENTIRETY I

HADOAM NECK 0418

4 L

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i SECTIONS 3.8 AND 4.8 ELECTRICAL POWER SYSTEMS i

i DELETED IN THEIR ENTIRETY i

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3/4.9 REFUELING OPERATIONS 3/4.9.1 B0RON CONCENTRATION ITMfTIMc ratenTTfAM rna nprRaTfAM 3.9.1 The boron concentration of all filled unisolated portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure a K,, of 0.94 or less.

APPLICABILITY:

MODE 6*.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpa of a solution containing a minimum of 14000 ppe boron or its equivalent until K,, is reduced to less than or equal to 0.94.

canvrfi n amer ernssf arMrvic 4.9.1.1 The above reactivity condition shall be determined prior to:

Removing or unbolting the reactor vessel head, and a.

b.

Withdrawal of any control rod in excess of 3 feet from its fully inserted position within the reactor vessel except when control rod drag testing is being performed, at which time the reactivity condition shall be determined prior to the first control rod withdrawn in excess of 3 feet and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter until completion of the testing.

i v.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

HADCAN NECK 3/4 9-1 Amendment No. Id,193

- __-=-.

REFUELING OPERATIONS 3/4.9.2 INST **.ENTATION i

fTMf7fMC PAMnfTfnN rna ADrRaTfnN 3.9.2.a As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and contr 4

room when CORE ALTERATIONS or positive reactivity changes are taking place.

i When CORE ALTERATIONS or positive reactivity changes are not taking place, at least one Source Range Neutron Flux Monitor shall be OPERABLE and operating with a vi'sual indication in the control room and audible indication in the containment.

3.9.2.b As a minimum, two Source Range High Neutron Level Alarms (Containment Evacuation) shall be OPERABLE and operating with a minimum logic to audibly alarm in both the control room and containment of one (1) of two (2).

APPLICABILITY:

MODE 6.

4 ACTION:

With one of the above required monitors inoperable or not operating, a.

immediately suspend all operations involving CORE ALTERATIONS or 3

positive reactivity changes.

i b.

With both of the required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at i

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

}

tinevrfi e auer Ernif f arMrurc 4.9.2 Each source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

4 A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a.

b.

An ANALOG CHANNEL OPERATTONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

c.

HADDAM NECK 3/4 9-2 Amendment No. //J Jf7, JM,193 0620

REFUELING OPERATIONS 3/4.9.3 DECAY TINE LIMITING ColeITION FOR OPERATION 3.9.3.a

~

The reactor shall be subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

3.9.3.b Irradiated fuel shall remain in the reactor vessel for at least the time required in Figure 3.9-1 prior to movement to the spent fuel pool.

3 APPLICABILITY: During movement of irradiated fuel in the reactor vessel.*

f ACTION:

With the reactor subcritical for less than 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , suspend all operations a.

involving movement of irradiated fuel in the reactor vessel.

)

b.

With the combination of reactor hold time and cooling water temperature in the unacceptable region of Figure 3.9-1, suspend all operations involving movement of irradiated fuel from the reactor vessel to the spent fuel pool until the combination of reactor hold time and cooling water temperature return to the acceptable region of Figure 3.9-1.

SURVEILLANCE REQUIRENENTS A

4.9.3.1 The reactor shall be determined to have been subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor vessel.

4.9.3.2 Verify that the combination of reactor hold time and cooling water temperature are in the acceptable region of Figure 3.9-1 prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during transfer of irradiated fuel from the reactor vessel to the spent fuel pool.

Specification 3.9.3.b does not apply if less than 53 fuel assemblies are transferred to the spent fuel pool.

MADOAN NECK' 3/4 9-3 AmendmentNo.J#,1/4,193 mm 1

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REQUIRED IN-CORE DECAY TIME (HOURS) i,

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FIGURE 3.9-1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE OFFLOAD I

i ME 3/4 9-3a Amendment No. IM193 i

REFUELING OPERATIONS

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3/4.9.4 CONTAllBIENT BUILDING PENETRATIONS i1Mf71Mt PAMn1TIAM FAR ADreATfnN 1

3.9.4 The containment building penetrations shall be in the following j

status:

l 1

The equipment hatch installed and secured in place, a.

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A minimum of one door in the airlock is closed, and Each penetration providing direct access from the containment c.

4.

atmosphere to the outside atmosphere shall be, either:

i 1)

Closed by an isolation valve, blind flange, manual valve, or special device, or 2) j Se capable of being closed by an OPERABLE containment purge supply, purge exhaust, or purge exhaust bypass isolation valve.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within j

the containment.

4' j

ACTION:

With the requirements of the above specification not satisfied, immediately 3

1 suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building, other than placing an irradiated fuel l

assembly into a safe storage location.

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4.9.4 Each of the above required containment building penetrations shall be detensined to be either in its closed / isolated condition or capable of i

j being closed by an OPERABLE containment purge supply, purge exhaust, or i

- purge exhaust bypass isolation valve or capable of being closed by an OPERABLE airlock door within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prier t2 the start of and at least 1

once per 7 days during CORE ALTERATIONS or Lovement of irradiated fuel in i

the containment building by:

Verifying the penetrations referred to in Specification 3.9.4c are a.

in their closed / isolated condition, b.

Testing the containment purge supply, purge exhaust, and purge exhaust bypass isolation valves in accordance with Specification 4.9.9, and Verifying that at least one of the doors in the airlock is capable c.

of being closed.

