ML20247H452

Application for Amend to License NPF-42,revising Tech Spec Surveillance Requirements 4.9.6.1 & 4.9.6.2 to Change Time When Surveillances Must Be Performed

ML20247H452
Person / Time
Site:	Wolf Creek
Issue date:	07/25/1989
From:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247H457	List: ML20247H452 ML20247H464
References
WM-89-0197, WM-89-197, NUDOCS 8907310026
Download: ML20247H452 (7)

Text

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,) m-7 s W$A.FCREEK NUCLEAR OPERATING CORPORATION July 25, 1989 g%

c Y M omcer WM 89-0197 l

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C., 20555 7

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Subject:

Docket No. 50-462: Revision to Technical' Specification Surveillance Requirements 4.9.6.1 and 4.9.6.2 - Refueling Machine and Auxiliary Holst Gentlemen:

The purpose of this letter is to transmit an application for amendment to-Facility Operating License No. NPF-42 for. Wolf Creek Generating Station (WCGS),

Unit No. 1. This license amendment request proposes revising Technical.

Specification Surveillance Requirements 4.9.6.1 and 4.9.6.2 to change the time when the surveillance must be performed.

-A complete Safety Evaluation and. No significant Hazards Consideration determination are provided as Attachments I and II respectively. The proposed.

changes to the Technical Specifications are provided as Attachment III.

In accordance with 10 CFR 50.91, a copy of this application, with attachments is being provided to the designated Kansas State official. This proposed revision to the WCGS Technical Specifications will be fully implemented within 30 days of formal Nuclear Regulatory Commission approval.

If you have any questions concerning this matter, please contact me or Mr. O. L.

Maynard of my staff.

Very truly yours, Bart D. Withers President and Chief Executive Officer BDW/aem 1

Attachments I - Safety Evaluation II - Addressing The Standards in 10 CFR 50.92 III - Proposed Technical Specification Changes cc G. W. Allen (KDHE), w/a B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a [j0I R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364 8831 890731OO26 890725 FDR ADOCK 05000482 An Equal Opportunity Emp6 oyer MT/HC/VEI P FDC

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Bart D. Withers, of lawful age, being first duly sworn upon oath says that he is President and Chief Executive Officer of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the content thereof that he has executed that came for and on behalf of said Corporatic, a with full power and authority to do so; and that the facts thereir. hted a.=e true and correct to the best of his knowledge, informe nor. and belief, a

By Bart'D. Withers President and Chief Executive Officer SUBSCRIBED and sworn to before me this N day of 'f,,1989.

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ATTACliMENT I SAFETY EVALUATION i

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Attachm%nt I to WM 89-0197 Page l'of 2 L

SAFETY EVALUATION i

Technical Specification Surveillance Requirements 4.9.6.1 and 4.G.6.2 curk require the Refueling Machine used for movement of fuel assemblies and q Auxiliary Hoist and associated load indicator used for movement of drive rods %

be demonstrated Head.

The operability operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to removal of the Reactor Ve requirements for the refueling machine and auxiliary ss hoist ensure that:

1) manipulator cranes will be used for movement of fuel assemblies and drive rods, 2; each crane has sufficient load capacity to lift a fuel assembly or a drive rod. and

3) the Core Internals and Reactor Vestel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

The proposed technical specification change would revise Surveillance Requirement 4.9.6.1 to require the Refueling Machine to be demonstrated operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the movement of fuel assemblies within the Reacter Vessel. The proposed change would also revise Surveillance Requirement 4.9.6.2 to require the Auxiliary Hoist to be demonstrated operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> l prior to the movement of drive rods within the Reactor Vessel. As Technical Specifications currently read, the Refueling Machine and the Auxiliary Holst both must be proven operable 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to lifting the Reactor Vessel Head.

The sequence of events for commencement of Fuel Movement during a Refueling Outage is as follows:

1) Strip Vessel Head of support equipment.

2) Detension Vessel Head Studs and remove them to storage area.

3) Lift Vessel Head and place it in it's storage location.

4) Raise Reactor Coolant Level and Refueling Pool level up to 23 feet above the Fuel Assemblies and unlatch the Control Rods, using the Auxiliary Holst.

5) Level is then raised to 23 feet above the Reactor Vessel Flange and the Upper Internals is removed from the Reactor Vessel and placed in its storage location.

6) Fuel Assemblies are then removed from the Reactor Vessel using the Refueling Machine (Manipulator Crane).

