ML20023B928

Amend 87 to License DPR-32,revising Tech Specs to Raise Control Rod Bank Insertion Limits

ML20023B928
Person / Time
Site:	Surry
Issue date:	04/26/1983
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20023B929	List: ML20023B928 ML20023B930 ML20023B932
References
NUDOCS 8305090327
Download: ML20023B928 (5)

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o, UfflTED STATES

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NUCLEAR REGULATORY COMMISSION

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.y 11 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO' FACILITY OPERATING LICENSE Amendment No. 87 2

License No. DPR-32

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1.

The Nuclear Regulatory Commission (the Commission) has found that:

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A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated April 14, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the orovisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; f

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E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements

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have been satisfied.

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8305090327 830426 PDR ADOCK 05000200 P

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2.

Accordingly, the license is amended tar changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 87, are f

hereby incorporated in the license. The licensee shall

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operate the facility in accordance with the Technical Specifications.

1 3.

This license amendment is effective as of the date of its issuance.

I' FOR THE NUCLEAR REGULATORY COMMISSION

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. s t-s Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: April 26,1983

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ATTACHMENT TO LICENSE AMENDMENT t

AMENDMENT NO. 87 TO FACILITY OPERATING LICENSE fl0. DPR-32 DOCKET NO. 50-280 r

Revise Appendix A as folicws:

Remove Pages Insert.Pages 3.12-12 3.12-12 Figure 3.12-1 A Fiqure 3.12-l A i

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TS 3.12-12 on the maximum inserted rod worth in the unlikely event of a hypothetical assembly ejection and provide for acceptable nuclear peak'ing factors.

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limit may be determined on the basis of unit startup and operating data to i,

provide a more realistic limit which will allow for more flexibility in unit operation and still assure compliance with the shutdown requirement. The maximum shutdown cargin requirement occurs at end of core life and is based on the value used in the analysis of the hypothetical steam break accident. The 1

rod insertion limits are based on end of core life conditions.

The shutdown o

margin for the entire cycle length is established at 1.77% reactivity. All other accident analysis with the exception of the chemical and volume control n

system malfunction analysis are based on 1% reactivity shutdown margin.

Relative positions of control rod banks are determined by a specified control rod bank overlap. This overlap is based on the consideration of axial power shape control. The specified control rod insertion limits have been establish-ed to limit the potential ejected rod worth in order to account for the effects of fuel densification. The Unit 1 limits have been raised as shown in Figure 3.12-1A to ensure acceptable radial power peaking during Cycle 7 core life. The various control rod assemblies (shutdown banks, control banks A, B, L

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C, and D) are each to be moved as a bank; that is, with all assemblies in the t,

t bank within one step (5/8 inch) of the bank position.

Position indication is G

provided by two methods: a digital count of actuating pulses which shows the

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demand position of the banks, and a linear position indicator, Linear Variable t

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Differential Transfor=er, which indicates the actual assembly position.

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position indication accuracy of the Linear Differential Transformer is approx-h imately +5% of span ( 12 steps) under steady state conditions.

The relative f.

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accuracy of the linear position indicator has been considered in establishing t

f the maximum allowable deviation of a control rod assembly from its indicated group step demand position.

In the event that the linear position indicator r

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1.0 0.0 0.2 0.4 0.6 0.8 1.0 FRACIION OF RATED P0k'ER FIGURE 3.12-1A CONTROL BANK INSERTION LIMITS FOR 3-LOOP NORMAL OPERATION-UNIT 1 4

Amendment No. 87 h(

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