H.A.D.OAM NECK 3/4 9-4 Amendment No. $,193

REFUELING OPERATIONS 3/4.9.5 C0fetMICATIONS I1M1T1MC PnMnfTinM rna nornaTinN 3.9.5 Direct communications shall be maintained between the control room and personnel at the refueling cavity manipulator crane area.

APPLICABILITY: During CORE ALTERATIONS.

ACTION:

{

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building other than placing an irradiated fuel assembly into a safe storage location.

siinvriie auer nroerrnrurwrs 4.9.5 Direct communications between the control room and personnel at the refueling cavity manipulator crane area shall be demonstrated within I hour prior to the start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS.

i 1

4 i

i HADDAN NECK 3/4 9-5 Amendment No. 75%193 l

4

REFUELING OPERATIONS 3/4.9.6 NANIPULATOR CRANE ITMfTfMA rnMnf77AM rnN OprDATTnN 3.9.6 The manipulator crane and auxilisry hoist shall be used for movement of control rod-drive shafts

or fuel assemblies and shall be OPERABLE with The manipulator crane used for movement of fuel assemblies having:

a.

1)

A minimum capacity of 1650 pounds, and 2)

An overload cut off limit less than or equal to 175 pounds above the indicated weight for wet conditions for a stainless steel clad fuel assembly with a full length RCCA inserted.

b.

The auxiliary hoist used for latching and unlatching control rod drive shafts having a minimum capacity of 1500 pounds.

APPLICABILITY: During movement of control rod drive shafts or fuel assemblies within the reactor vessel.

ACTION:

With the requirements for crane and/or hoist OPERABILITY not satisfied, place any fuel assembly or control rod in transit into a safe auxiliary hoist from operations involving the movement of control r shafts or fuel assemblies within the reactor vessel.

sinnvr1:I awr Ern##rerurvTt 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing a load test of at least 2063 exceeds 175 pounds above the indicated weight for wet conditions for a stainless steel clad fuel assembly with a full length RCCA inserted.

4.9.6.2 Each auxiliary hoist used for movement of control rod drive shafts within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations.

If loads greater than the weight of a stainless steel clad fuel assembly with an RCCA inserted are to be lifted within the reactor vessel with the auxiliary hoist then a load test will be perfonned for 1257, of the weight of the load to be lifted.

The RCCA's may be attached to the control rod drive shafts during some refueling evolutions.

HADDAM NECK un 3/4 9-6 Amendment No. JM,193 4

REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STon_ ace BUILDING IIMITING enMnf7fnN rne nornATinM 3.9.7 fuel assemblies in the storage pool. Loads in excess of 1650 pounds sh APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

With the requirements of the above specification not satisfied, a.

place the crane load in a safe condition.

b.

The provisions of Specification 3.0.3 are not applicable.

sinnvrriimuer nrniernrururs 4.9.7 Administrative controls that prevent the travel of loads in excess of 1650 pounds over fuel assemblies shall be in place prior to lifting a load in excess of 1650 pounds.

i 1

HADDAN NECK 3/4 9-7 Amendment No. 446, @,193

REFUELING OPERATIONS i

3/4.9.8 RESIN 1A1 NEAT REN0 VAL AM) C00LAKf CIRCULATION HIGN WATER LEVEL i 1N1T1MC Ptm1TinM rnD nDrDAT1bN 3.9.8.1 At least one RHR LOOP shall be OPERABLE and in operation.*

APPLICABILITY: M00E 6, when the wator level is greater than or equal to 23 feet above the top of the reactor vessel flange.

i ACTION:

With no RHR LOOP OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron j

concentration of the Reactor Coolant System and immediately initiate I

corrective action to return the required RHR LOOP to OPERABLE and operating status as soon as possible.

direct access from the containment atmosphere to the outside atmosph within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

cavr11:auer nrnaiferurwTs l

i 4.9.8.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify at least one RHR LOOP is in operation and circulating reactor coolant at a flow rate of greater than or i

equal to 2000 gps.

l The RHR LOOP may be removed from operation for up to I hour per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.

i HADOAM NECK 3/4 9-8 AmendmentNo.12V,193

REFUELING OPERATIONS LOW WATER LEVEL ifMfTfMc enunf7TDM rnD nerDATfnN 3.9.8.2 Two-independent RHR LOOPS shall be OPERABLE, and at least one RHR LOOP shall be in operation.

APPLICABILITY: M00E'6 when the water level is less than 23 feet above the top of the reactor vessel flange.

ACTION:

With less than the required RHR LOOPS OPERABLE, immediately a.

initiate corrective action to return the required RHR LOOPS to OPERA 8LE status, or establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible.

b.

With no RHR LOOP in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR LOOP to operation.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

cievrfieme r ernufgrurvrs 4.9.8.2.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify at least one RHR LOOP is in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpa.

4.9.8.2.2 The RHR LOOP not in operation shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

HADDAM NECK 3/4 9-9 Amendment No. IlJ,193 I

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REFUELING OPERATIONS 3/4.9.9 CONTAIMENT PlanGE SUPPLY. PtinGE EXHAUST. Ale PU l

ISOLATION SYSTEM 1TurTruc enuntrinu rna nornartnu 3.9.9 bypass isolation valves shall be OPERABLE.The containment purge sup APPLICABILITY: During CORE ALTERATIOlS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not safistied, a.

immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building, other than placing an irradiated fuel assembly into a safe storage location.

b.