The Auxiliary Hoist is not required until the Control Rods are to be unlatched and the Refueling Machine is not required until the start of fuel movement. As shown in the Refueling Sequence above, neither the Auxiliary Hoist or Refueling Machine are required until after removal of the reactor vessel head.

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, past, Reactor Vessel Eead lifts have been delayed until the surveillance l procedures could be completed satisfactorily for the Refueling Machine even l though it was not needed.

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'Attachmsnt I'to WM 89-0197 Page'2 of 2-

. As the Reactor Vessel Head Studs are being detensioned and removed prior to. the Reactor Vessel Head 111ft. 'the Reactor Coolant level is maintained at least one  ;

foot below.the Vessel Flange. During this' period of time, the Reactor Coolant System (RCS) is in a reduced inventory situstion. If the Reactor Vessel Head is ready to be lifted but a' problem exists on the Refueling Machine or the

- Auxiliary Hoist..the RCS will have to remain in this reduced inventory situation until the surveillance requirements are met Should a loss of- Residual Heat

. Removal occur at this time, there would be less water inventory available for a heat sink. If the Surveillance requirements did not need to'be met until the h equipment is! needed, then the head could.be lifted. With the head already lifted, the Reactor Coolant level could be raised to the control rod unlatch level, thus considerably increasing the available heat sink for the core.

Based on the above discussions and the considerations presented in Attachment' II, the proposed revision to the WCGS Technical Specifications does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; or- create a possibility for an accident or malfunction of a different type than-any previously evaluated in the safety analysis reports or reduce the margin of safety. as defined in the basis for any technical specification.

l Therefore, the proposed revision does not adversely affect or endanger the health or safety of the general public or-involve a significant safety hazard.

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ATTACMENT II ADDRESSING THE STANILULDS IN 10 CFR 50.92 i

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, Attachm:nt II to WM 89-0197 l Page 1 of 1 l

ADDRESSING THE STANDARDS IN 10 CFR 50.92 The proposed technical specification change would revise . Surveillance Requirement 4.9.6.1 to require the Refueling Machine to be demonstrated operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the movement of fuel assemblies within the Reacter Vessel. The proposed change would also revise Surveillance Requirement 4.9.6.2 to require the Auxiliary Hoist to be demonstrated operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the movement of drive rods within the Reactor Vessel. As Technical Specifications currently read, the Refueling Machine and the Auxiliary Hoist both must be proven operable 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to lifting the Reactor Vessel Head. The following sections discuss the proposed changes under the three 10 CFR 50.92 standards:

Standard 1 - Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated.

This proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change only involves whether the Refueling Machine has to be demonstrated operable prior to Reactor Vessel Head Lift, or prior to when it is required. The Refueling ,

Machine and the Auxiliary Hoist does not perform any function until after the i Head has been lifted and the Refueling Pool has been partially flooded. i Standard 2 - Create the Possibility of a New or Different Kind of Accident From any Accident Previously Evaluated.

This proposed change does not create the possibility of a new or different kind of accident previously evaluated. This change does not involve any setpoints or change when any equipment is operated. It is only requiring the Surveillance Requirements for the Refueling Machine and the Auxiliary Hoist be performed prior to using the equipment.

Standard 3 - Inw - C8 gnificant Reduction in a Margin of Safety.

The proposed change does not involve a significant reduction in a margin of safety. This change only involves when a Surveillance Requirement is required, it has no significant changes to any margin to safety.

Based on the above discussions and those presented in Attachment I, it has been determined that the requested Technical Specification revisions do not involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluations; or creat.e the possibility of a new or different kind of accident over previons evaluations; or involve a significant reduction in a margin of safety. Therefore, the requested changes do not involve a significant hazards consideration.

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6 ATTACEMENT III PROPOSED TECHNICAL SPECIFICATION CHANGES l

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. , . s (j REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS'(Continued) ,

the movement of fuel assemblies in the rea to vesse to rer.v; O, the 7:::ter v sec h: d y performing a load test of at least 125%

of the secondary automatic overload cutoff and. demonstrating an automatic load 4

-cutoff when the refueling machine load exceeds the Setpoints of Specification /

3.9.6a.2) and by demonstrating an~ automatic load reduction trip when the load *'

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reduction exceeds the Setpoint of Specification 3.9.6a.3). 1 4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor vessel shall be demonstrated OPERABLE within

'100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to,r:: val of the rc;;ter c::::1 h::d by performing'a load test of at least 1250 pounds. ,

the movement of drive rods within the reactor vessel

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J WOLF CREEK - UNIT 1 3/4 9-7

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