ML20211G663

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Application for Amend to License NPF-9,revising Tech Specs 3.1.4, Rod Group Alignment Limits
ML20211G663
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 08/27/1999
From: Barron H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211G670 List:
References
NUDOCS 9908310328
Download: ML20211G663 (7)


Text

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g]p g Duke Energy Corpor: tion McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078 9340 t

  • (704) 875-4800 0FFICE

. .f '**, (704) 873-4809 FAX August 27, 1999 U.S. Nuclear Regulatory. Commission ATTENTION: Document' Control Desk Washington, DC 20555-0001

SUBJECT:

Duke Energy Corporation (DEC)

McGuire Nuclear Station Unit 1 Docket Nos. 50-369 Proposed Technical Specification Amendment Technical Specification 3.1.4 - Rod Group Alignment Limits.

Introduction

' Pursuant to 10CFR50.90, 10CFR50.91, and 10CFR50.4, this letter submits a one-time exigent license amendment request (LAR) for the McGuire Nuclear Station Facility Operating License (FOL) and Technical Specifications (TS). The changes proposed by DEC in this LAR will provide for the one time extension of the surveillance frequency for TS Surveillance Requirement (TSSR) 3.1.4.2 beyond.the 25% extension allowed by TSSR 3.0.2. This amendment is applicable to Facility Operating License NPF-9 for the McGuire Nuclear Station. It will be effective on issuance and expire upon entering Mode 3 during Unit 1 startup following the Unit 1.End of Cycle 13 (1EOC13) refueling outage.

Background

The safety function of the reactor control rods is to fall into the core for safe shutdown of the reactor on receipt of a reactor trip signal. In lieu of testing this function by tripping the control rods, TSSR 3.1.4.2 provides confidence that all rods are operable by verifying individual control rod movement every 92 days. During a performance of this TSSR on August 21, 1999, the Unit 1 Rod Control System experienced an electrical control system' failure which prevented mevement of some control rods and completion of the TSSR. Assuming a Unit 1 unscheduled outage does not occur prior to the 1EOC13 refueling outage, McGuire proposes to effect repairs and complete TSSR 3.1.4.2 during the 1EOC13 refueling outage, currently scheduled to begin on September 17, 1999.

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l U.S.. Nuclear Regulatory Commission l August-27, 1999 Page 2 of 7 Factoring in-the 25% extension of the surveillance frequency allowed by.TSSR 3.0.2, the late date for completion of TSSR 3.1.4.2 on Unit 1 is September 12, 1999. Approval of this LAR will allow a one time extension of this late date to facilitate completion of TSSR 3.1.4.2 during the 1EOC13 refueling outage.

McGuire Probabilistic Risk Assessment (PRA) analyses indicate that the requested surveillance interval extension is expected to have no significant impact on the McGuire core damage frequency.

Repair of the failed equipment or completion of the surveillance testing at power would introduce the potential for a reactor trip. In'the past, McGuire Nuclear Station has experienced reactor trips while performing maintenance on rod control and reactor trip circuitry at power (reference LERs 369/98-02 and 370/99-04). In addition, if the surveillance testing was continued, the associated rod movement would increase the potential that the control circuits common to all rods might '

experience a fault or be affected by the existing fault, potentially resulting in a reactor trip. McGuire PRA analyses {

indicate that reactor trips at power.do contribute to the Core l Damage Probability. Consequently, repair and completion of the j surveillance testing during an outage will pose less nuclear safety risk than the inherent reactor trip risks associated with online repairs and testing. I The equipment failure which caused the Unit 1 control rod movement problems has not caused the affected rods or the Unit 1 Rod Control System to be inoperable. The intent of TSSR 3.1.4.2

~is to provide confidence that the control rods can trip the reactor by verifying individual rod movement. The BASES for that TSSR state that, if a control rod is experiencing movement problems, but remains trippable and aligned, the control rod is considered to be operable. All Unit 1 control rods currently satisfy the alignment criteria of TS 3.1.4 and TSSR 3.1.4.1. The BASES for TSSR'3.1.4.2 indicates that confidence as to the trippability of the control rod (s) can be obtained by verification that any movement problem is due to an electrical related control system failure and not the result of mechanical binding of the rods. The equipment failure which is preventing ,

movement of some of the Unit 1 control rods is an electrical  !

control system failure which does not affect the ability to trip rods. Since all Unit 1 control rods are trippable and properly aligned, they are operable. Note that the inability to move some i of the McGuire Unit 1 control rods will not impact the ability to !

safely control the reactor during steady state power operations prior to the 1EOCl3 refueling outage. In addition, plant l procedures and processes will ensure the safe controlled shutdown of Unit 1 at the start of the outage. Finally, the subject equipment failure will not impact the ability to trip the reactor if necessary.

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e t U.S. Nuclear-Regulatory Commission August 27,-1999 Page 3 of 7 Exigent Criteria-Given that the rod movement problem was discovered on August 21, 1999, less than 30 days exists to allow for the normal comment period under 10 CFR 50e91. The normal surveillance period of TSSR_3.1.4.2 is 92 days. Factoring in 25% grace as allowed by TS 3.0.2, the surveillance will be due on September 12, 1999. This allows only 22 days from the point of discovery until the point, absent the performance of the surveillance or an amendment, the plant would be forced to shutdown under the requirements of TS 3.0.3. There was no prior opportunity to identify the need for a TS amendment-by Duke Energy. In addition, prior to the performance of the attempted surveillance on August 21, 1999, the rod control system had exhibited normal'E33fEhion. As such, DEC l anticipated successful completion of the surveillance well within  !

the 92 day surveillance period. Duke could not have anticipated i the need tor a license amendment under these circumstances.