The provisions of Specification 3.0.3 are not applicable.

siinvrtieauer ernitrarurutt 4.9.9 The containment purge supply, purge exhaust, and purge exhaust bypass isolation valves shall be verified OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to i

the start of and at least once per 7 days during CORE ALTERATIONS and prior to movement of irradiated fuel within containment by verifying that containment purge, bypass or exhaust isolation valves are accessible for manual operation or verifying that the associated penetrations are blind flanged.

MADDAN NECK 3/4 9-10 Amendment No. Iff,193

REFUELING OPERATIONS 3/4.9.10 WATER LEVEL - REACTOR VESSEL l TMfTIMc entmfTfDN rDR nprDaffnN 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor vessel flange.

APPLICABILITY: During movenant of fuel assemblies or control rods within the containment while in MODE 6.

ACTION:

With the requirements of the above specification not satisfied, place any fuel assembly or control rod in transit into a safe storage location and suspend all further operations involving movement of fuel assemblies or control rods within the reactor vessel.

simvrtiiaver ErnestDrurwit 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of fuel assemblies or control rods.

T HADDAM NECK 3/4 9-11 Amendment No. ff5,193

ei REFUELING OPERATIONS 3/4.9.11 MATER LEVEL-STOPM E POOL tTMfTTMC rnunfffnN ran AprDaTfnN 3.9.11 At least 20 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the stcrage pool.

ACTION:

With the requirements of the above specification not satisfied, suspend a.

all movements of fuel assemblies and crane operations with loads in the

{

fuel storage areas and restore the water level to i

within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The provisions of Specification 3.0.3 are not applicable.

tvinvrf t i auer nrnif fDrurvis 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

j i

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'i i HADDAM NECK 3/4 9-12 Amendment No. 72T,193 j i M

REFUELING OPERATIONS 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEN LINITING CONDITION FOR OPERATION i

3.9.12 The Fuel Storage Building Air Cleanup System shall be OPERABLE and in operation.

APPllCABILITY:.During operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool.*

ACTION:

I With the Fuel Storage Building Air Cleanup System inoperable, or a.

l not operating, suspend all operations involving movements of fuel within the storage pool or crane operation with loads over the storage pool.*

i b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIRENENTS 1

4.9.12 The Fuel Storage Building Air Cleanup System shall be demonstrated OPERABLE and in operation:

At least once per 18 months or (1) after any structural a.

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting fire, or chemical release in any ventilation zone commun,icating with the system by:

1)

Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a C.5.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 4000 cfm i 10%;

2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86*F, 95% relative humidity atmospheric pressure, and 40 feet / min face velocity in accordance with ASTM D3803; and 3)

Verifying a system flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N510-1980.

t

The above specification does not apply during movement of fuel storage rack modules into or out of the SFP during the Cycle 19 rerack, provided an approved safe loading path is established with no loads over stored fuel assemblies.

HADDAN NECK J/4 9-13 Amendment No. JfJ, IW,193

REFUELING OPERATIONS tilDVFf f I Amer DrtMlfDFMFMTC (f*nntinnad}

b.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86*F, 95% relative humidty, atmospheric pressure, and 40 feet / min, face velocity in accordance with ASMT D3803.

At least once per 18 months by:

c.

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 4000 cfm 10%, and 2)

Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than 0 inch Water Gauge differential relative to the outside atmosphere during system operation.

d.

After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 4000 cfm

_10%; and After each complete or partial replacement of a charcoal adsorber e.

bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm i 10%.

HADOAN NECK 3/4 9-14 Amendment No. J17,117,193

REFUELING OPERATIONS 3/4.9.13 NOVENENT OF FUEL IN SPENT FUEL POOL LINITING 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 greater than or equal to 800 ppm.

APPLICABILITY: Whenever a fuel assembly is moved in the spent fuel pool.

ACTION:

1 With the boron concentration less than 800 ppa, suspend the movement of all fuel in the spent fuel pool.

4 SURVEILLANCE REQUIREMENT 4

4.9.13 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to any movement of a fuel assembl and every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter.

HADDAN NECK 3/4 9-15 AmendmentNo./If,193

REFUELING OPERATIONS 3/4.9.14 SPENT FUEL P0OL--REACTIVITY CONDITION LIMITING ColeITION FOR OPERATION The lieactivity Condition of the spent fuel pool shall be such that 3.9.14 rw is less-than-or-equal-to 0.95 at all times.

APPLICABILITY:

Whenever fuel is in the spent fuel pool.

ACTION:

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

SURVEILI.ANCE REQUIRENENT 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.

HADDAN NECK 3/4 9-16 Amendment No. JM, M 193

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l HADOAM NECK 3/4 9-18 Amendment No. 75. M 193

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HADDAM NECK 3/4 9-19 Amendment No. 2 W i m i

4 REFUELING OPERATIONS 3/4.9.15 SPENT FUEL POOL COOLING LIMITING C00SITION FOR OPERATION 3.9.15 The spent fuel pool cooling system shall be OPERABLE with:

Both spent fuel pool cooling pumps OPERABLE and at least one a.

spent, fuel pool cooling pump and the plate heat exchanger in operation, and b.

Spent fuel pool temperature less than 150 degrees F.

APPLICABILITY: NODE 6, during transfer and storage of irradiated fuel from the reactor vessel to the spent fuel pool for a full core offload.*

ACTION:

spent fuel pool temperature greater than 150 degrees involvir.g the addition of irradiated fuel to the spent fuel pool and initiate corrective action to restore the spent fuel pool cooling system to OPERABL status as soon as possible.

