ML20246E281

Amend 32 to License NPF-42,revising Tech Specs 3.1.3.4 & Figure 3.1-1 to Change Fully Withdrawn Position of Rod Cluster Control Assemblies to Range of 222 to 231 Steps, Inclusive

ML20246E281
Person / Time
Site:	Wolf Creek
Issue date:	07/05/1989
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246E285	List: ML20246E281 ML20246E324
References
NUDOCS 8907120176
Download: ML20246E281 (7)

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3'2 License No. NPF-42 1.

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

A.

The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by theWolfCreekNuclearOperatingCorporation(theCorporation),

dated April 13, 1989, complies with the standards and requirements of the Atonic 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, as amended, the provisions of the Act, and the rules and regulations of the Corrission; 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 issuence of this license amendment will not be inimical to the corren defense and security or to the health and safety of the public; and E.

The issuance of this amer.cment is in accodance with 10 CFR Part 51 of the Ccamitsion's regulations and all applicable requirements have been satisfied.

L 8907120176 890705 PDR ADOCK 05000482 P

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Accordingly, the license.is amended by changes to the Technical Specifi-cations Es indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:

2.

Technical Specifications The. Technical Specifications contained in Appendix A, as revised through Amendment No. 32, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the

' Environmental Protection Plan.

3.

The. license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISS10tl ew% r0.

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Frederick J. Hebdon, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 5, 1989 1

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1 ATTACHMENT TO LICENSE AfiENDMENT t:0. 32 FACILITY OPERATING LICENSE NO. NPF-42

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DOCKET NO. 50-482 Revise Appendix A Tect.o 91 Specifications by removing the pages identified below and inserting the

losed pages. The revised pages are identified by

{

amendrent number and contain. marginal lines indicating the area of change.

l The corresponding overleaf pages are also provided to maintain document cor.pleteness.

REMOVE PAGES INSERT PAGES 3/4 1-19 3/4.1-19 3/4 1-22 3/4 1-22 i

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REACTIVITY CONTROL SYSTEMS

-ROD DROP TIM:

i

-LIMITING CONDITION FOR OPERATION l

l 3.1.3.4 The individual tall-length shutdown and control rod drop time from.

the physical fully withdrawn position shall be less than or equal to 2.2 seconds l

from beginning of decay of stationary gripper coil voltage to dashpot entry with;

a. ' T,yg greater than or equal to 551 F, and b.

All reactor coolant pumps operating.

l APPLICABILITY:

MODES I and 2.

ACTION:

With'the rod drop time of any full-length rod determined to exceed a.

the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

-With the rod drop times within limits but determined with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 66% of RATED THERMAL POWER.

SURVEILLANCE RE0UIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

For all rods following each removal of the reactor vessel head, a.

b.

For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific reds,, and c.

At least once per 18 months.

1' l

W?Le CREEK - UNIT 2 3/4 1-19 Amendment No.32

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-REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT

. LIMITING CONDITION FOR OPERATION l

3.1.3.5~ All shutdown rods shall be fully withdrawn.

-APPLICABILITY: -MODES 1* and 2*#.

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specific'ation 4.1.3.1.2, within I hour either:

a.

Fully withdraw the rod, or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined fully withdrawn:

i a.

Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an approach to reactor criticality, and

' b.

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

• See Special Tect Exceptions Specifications 3.10 2 and 3.10.3.

1. With K,ff greater than or equal to 1.

WOLF CREEK - UNIT 1 3/4 1-20

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITIN3 CONDITION FOR OPERATION 3.1. 3. 6 The control banks shall be limited in physical insertion as shown in Figure 3.1-1.

-APPLICABILITY:

MODES 1* and 2*#.

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:

Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or a.

b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to itss than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the above figure, or Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

"See special Test Exc+ptions Specifications 3.10.2 and 3.10.3.

1. With K,ff greater than or equal to 1.

1 i

WOLF CREEK - UNIT 1 3/4 1-21

(FULLY WITHDRAWN +)

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RELATIVE POWER (Percent)

FIGURE 3.1-1 ROD BANK INSERTION LIMIT VERSUS THERMAL POWER-FOUR LOOP OPERATION

• Fully Withdrown sho!! be the condition where control rods are et a position within the interval of h 222 and c 231 steps withdrawn.

WOLF CREEK - UNIT I 3/4 l-22 Amendment No.32

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