ML20235A510

Application for Amend to License NPF-42,revising Tech Spec 3/4.3.1 Re Reactor Trip Sys Instrumentation in Accordance W/ Generic Ltr 85-09.Safety Evaluation & Significant Hazards Consideration Encl.Fee Paid

ML20235A510
Person / Time
Site:	Wolf Creek
Issue date:	06/29/1987
From:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235A512	List: ML20235A510 ML20235A553
References
GL-85-09, GL-85-9, WM-87-0177, WM-87-177, NUDOCS 8707080461
Download: ML20235A510 (9)

Text

r

.i LF CREEK W@ NUCLEAR OPERATING Bart D. Withers President and Chief Executive otheer June 29, 1987 U.S. Nuclear Regulatory Conmission ATI'N: Document Control Desk Washington, D.C. 20555 Letter: WM 87-0177 Re:

Docket No. 50-482 Subj:

Revision to Technical Specification 3/4.3.1 - Reactor Trip System Instrumentation (Generic Letter 85-09)

Gentlemen:

The purpose of +nis letter is to transmit an application for amendment to Facility Operating License No.

NPF-42 for Wolf Creek Generating Station, Unit No.

1.

This license amendment request proposes revising Technical Specification 3/4. 3.1, which addresses Reactor Trip System Instrumentation.

This application for amendment revises Technical Specification 3/4.3.1, Reactor Trip System Instrumentation, in accordance with the requirements of Generic Letter 85-09.

A coJplete Safety Evaluation and Significant Hazards Consideration are provided as Attachments I and II respectively.

The proposed changes to the Technical Specification are provided in Attachment III.

In accordance with 10 CFR 50.91, a copy of this application for amendment with attachments is being provided to the designated Kansas state official.

Enclosed is a check (No.000202) for the $150.00 application fee required by 10 CFR 170.21.

i 1

A- (s@o$9

$5 8707080461 B70629 0

g gh DR ADOCK 0500 2

P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364 8831 An Eaual opportunity Ernpioyer M'F/HC/ VET t

4

WM 87-017'i Page 2 June 29,1987 The proposed revision to the Wolf Creek Generating Station Technical Specifications will be fully implemented within 30 days of formal Nuclear Regulatory Comission approval.

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

Very truly y urs, kn _-

-s Bart D. Withers President and 3DN.jad Chief Executive officer Enclorr tre Attachwients:

1, Safety Evaluation II - Significant Hazards Consideration III - Proposed Technical Specification Change cc:

PO'Connor (2)

JCumins GAllen RMartin I

l STATE OF KANSAS

)

) S3 COUNTY OF C0FFEY

)

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 kr.ows the content thereof; that he has executed that same for and on behalf of said j

Corporation with full power and authority to do so; and that the facts 1

therein stated are true and correct to the best of his knowledge, information and belief.

By Bart'D. Withers President and Chief Executive Officer SUBSCRIBED aiid sworn to before me this,2 f day of 1987.

j

%sLa /

i

},.*......1.9*[>,

n

+

Notary Public

,,. N

.O C y A~,g m.

e Expiration Date f ufad Qg()

b

,- y

()

l

6 e

O ATTAOMPRP I i

SAFETY EVALUATION I

l i

i

Attachment I to WM 87-0177 Page 1 of 2 June 29,1987 SAFEfY EVMinTION This Amendment Pequest revises Wolf Creek Generating Station (NCGS),

Unit No. 1, Technical Specification 3/4.3.1, Reactor Trip System Instrumentation in accordance with the requirements of Generic Letter 85-09.

Background

on May 23, 1985 the Nuclear Regulatory Comnission (NRC) issued Generic Letter 85-09 to all Westinghouse Pressurized Water Reactor Licensees.

The Generic Letter explicitly described Technical Specification revisions required by Item 4.3 of Generic Letter 83-28, "Requireo Actions Based on Generic Implications of Salem ATWS Events".

Item 4.3 in part established the requirement for the automatic actuation of the shunt trip attachment for Westinghouse plants.

Based on a review of the Westinghouse design for automatic actuation of the shunt trip attachments the NRC Staff concluded that revisions to Licensee Technical Specifications were required to explicitly require independent testing of the undervoltage and shunt trip attachments during power operation and indeoendent testing of the control room manual switch contacts during each refueling cutage.

The Staff concluded that these changes were necessary to ensure reliable operation of the Reactor Trip Breakers.

Evaluation In response to the NRC requirements the following Technical Specification revisions are being proposed:

1.

ACTION 12 is being added to Table 3.3-1.

This action statement corresponds to Functional Unit 19 (Reactor Trip Breakers) and allows continued plant operation for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with one of i

the diverse trip features inoperable.

The proposed Reactor Trip Breaker surveillances will serve to independently verify the operability of the shunt and undervoltage trip features. There is a high degree of confidence that the remaining operable trip feature would be capable of initiating a reactor trip within the allowed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

2.

Table Notation 11 of Table 4.3-1 has been revised to verify the operability of the undervoltage and shunt trip circuits for Functional Unit 1 (Manual Reactor Trip).

This notation will also verify the OPERABILITY of the Bypass Breaker trip circuits.

3.

Table Notation 14 is being added to Table 4.3-1.

This notation corresponds to Functional Unit 19 (Reactor Trip Breaker).