SURVEILLANCE REQUIRENENTS 4.9.15.1 that both spent fuel pool cooling pumps are lined up to heat exchanger.

4.9.15.2 cooling pump is running.At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify that at least one spen 4.9.15.3 is less than 150 degrees F.At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify that the spent fuel p

Specification 3 915 d transferred to the spent fuel pool.oes not apply if less than 53 fuel assemblies are HADDAM NECK 3/4 9-20 AmendmentNo.Jd193

REFUELING OPERATIONS 3/4.9.16 SPENT FUEL P00L COOLING - DEFUELEO t

LIMITING CONDITIONS FOR OPEPATION 3.9.16 The spent fuel pool coolant temperature shall be maintained at less than or equal to 150 degrees F.

APPLICABILITY:

Whenever irradiated fuel assemblies are stored in the spent fuel pool.

\\.

ACTION:

With the spent fuel pool coolant temperature not within limit:

Imediately initiate action to restore the spent fuel pool coolant a.

temperature to within limit,.and b.

Imediately verify that a spent fuel pool makeup water source is available, and Within 7 days, restore the spent fuel pool coolant temperature to c.

within the limit.

i SURVEILLANCE REQUIREMENTS 4.9.16 At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , verify that the spent fuel pool coolant temperature is less than or equal to 150 degrees F.

L HADDAM NECK 3/4 9 21 Amendment No.193

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9421

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIM 110 EFFLUENTS CONCENTRATION LIMITING COMITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-1) shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10" nicroCi/ml total activity.

APPLICABILITY: At all times.

AGIlM:

With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Section I of the REMODCM.

4.11.1.1.2 The results of the radioactive analysis shall be used in accordance with the methods of Section II of the REM 00CM to assure that the concentration of the point of release are maintained within the limits of Specification 3.11.1.1.

HADDAR IECK 3/4 11-1 Amendment NO. M,193 osaa

RADIGACTIVE EFFLUENTS DOSE. LIOUIDS i

LIMITING C00SITION FOR OPERATION i

l 3.11.1.2 The dose or dose commitment to any MEMBER OF THE PUBLIC from 5.1-1) shall be limited: radioactive materials in liquid effluents released from the sit During any calendar quarter to less than or equal to 1.5 arem to a.

the total body and to less than or equal to 5 area to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mres to any organ.

APPLICABILITY: At all times.

ACTION:

I With the calculated dose from the release of radioactive materials a.

in liquid effluents exceeding any of the above limits, prepare and submit to the Coassission within 30 days, pursuant to S 6.9.2, a Special Report which identifies the cause(s) pecification for exceeding the limit (s) and defines the corrective actions to be i

taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PURIC from such i

release during the calendar year is within 3 area to the total body and 10 aren to any organ.

b.

DELETED l

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with Section II of the REM 00CN.

4.11.1.2.2 Relative accuracy or conservatisms of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REMODCM.

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NADDAR IECK 3/4 11-2 Amarrement No. MF.193 essa

- _ ~.

RAD 10 ACTIVE EFFLUDfTS 3/4.11.2 GAiran$ EFFLUENTS t

DOSE RATE LIMITING COM ITION FOR OPERATION l

3.11.2.1 The dose rate, at any time, offsite (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

1 The dose rate limit for noble gases shall be less than or equal to a.

500 aren/yr to the total body and less than or equal to 3000 aresVyr to the skin, and i

b.

The dose rate limit due to inhalation for tritium and for all radioactive materials in particulate form with half-lives greater l

than 8 days shall be less than or equal to 1500 mres/yr to any organ.

i APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the above limits, decrease the release rate within 15 minutes to comply with the limit (s) given in Specification l

3.11.2.1.

SE VEILLANCE REQUIREMENTS i

4.11.2.1.1 The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established above in Specification 3.11.2.1.

The corresponding release rate shall be determined in accordance with the methodology of Section II of the REM 00CM.

4.11.2.1.2 The noble gas effluent monitors of Specification 3.3.3.8 shall be used to control release rates to limit offsite doses within the values established in Specification 3.11.2.1.

4.11.2.1.3 The release rate of radioactive materials in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Section I of the REM 00CM (Table D-1). The corresponding dose rate shall be determined using the methodology and parameters given in the ODCM (Section l

II of the REM 00CM).

HAIEhAN IECK 3/4 11-3 Amaruhent No. /#.193 maa

RADI0 ACTIVE EFFLUENTS DOSE. NOBLE GASES l

LIMITING ColGITION FOR OPERATION 3.11.2.2 The air dose offsite (see Figure 5.1-1) due to noble gases released in gaseous ' effluents shall be limited to the following:

During any calendar quarter, to less than or equal to 5 mrad for a.

gamma radiation and less than or equal to 10 mrad for beta radiation, and b.

During any calendar year to less than or equal to 10 mrad for gamma radiation and less than o equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from radioactive noble gases in a.

gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to S 6.9.2, a Special Report which identifies the cause(s) pecification 1

for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

DELETED l

SURVEILLANCE REQUIREMENfS 4.11.2.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with Section II of the REMODCM once every 31 days.

4.11.2.2.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I of the REMODCM.

