ML20085J343

Proposed Tech Spec Changes 209 & 76 to Licenses DPR-66 & NPF-73

ML20085J343
Person / Time
Site:	Beaver Valley
Issue date:	06/15/1995
From:	DUQUESNE LIGHT CO.
To:
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ML20085J332	List: ML20085J328 ML20085J343
References
NUDOCS 9506220114
Download: ML20085J343 (5)

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1. -g a

-so ATTACHMENT TO LICENSE AMENDMENT NO.

t FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A,1 Technical Specifications, with the enclosed pages as indicated.

The revised' pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 1-8 1-8 6-19 6-19 0

9506220114 950615 PDR ADOCK 05000334 P

PDR

p.c r a jf W

As ~,

i 2

L 36 '

M){-66J k M DEFIN'ITIONS" x

zgM L2):

' Major (fchangest~in lthe ' design:Loff radwaste treatment

-systems 1(liquid,".

gaseous' and. solid): ;that could E

significantly.. increase: the! quantities oriactivitylof 4 y

effluents released'or volumes of solid waste stored or a

shipped.offsite from those 'previously considered-in; tn y

Lthe FSAR.and SERL(e.g.,-use of; asphalt system in place t of cement);'

3)'

-Changes in,. system. design which' may1finvalidate:the-accident analysis as described 1 in the SERr ( e. g.', ;

1 changes in. tank capacity.that would-alter the curiesL 1

4

. released); and 4)

Changes in' system design that could potentially result"

('*

in a

significant increase;in occupational exposure.of operating personnel (e.g., use of temporary.. equipment j

without. adequate shielding provisions).

s.

MEMBER (S) OF THE PUBLIC 1.36 MEMBERS OF THE PUBLIC shall' include all persons who?are.not 1 occupationally associated with -the plant.

This category'does'not j

include employees of the-utility, its contractors or its vendors.

Also excluded-from this category are persons who enter the site to service equipmenti or to make' deliveries and persons who< traverse.

a

portions-of the site as the consequence of~a public; highway,trailway

~

or waterway located within the. confines ofstheisite boundary.

This~

category does include persons who use portions:;of the siteifor-

' recreational, occupational,. 'or other:; purposes:not associated with~

i the plant.

CORE OPERATING' LIMITS REPORT' l.37-The CORE OPERATING LIMITS REPORT - (COLR) ~is the unit-specific -

l document.

that provides core coperating limits 'for~.the-current'

. operating reload ' cycle.

These cycle-specific core-operatingflimits

.shall' be determined for each reload cycle in accordance with'

' Specification 6.9.1.12.-

Plant operation within these operating :l limits is addressed in individual specificetions, r

1 BEAVER. VALLEY - UNIT-1 1-8 Amendment'No.

l DPR-66 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (4) 6.9.1.11 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted before April 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

CORE OPERATING LIMITS REPORT 6.9.1.12 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a

reload cycle.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1.

WCAP-9272-P-A,

" WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

July 1985 (Westinghouse Proprietary).

Methodology applied for the following Specifications:

3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control 3.2.2, Heat Flux Hot Channel Factor-Fq(Z) 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H 2.

WCAP-10266-P-A Rev. 2 / WCAP-11524-NP-A Rev.

2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"

Kabadi, J.

N.,

et al., March 1987; including Addendum 1-A " power Shape Sensitivity Studies" 12/87 and Addendum 2-A

" BASH Methodology Improvements and Reliability Enhancements" 5/88.

Methodology applied for the following Specification:

3.2.2, Heat Flux Hot Channel Factor-Fg(Z) 3.

WCAP-8385,

" POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT,"

September 1974 (Westinghouse Proprietary).

Methodology applied for the following Specification:

3.2.1, Axial Flux Difference-Constant Axial Offset Control (4) A single submittal may be made for a multi-unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste I

systems, the submittal shall specify the releases of radioactive material from each unit.

l BEAVER VALLEY - UNIT 1 6-19 Amendment No.

~.

, !. 4 ' *

.. f.i..;

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY' OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-411

' Replace the following pages of Appendix A, Technical Specifications,

'with - the enclosed pages as indicated.

The revised pages are identified. by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 6-20 6-20 t

i l

I i

4

+

'Ib NPF-73

~4 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 2.

WCAP-10206-P-A Rev.

2

/

WCAP-11524-NP-A Rev.

2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH. Code,"

Kabadi, J.

N.,

et al., March 1987; including Addendum 1-A

" Power Shape Sensitivity Studies" 12/87 and Addendum 2-A

" BASH Methodology Improvements and Reliability Enhancements" 5/88.

Methodology applied for the following Specification:

3.2.2, Heat Flux Hot Channel Factor-F (Z).

g 3.

WCAP-8385,

" POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING TOPICAL REPORT,"

September 1974 (Westinghouse PROCEDURES Proprietary).

Methodology applied for the following Specification; 3.2.1, Axial Flux Difference-Constant Axial Offset Control.

4.

T.

M. Anderson to K. Kniel (Chief of Core Performance Branch, j

NRC)

January 31, 1980

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

Methodology applied for the following Specification:

3.2.1, i

Axial Flux Difference-Constant Axial Offset Control.

5.

NUREG-0800, Standard Review

Plan, U.S.

Nuclear Regulatory Commission,-

Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev.

2, July 1981. Methodology applied for the following Specification:

3.2.1, Axial Flux Difference-Constant Axial Offset Control.

The core operating limits shall be determined so that all applicable limits (e.g.,

fuel thermal-mechanical limits, core thermal-hydraulic

(

l

limits, ECCS

limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS

REPORT, including any mid-cycle l

revisions or supplements

thereto, shall be provided upon issuance, l

for each reload cycle, to the NRC Document Control Desk.

EPECIAL REPORTS I

(

6.9.2 Special reports shall be submitted to the U.S.

Nuclear l

Regulatory Commission, Document Control Desk within'the time period specified for each report. These reports shall be submitted covering I

the activities identified below pursuant to the requirements of the i

applicable reference specification:

r a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

I I

b.

Inoperable seismic Monitoring Instrumentation, Specification r

3.3.3.3.

BEAVER VALLEY - UNIT 2 6-20 Amendment No.

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