The proposed notation requires that the TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip

Breakers, i

l j

l

Attachment I to WM 87-0177 Page 2 of 2 June 29, 1987 4.

Table 4.3-1 is being revised to add Functional Unit 21.

(Reactor Trip Bypass Breaker).

This Functional Unit requires a TRIP ACTUATING DEVIC 2 OPERATIONAL TEST (TADOT).

Table Notation 15 requires a. local manual shunt trlp prior.to placing the breaker in service.

Table Notation 16 requires an automatic undervoltage trip.

The proposed revisions to the Wolf Creek Generating Station Technical i

Specification is based upon the NRC Staff evaluation of the Westinghouse shunt trip attachment design and the requirements of Generic Letter 85-09.

The proposed revisions will not. affect the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report..

These revisions serve to ensure the reliable operation of the Reactor Trip Breakers without unnecessarily compromising their overall availability.

The proposed revisions would not create the possibility for'an accident or malfunction of a different type thau any previously evaluated in the Safety Analysis Report.

No additional plant equipment is being added nor will any existing plant equipment be operated in_a manner inconsistent with existing requirements.

The proposed revisions do not affect the margin of safety as defined in the I

basis for any Technical Specification.

These revisions do not alter any instrumentation calibration, setpoints or logic.

Conclusicn Based on the above discussion and the considerations presented in Attachment II, the proposed revisions to Technical Specification 3/4.3.1 do not increase the probability of eccurrences or the cons quences of an accident or malfunction of equipment 'important to safety puviously evaluated in the Safety Analysis Report; or create the possibility for an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report; or reduce the margin of safety as defined in the basis for any Technical Spacification.

Therefore, the proposed revisions do not adversely affect or endanger the health and safety of the general public or involve a significant safety hazard.

i i

i 1

ATT1CfMINT IT SIGIFICMff HAZARDS CONSIDERATION

Attachment II to WM 87-0177 Page 1 of 2 June 29, 1987 SIGNIFICANT HAZARDS CONSIDERATION This Amendment Request revises Wolf Creek Generating Station (WCGS),

Unit No. 1, Technical Specification 3/4.3.1, Reactor Trip System Instrumentation in accordance with the requirements of Generic Letter 85-09.

1 In response to the NRC requirements issued in Generic Letter 85-09, the j

following revisions are being made to Technical Specification 3/4.3.1:

l.

ACTION 12 is being added to Table 3.3-1.

This action statement corresponds to Functional Unit 19 (Reactor Trip Breakers) and allows continued plant operation for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with one of the diverse trip features inoperable.

The proposed Reactor Trip Breaker surveillances will serve to independently verify the operability of the shunt and undervoltage trip fu tures. There is a high degree of confidence that the reman ing operable trip feature would be capable of initiating a reactor trip within the allowed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

2.

Table Notation 11 of Table 4.3-1 has been revised to verify the operability of the undervoltage and shunt trip circuits for Functional Unit 1 (Manual Reactor Trip).

This notation will also verify the OPERABILITY of the Bypass Breaker trip circuits.

3.

Table Notation 14 is being added to Table 4.3-1.

This notetion corresponds to Functional Unit 19 (Reactor Trip Breaker).

The proposed notation requires that the TRIP ACTUATING DEVICE 3

OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

4.

Table 4.3-1 is being revised to add Functional Unit 21 (Reactor Trip Bypass Breaker).

This Functional Unit requires a TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT).

Table Notation 15 requires a local manual shunt trip prior to placing the breaker in service.

Table Notation 16 requires an automatic undervoltage trip.

The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

These changes are being proposed to comply with NRC requirements issued in Genaric Letter 85-09.

These changes serve to ensure the reliable operation of the Reactor Trip Breakers without unnecessarily compromising their overall availability.

An allowed outage time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is established for the loss of one diverne trip feature (undervoltage or shunt trip attachment).

This is consistent with the requirements of the proposed surveillances j

(Table Notations) to independently verify the OPERABILITY of the undervoltage and shunt trip attachments, their associated circuits, and the bypass breakers.

Thus the temporary inoperability of one of the diverse trip features would not significantly affect the capability of initiating a reactor trip within the allowed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The proposed changes do not significantly affect the ability of the Reactor Trip Breakers to perform their safety function.

Attachment II to WM 87-0177 Page 2 of 2 i

June 29,1987 i

The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

There are no new failure modes or mechanisms associated with the proposed changes.

These changes do not involve any modification in the operational limits or physical design of the involved systems.

The changes establish an ACTION statement allowed outage time based upon confidence in the operability of diverse features and appropriate surveillance requirements in accordance with NBC requirements.

i The proposed changes do not involve a significant reduction in a :argin of safety.

These changes do not affect any Technical Specification margin of safety. The capability of the Peactor Trip Brea.kars to perform their safety

' function is not significantly affected by the propcsed Technical Specification revision.

The Conmission has established guidance concerning the determination of whether a significant hazards consideration exists by provid.:ng certain examples (51 FR 775) of amendaents not likely to involve a significant hazards consideration.

The proposed Technical Specification 3/4.3.1 conforms to NRC example (ii)

"A change that constitutes an additional limitation, restriction or control not presently included in the technical specifications, e.g. a more stringent surveillance requirement."

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 create the possibility of a new or different kind of accident or condition over previous evaluations; or involve a significant reduction in a margin of safety.

Therefore, the requested license amendment does not involve a significant hazards condition.

l

.