HADDAR IECK 3/4 11-4 Amendment No. ITF.193 osa

1 RADI0 ACTIVE EFFLUENTS DOSE. RADI0 ACTIVE MATERIAL IN PARTICULATE FORN AND RADInMLCLIDES OTHER THAN NOBLE GASES l

LIMITING C0fCITION FOR OPERATION 3.11.2.3 The dose,to any M2MBER OF THE PUBLIC tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous l effluents released offsite (see Figure 5.1-1) shall be limited to the following:

During any calendar quarter to less than or equal to 7.5 ares to a.

any organ; b.

During any calendar year to less than or equal to 15 arem to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radionuclides, a.

radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above 1

limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 ares to any organ.

b.

DELETED l

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REM 00CM once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REM 00CM.

MADDAN IECK 3/4 11-5 Amendment No. 177.193 uss

R&DIQACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE LIMITING C00SITION FOR OPERATION 3.11.3 The dose or dose commitment from the site to a MEMBER OF THE P is limited to less,than or equel to 25 area to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mres) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials a.

in liquid or gaseous effluents exceeding twice the limits of i

Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3, prepare and submit a Special Report to Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment from the site to any MEMBER OF THE PUBLIC is limited to less than or equal to 25 mres to the total body or any organ (except thyroid, which is limited to less than or equal to 75 area) over 12 consecutive months.

This Special Report shall include an analysis which demonstrates that radiation exposures from the site to any MEMBER OF THE PUBLIC (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b.

DELETED l

ERVEILLANCE REQUIREMENTS 4.11.3 Cumulative dose contributions from liquid and gaseous effluents and direct radiation shall be determined in Specifications 4.11.1.2.1, 4.11.2.2.1 and 4.11.2.3.1 and in accordance with Section II of the REMODCM once per 31 days.

IIAlmAll m 3/4 11-6 Amendment No.W.193 enaa

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8ASES FOR SECTIONS 3.0 ANO 4.0 LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 1

= _ - -.

PLANT SYSTEMS 3/4.7.5 SEA 1 m mMCE CONTAMINATION SURVEILLANCE REQUIREMENTS (Continued) b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months.

Sealed sources and fission detectors transferred without a certificate l

indicating the last test date shall be tested prior to being placed into use; and c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested following repair or maintenance to.the source.

R'eports - A report shall be prepared and subaltted to the 4.7.5.3 Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removal contamination.

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MADDAM NECK om 3/4 7-15 Amendment No. / M 193

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i SECTIONS 3.7.6 THROUGH 3.7.12; I

SECTIONS 4.7.6 THROUGH 4.7.12; I

TABLES 3.7-3 THROUGH 3.7-6; AND PAGES 3/4 7-16 THROUGH 3/4 7-36 DELETED i

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3/4 LINITING C"31TIONS FOR OPERATION AfW SURVEILLANCE 3/4.0 APPLICMILITY BASES i

Snecifications 3.0.1 throuah 3.0.4 establish the applicable to Limiting Conditions for Operation. general requirements These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal, Regulations,10CFR50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

l Soecification 3.0.1 establishes the Applicability statement within each I

individual specification as the requirement for when (i.e., specified applicable conditions required for safe oper)ation of the facility.confonmance to the Limiting Co The ACTION requirements

)

limits when the requirements of a Limiting Condition for O 3

met.

There are two basic types of ACTION requirements.

The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

level of safety for unlimited continued operation as long as In i

l requirements continue to be met.

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met.

This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits.

these actions are not completed within the allowable outage time limits, it is If required that the facility be placed in a s which the specification no longer applies. pecified applicable condition in It is not intended that the ACTION voluntary removal of a system (srequirements be used as an operationa alternatives that would not resu)lt in redundant systems or compon or component (s) from service in lieu of other inoperable.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems.

include a specified time limit for the completion of a SurveillanceIndividual specifi j

Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable i

l when this limit expires if the surveillance has not been completed.

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.H.A.D.RAN IECK B 3/4 0-1 Amendment No. M.193

3/4.0 APPLICABILITY BASES (Con't) 4 i

Specification 3.0.2 establishes that noncompliance with a specification exists when the requirements of the Limiting condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not within the time interval specified in the associated ACTION requirements.

4 Snecification 3.0.3 DELETED l

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NADWW NECK 5 3/4 0-2 Amendment No. )F/7,193

3/4.0 APPL ICABILITY

_ BASES (Con't)

Specification 3.0.4 establishes limitations on changes from a specfied applicable condition when a Limiting Condition for Operation is not met.

purpose of this specification is to ensure that the facility is no The obtain compliance with a specification by restoring equipment to OPERABLE status or parameters,to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant.

specified applicable Therefore, in this case, entry into a of the ACTION requirements. condition may be made in accordance with the provisions The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status.

l Soecifications 4.0.1 throuah 4.0.4 establish the general requirements l

applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10CFR50.36(c)(3):

HAlmAll IECK 8 3/4 0-3 Amendment No. JJJ.193 esas

1 3/4.0 APPLICABILITY BASES (Con't) 1

[

" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of j

systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met.",

Snecification 4.0.1 establishes the requirement that surveillances must be performed during the specified applicable conditions for which the j

requirements of the Limiting Conditions for Operation apply unless otherwise l

stated in an individual Surveillance Requirement.

The purpose of this t

specification is to ensure.that surveillances are performed to verify the operational status of systems and components and that parameters are within j

specified limits to ensure safe operation of the facility when the plant is j

l in a specified applicable condition for which the associated Limiting l

Conditions for Operation are applicable.

j Soecification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.