Given the above and the determination that this LAR involves no ,

significant hazards as specified under 10 CFR 50.92, DEC believes I the criteria for exigency as described in 10 CFR 50.91 are met. )

Consequently, DEC requests that this LAR be processed as an exigent change pursuant to the requirements of 10 CFR 50.91 (6)

(i) which allows for either (A) a 14 day FEDERAL REGISTER notice i or (B) a local media notice if less than 14 days exists for the FEDERAL REGISTER notice.

Contents of Amendment Request Given the determination that this proposed amendment contains no significant hazards considerations, McGuire maintains that I precluding the possibility of an unnecessary plant transient by implementing this exigent one time LAR is in the best interests of the overall health and safety of the public.

Attachment 1 provides marked up pages of the existing McGuire TS 3.1.4 showing the proposed changes. Attachment 2 contains the new McGuire TS 3.1.4 pages. The Description of Proposed Changes and Technical Justification is provided in Attachment 3.

Pursuant to 10CFR50.92, Attachment 4 documents the determination that this proposed amendment contains No Significant Hazards considerations. Pursuant to 10CFR51.22 (c) (9) , Attachment 5 provides the basis for the categorical exclusion from performing an Environmental Assessment / Impact Statement. Implementation of this amendment to the McGuire FOL and TSs will not impact the McGuire UFSAR.

In accordance with Duke internal procedures and the Quality Assurance Program Topical Report, this proposed amendment has been previously reviewed and approved by the McGuire Nuclear

U.S. Nuclear Regulatory Commission l August 27, 1999 Page 4 of 7 Stdtion Plant Operations Review Committee and the Duke Corporate Nuclear Safety Review Board. Pursuant to 10CFR50.91, a copy of this LAR is being forwarded to the appropriate North Carolina State Officials.

Commitments McGuire intends to repair the failed rod control equipment and perform TSSR 3.1.4.2 during the 1EOCl3 refueling outage.

However, if a Unit 1 unscheduled outage occurs prior to the i 1EOC13 refueling outage, McGuire will perform repairs during that U outage and complete TSSR 3.1.4.2 prior to entering Mode 3 upon startup from that outage. Upon verification of acceptable rod movement, the McGuire NRC Resident Inspector would be notified.

Please direct questions on this LAR to Julius Bryant at 704-875-4162.

Very truly yours,

/lQ 7(f /? 4E4-c4v~~ - ) !

1 H. B. Barron, Vice President 1 McGuire Nuclear Station l

Attachments i

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. . i U.S. Nuclcar Regulatory Commission August 27, 1999 Page 5 of 7 j

. , I xc: (w/ attachments) l l

L.A. Reyes )

Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA. 30323 S.M. Shaeffer NRC Senior Resident Inspector j McGuire Nuclear Station  !

F. Rinaldi NRC Senior Project Manager (MNS)

Office of U.S. Nuclear Reactor Regulation One White Flint North, Mail Stop O-14H25 Washington, D.C. 20555-0001 R.M. Fry, Director Division of Radiation Protection State of North Carolina 3825 Barrett Drive Raleigh, N.C. 27609-7221 l

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l- .U.S. Nuclear Regulatory Commission I

August 27, 1999 Page 6 of 7 H . 'B . Barron, being duly sworn, states that he is Site Vice j President of McGuire Nuclear Station Duke Energy Corporation; i

that he is authorized on the part of Duke Energy Corporation to sign and file with the U.S. Nuclear Regulatory Commission this revision to the McGuire Nuclear Station Facility Operating License No. NPF-9; and, that all statements and matters set forth therein are true and correct to the best of his knowledge.

H. B. Barron, Vice President McGuire Nuclear Station Duke Energy Corporation l

I Subscribed and sworn to before me this 27th day of August 1999.

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MICHAELT. CASH Notary Public Notay PWic Lincoln County, North Carolina l ,

Commission Expires January 22,2003 My Commission Emires:

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-U.S. Nuclear Regulatory Commissioni

' August-87, 1999~

-Page:7.of 7 ibxd: (w.' attachments);

H.B.tBarron'-(MG01VP)

B.L. Peele Jr.. (MG01VP)

B.J. Dolan (MG01VP)

.M.T. Cash (MG01RC)

J.W. Bryant (MG01RC)

' P.T.,Vu~(MG01RC)

. K.L. Crane (MG01RC)

'J.W. Boyle (MG05EE)

.D.M- Jamil (MG01IE)

G.R.'Peterson (CN01VP)

P.R. Herran'(CN01EM)

S.L. Bradshaw (CN01SA)

G.D. Gilbert (CN01RC)

L'.J. .Rudy (CN01RC)

J.J. Fisicaro (EC07Q)

L . A .' Keller- (EC050)

G.B Swindlehurst-(EC08H)

ELL '(EC050)

McGuire-Masterfile i NSRB-Support Staff.(EC05N)

NCMPA-1 ,

NCEMC' PMPA SREC l

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