ML20237E363

Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features

ML20237E363
Person / Time
Site:	Yankee Rowe
Issue date:	08/20/1998
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20237E359	List: ML20237E357 ML20237E363
References
NUDOCS 9808310187
Download: ML20237E363 (8)

Text

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ATTACHMENT A l Revised Technical Specification Panes Annotated Version l

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1.0 DEFINITIONS (Continued) 0FF-SITE DOSE CALCULATION MANUAt (ODCM) l 1.6 The OFF-SITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of off-site doses resulting l from radioactive gaseous and liquid effluents, in the calculation of l gaseous and liquid effluent monitoring alarm / trip setpoints, and in I l

the conduct of the Environmental Radiological Monitoring Program.  ;

'The 00CM also contains (1) the Radioactive Effluent Controls and I l Radiological Environmental Monitoring Programs required by i

Section 61.8, and (2) descriptions of the information that should be l included in the Annual Radiological Environmental Operating and l

Semiannual Radioactive Effluent Release' Reports required by ]

i Specifications 6.8.2.a and 6.8.2.b.

OPERABLE - OPERABILITY l 1.7 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified l safety function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other

! J' auxiliary equipment that are required for the system, subsystem,

,' train, component or device to perform its safety function (s) are I also capable of performing their necessary s'upport function (s).

PROCESS CONTROL PROGRAM (PCP) l 1.8 The PROCESS' CONTROL PROGRAM contains the current formulas, sampling.

l analyses, test, and determinations to be made to ensure that

. processing and packaging of solid radioactive wastes based on i demonstrated processing of actual or simulated wet solid wastes will j be accompitshed in such a way as to.assu're compliance with 10 CFR l

[ Parts 20, 61, and 71, state regulations, burial ground requirements.

l and other requirements. governing the disposal of solid radioactive  ;

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l REPORTABLE EVENT i

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

-6HE-BOUM9ARV 1.10 The SITE SOUNDARY :h:11 be that line defining :n are: within which the land is eened, letted, Or otherwi:e' controlled by the licen:00.

fny :re: within the SITE SOL'M0?9Y ::ed f0r re:f d0nti:1 qu:rter: Or i ' YANKEE-ROWE 1-2

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l i' l 5.0 DESIGN FEATURES 5.1 SITE LOCATTON l

5.1.1 The ;;;1usic.. ar;; shall i; ;; sh; = in 'igur; 5.1 ;

l- The Yankoo fluclear power 7,tation in located in the town of Rowe, Massachuustts, three-quarters of a nile nouth of the vermont-Massachunotts border. The site in at the bottom of a l

deep valley along the Deerfield River on the noutheant bank of Shernan Reservoir. . The geographical coordinates of the centerline of the reactor containment structure (Vapor l Container) are as follown: I Latitude ti 42' 43 ' 41" Longitude: W 72* 55' 42' 5.2 -FUEL STORAGE CRITICALITY 5.2.1 The spent fuel storage racks _are designed and shall be maintained with a center-to-center' distance between fuel assemblies placed in the storage racks to ensure a k,gg equivalent to 0.95 with the spent fuel storage areas flooded with unborated water. The k,gg . of 0.95 includes a conservative allowance of 3% Ak/k for uncertainties.

DRAINAGE 5.2.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pit.

CAPACITY 5.2.3 The spent fuel pit is designed and shall be maintained with a storage capacity limited to no more than 540 fuel assemblies.

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ATTACHMENT B Revised Technical Snecincation Pages 1-2 5-1 l-i 1

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1.0 DEFINITIONS (Continued) l l

0FF-SITE DOSE CALCULATION MANUAL (00CM)

! 1.6 The OFF-SITE DOSE CALCULATION MANUAL (0DCM) contains the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by f

Section 6.7, and (2) descriptions of the information that should be

' included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.8.2.a and 6.8.2.b.

OPERABLE - OPERABILITY 1.7 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s).. Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety function (s) are also capable of performing tneir necessary support function (s).

EROCESS CONTROL PROGRAM (PCP) 1.8 The PROCESS CONTROL PROGRAM contains the current formulas, sampling, analyses, test (s), and determinations to be made to ensure that .

processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71,* state regulations, burial ground requirements, and other requirements, governing the disposal of solid radioactive waste. ,

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

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5.0 DESIGN FEATURES 5.1 SITE LOCATION The Yankee Nuclear Power Station is located in the town of Rowe, Massachusetts, three-quarters of a mile south of the Vermont-Massachusetts border. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir. The geographical coordinates of the centerline of the reactor containment structure (Vapor container) are as.follows:

Latitude N 42* 43' 41' Longitudes W 72* 55' 42' 5.2 FUEL STORAGE CRITICALITY

, 5.2.1 The spent fuel storage racks are designed and shall be maintained with-a center-to-center distance between fuel assemblies placed in the storage racks to ensure a k ort 1 ' equivalent to 0.95 with the spent fuel storage areas flooded with unborated water. The k,gg of 0.95 includes a conservative allowance of 3% Ak/k for uncertainties.

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

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prevent inadvertent draining of the pit.

CAPACITY 5.2.3 The spent fuel pit is designed and shall be maintained with a storage capacity limited to no more than 540 fuel assemblies.

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