It perwits an

{

allowable extension of the normal surveillance interval to facilitate j

surveillance scheduling and consideration of plant operatin may not be suitable for conducting the surveillance; e.g., g conditions that 1

transient conditions or other ongoing surveillance or maintenance activities.

The limitation of Specification 4.0.2 is based on engineering judgement and the 3

recognition that the most probable result of any particular surveillance being j

performed is the verification of conformance with the Surveillance Requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

4 j

Snecification 4.0.3 establishes the failure to perform a Surveillance i

Requirement within the allowed surveillance interval, defined by the i

provisions of Specification 4.0.2, as a condition that constitutes a failure i

to meet the OPERABILITY requirements for a Limiting Condition for Operation.

under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been i

satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or j

components are OPERABLE when they are found or known to be inoperable i,

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4 blAlmAll m B 3/4 0-4 AmendmentIlo.NJ,193 esas

3/4.0 APPLICABILITY BASES (Con't) although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed from the point in time it is identified that a surveillance has no performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable

)

outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was i

a violation of the OPERASILITY requirements of a Limiting Condition for Operation.

~

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a 24-hour allowance is provided to permit a delay in implementing the ACTION Surveillance Requirements that have not been performed. requirements. T l

The purpose of this allowance is to permit the completion of a surveillance before remedial measures would be required that may preclude completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the

'24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable i

equipment because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

Soecification 4.0.4 establishes ti,e requirement that all applicable surveillances must be met before entry into a specified applicable condition l

i of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERASILITY requirements or parameter limits are met before entry into a specified applicable condition l for which these systems and components ensure safe operation of the facility.

t MAIS AN IEEK 8 3/4 0-5 Amendment No. JM,193 was

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REFERENCES 1, 2, 3; AND i

PAGES 83/4 0-6 THROUGH B3/4 0-7 s

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POWER DISTRIBUTION LIMITS DELETED IN THEIR ENTIRETY I

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BASES 3/4.3.1 THROUGH 3/4.3.3.2; AND PAGES B 3/4 3-1 AND 8 3/ 3-la DELETED 3

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INSTRislENTATIM a

3/4.3.3 MONITORING INSTRUMENTATION j

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that su evaluate the response of those features important to safe 1

the design basis for the facility.ty is required to permit comparison of e

This capabili-l 314.3.3.4 METEOROLOGICAL INSTRUMENTATION l

i The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radio-t i

active materials to the atmosphere. This capability is required to evaluate of the public and is consistent with the recommendatio i

1.23, "Onsite Meteorological Programs," February 1972.

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J HADDAN NECK eens B3/4 3-2 Amendment No. JJJ, 177, 193

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BASES 3/4.3.3.5 AND 3/4.3.3.6 DELETED 0424

lINSTRUNENTATION BASES 3/4.3.3.7 RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

Alarm / Trip Setpoints for the.e instruments shall be calculated and adjusted The in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUNENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the REM 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consis-tent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

i HADOAN NECK B3/4 3-3 Amendment No. //J, JJJ, J77 193 um

1 BASF.S 3/4.3.3.9 AND 3/4.3.4; AND PAGE B 3/4 3-4 DELETED HADtWI NECK 0424

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BASES 3/4.4 REACTOR C00UUfT SYSTDI l

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HADDAM NECK i

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PLANT SYSTEMS BASES 3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.

Sealed sources which are continuously enclosed within a shielded mechanism (i.e.,

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

MADOAM NECK B3/4 7-4 Amendment No. J U JJ7, 177 193 o4n

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HADOAN NECK

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION the reactor will remain subcritical during CORE ALTERATIO (1) water volume having direct access to the reactor vessel. unifor

, and (2) a are consistent with the initial conditions assumed for the boron dilut incident in the accident analyses.

required for this accident.

A value of 0.94 or less for K, is additional 0.05 K For a core configuration of all rods in an crushing the core,into a more reactive configuration. penalty is required to 3/4.9.2 INSTRUMENTATION-The OPERABILITY of the Source Range Neutron Flux Monitors ensures that monitoring capability is available to detect changes in the reactivity condition of the core.

Redundant monitoring capability is required to detect changes in the reactivity condition of the core during fuel movement 3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of elapsed to allow the radioactive decay of the short-lived The minimum requirement for reactor hold time prior to movement of irradiat fuel from the reactor vessel to the spent fuel pool ensures that sufficient decay time has elapsed for adequate spent fuel pool cooling should a failure occur to the cooling system.

The required decay time assumes a conservative maxim water temperature.

transfer rate of six assemblies per hour.

with the assumptions used in the safety analysis.These decay times are consistent 3/4.9.4 CONTAINMENT SUILDING PENETRATIONS casure that a release of radioactive material within contai restricted from leakage to the environment.

The OPERABILITY and closure fuel element rupture based upon the lack of containment pr potential while in the REFUELING N00E.

3/4.9.5 COWIUNICATIONS-manipulator crane area personnel can be promptly inform i

changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

1 NADDAN NECK 83/4 9-1 Amendment No. Fff. M m

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REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERA 8ILITY requirements for the manipulator cranes ensure that:

manipulator cranes will be used for movement of control rod drive shafts and (1) fuel assemblies, shaft or fuel asse(mbly, and (3) the core internals and reacto protected from excessive li'thg f engaged during lifting operav.ans.orces in the event they are inadvertently 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the assemblies in the storage pool ensures that in the event this load is dropped:

single fuel assembly, and (2(I) the activity release will be limited to that cont racks will not result in a cr)itical array. This assumption is consiste with the activity release assumed in the safety analysis.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one RHR LOOP be in operation ensures that:

sufficient cooling capacity is available to remove decay heat and maintain (1) the water in the reactor vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is mai,tained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR LOOPS OPERABLE of the operating RHR t00P will not result in a complete loss of residual heat removal capability.

With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling.

Thus, in the event of a failure of the operating RHR LOOP, adequate time is provided to initiate emergency procedures to cool the core.

j 3/4.9.9 CONTAINMENT PURGE SUPPLY. PURGE EXHAUST. AND P ISOLATION SYST[g The OPERABILITY of this system ensures that the containment vent and purge penetrations can be isolated upon detection of high radiation levels within the containment.

release of radioactive material from the containment atmosphere to environment.

HADDAM NECK B 3/4 9-2 Amendment No. Jy, M 193

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SASES 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STO The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

consistent with the assumptions of the safety analysis.The minimum water depth is 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM all radioactive material released from an irradiated fuel a filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERA 8ILITY of this system and the resulting iodine i-removal capacity are consistent with the assumptions of the safety analysis.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

.t y_4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL handling accident in the spent fuel pool, K.,,

will remain s 0.95.The limitations of this specification ensure th E 4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION 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 racks, with no credit taken for soluble boron in the pool, are conservatively within the assumptions of the safety analysis.

3/4.9.15 SPENT FUEL POOL COOLING The limitations on the Spent Fuel Pool Cooling System ensure there is sufficient capacity to remove decay heat produced by the stored spent fuel elements with a full core offload and maintain the bulk pool temperature below 150*F with a maximum heat load of 22.4x10' BTU /hr. The maximum design heat i

load is based on an emergency full core offload scenario conservatively evaluated after the final operating cycle.

i Requiring both spent fuel pool cooling pumps to be OPERABLE provides backup

[

capability in the event the operating pump fails.

In the event of a complete loss of forced cooling during a full core offload, the time to boil is greater than 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months in the most severe discharge scanario.

This allows sufficient time to provide an alternate power source to the SFP pumps for an electrical failure or alternate SFP inventory makeup ct,, ability for a mechanical failure.

i In the event of a loss of offsite power and the A train diesel is out-of-service, there is sufficient time to repower the SFP cooling system from an alternate diesel generator.

Therefore, operability of the spent fuel pool t

cooling system does not require the A train diesel generator to be available.

Should failure to restore operation of the cooling system occur before boiling takes place, cooling of the spent fuel pool can be accomplished by allowing the SFP to boil and adding makeup water at a rate equal to or greater than the i

boil-off rate.

H400AM NECK 83/4 9-3 Amendment No. J77,177,177,193

1 3/4.9 REFUELING OPERATIONS BASES-4 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED The primary basis for 150 degrees F is to limit thermal stresses on the s fuel pool concrete ' tructures due to the differential temperature across the s

a internal and exterior surfaces of the walls and floor.

The basis is further discussed in License Amendment No. 188.

As of May 1998, the spent fuel heat load was calculated to be less than 4

2.3E+06 BTU /hr.

Each heat exchanger has the capability of removing this heat load.

One. spent fuel pool heat exchanger and one spent fuel pool cooling pump, that can be operated intermittently is sufficient to remove the decay heat load.

(

4 Assuming no forced or evaporative cooling, the calculated May 1998 heatup is approximately 1.2 degrees F/hr.

Thus, in the event of a complete loss of forced cooling and assuming an initial spent fuel pool temperature of 150 degrees F. the time to boil, assuming no evaporative cooling, is greater than 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months .

4 Therefore, sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory.

4 i

'f HADDAM NECX B 3/4 9-5 Amendment No.193

{

BASES 3/4.10 SPECIAL TEST EXCEPTIONS DELETED IN THEIR ENTIRETY

/

HA00AM NECK-

~ ~ ' - ' - ' '

3/4.11 RADI0 ACTIVE EFFLUENTS

^

BASES I

3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION 1

)

l This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will I

i be less than the concentration levels specified in 10 CFR Part 20, Appendix

)

B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within:

(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Frotection (ICRP) Publication 2.

3/4.11.1.2 DOSE. LIOUIDS This specification is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition I

for Operation implements the guides set forth in Section II.A of Appendix I.

l 1

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be i

kept "as low as is reasonably achievable".

The dose calculation methodology and parameters in the REM 00CM implement the requirements in Section III.A of Appendix I that conformance with the guides of Apper. dix I is to be shown by calculational procedures ba. sed on models and data, such that the actual i

exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the REMODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided I

in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April i

1977.

1 i

b 4

i NADOAM NECK B3/4 11-1 Amendment No. JU. Mdf,193 0427 4

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at anytime from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for all areas offsite. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual offsite to annual average concentrations exceeding the limits specified in Appendix 8, Table II of 10 CFR Part 20 (10 CFR 20,106(b)).

For individuals who may at times be within the site boundary, the occupancy of that individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

The specified ' release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrenVyear to the total body or to less than or equal to 3000 mrenvyear to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid or other organ dose rate above background to a child to less than or equal to 1500 mrea/ year from inhalation.

3/4.11.2.2 DOSE. NOBLE GASES This specification is provided to implement the requirements of Sections II.B., III.A and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,

" Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

The ODCM equations provided for determining the air doses at the site boundary are based upon utilizing successively more realistic dose calculational methodologies. More realistic dose calculational methods are used whenever simplified calculations indicate a dose approaching a substantial portion of the regulatory limits.

The methods used, in order are, previously determined air dose per released activity ratio, historical meteorological data and actual radionuclide six released, or real time meteorology and actual radionuclides released.

HA00AM NECK B3/4 11-2 Amendment No. 'JM,193 0427

\\

i RADI0 ACTIVE EFFLUEWS i

BASES 3/4.11.2.3 DOSE. RADI0ACTI'E MATERIAL IN PARTICULATE V

FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES l

i This specification is provided to implement the requirements of Sections II.C III.A and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

ACTION statements provide the required operating flexibility and at the same The time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in I

Section III.A of Appendix I that conformance with the guides for Appendix I be shown by calculational procedures based on models and data such that the be substantially underestimated. actual exposure of an individual through a The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision I, July 1977.

The release rate specifications for radioactive material in particulate form and radionuclides other than noble gases are l

dependent on the existing radionuclide pathways to man.

The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3/4.11.3 TOTAL DOSE This specification is provided to meet the reporting requirements of 40 CFR Part 190. For the purposes of the Special Report, it may be assumed that the dose commitment to any MEMBER OF THE PUBLIC from other fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.

1 HADDAN NECK B3/4 11-3 Amendment No. 125,193 0427

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p m

I SECTION 5.0 DESIGN FEATURES Den

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA-5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.

distance to the boundary of the exclusion area as defined in 10CFR100.3 The minimum shall be 1740 feet.

LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-2.

l 5.2 DELETED 5.3 DELETED 5.4 DELETED 5,5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.

HA00AM NECK 5-1 Amendment No. J M,193 04N

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- Protected Aree 88 *e

...-- sete r_

"x,(Exclusion Area)

J I

Eg Scale:

1 inch egnels approx. 850 ft.

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INFelpt4 TION REACTOR AllelENT CENTER l

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FIGURE 5.1-1

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o EXCLUSION AREA B00NORY AND SITE B0UNDARY FOR LIQUID AND GASE0 i

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LOW POPULATION ZONE I

HADDAN NECK om 5-3 h a h a+ "a

DESIGN FEATURES 5.6 SPENT FUEL STORAGE I

CRITICALITY l

and shall be maintained with:5.6.1 The spent fuel storage racks are made For Region 1, a nominal 10.98 inch (East / West) and a nominal 10.142 inch a.

(North / South) center-to-center distance including neutron absorber surrounding each assembly to ensure a 4 less than or equal to.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.

shown in Figure 3.9-4.The location of Region I within the Spent Fuel Pool is b.

For Region 2, a nominal 9.00 inch center-to-center distance including neutron absorber surrcunding each assembly to ensure a y less than or equal to.95 when flooded with unboreted water.

Storage of fuel in Region 2 must be in accordance with the requirements of Specification 3.9.14.

The location of Region 2 within the Spent Fuel Pool is shown in Figure 3.9-4.

For Region 3, a nominal 10.75 inch center-to-center distance to ensure a c.

4 less than or equal to.95 when flooded with unborated water.

No credit is taken for the neutrc h orber contained within the racks of this region. Storage of fuel '.. Esefon 3 must be in accordance with the I

requirements of Specification 3.9.14.

the Spent Fuel Pool is shown in Figure 3.9-4.The location of Region 3 within DRAINAGE I

i 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 27.0 feet NSL.

CAPACITY i

5.6.3 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 3

560 storage locations in Region 2, and 696 storage locations in Region 3 for a total of 1480 storage locations.

l l

1 i

NADCAN NECK 5-4 Amendment No. JJJ, JJJ, 17), 3 0193 mas e-wm

~r

SECTION 5.7; TABLE 5.7-I; FIGURES 5.6-1 AND 5.6-2; AND PAGES 5-5 THROUGH 5-8 DELETED i

l l

___=

6.0 ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures and/or administrative policies shall be established, implemented. and maintained covering the activities referenced below:

Guide 1.33. Revision 2. February 1978:The applicable a.

b.

ANSI N 18.7 1976.The requirements and reconmendations of S Fire Protection Program implementation.

c.

d.

Regulatory Guide 1.21 Rev. 1. June 1974. Quality contr RADIOLOGICAL EFFLUENT MONITORING AND e.

(REM 00CM) implementation 3FFSITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring.er ept for Section I.E.

f.

Process Control Program implementation, g.

Spent Fuel Pool Cooling and Makeup Monitoring Program implementation.

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. This Program shall provide reasonable assurance that the equipment, componen systems and water sources used for spent fuel pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected against freezing.

P HADDAM NECK 6 11 Amendment No. 125. MS 481 I

191. 192. 193

4

'6.0 ADMINISTRATIVE CONTROLS i

I 6.8.2 Each procedure of Specification 6.8.1. and changes thereto, shall l

be reviewed by the PORC and shall be approved by the Unit Director prior t implementation and reviewed periodically as set forth in each document or in i

administrative procedures.

)

1 t

i l

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

I The intent of the original procedure is not altered:

a.

i b.

The change is approved by a member of the plant management staff and a Certified Fuel Handler; and The change is documented reviewed by the PORC and approved by the c.

Unit Director within 14 days of implementation, j

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 l

Environmental l

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 l

approved by appropriate supervision.

l-Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL. within 14 days of implementation, i

i f

i HADDAM NECK 6-12 Amendment No. 435. MS. H8.

M1. M2.193 i

-

ML20202D152

Text

Attachment:

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