ML19316A648

Requests Amend to Tech Spec 4.1-2 Re Min Equipment Test Frequency.Proposed Tech Spec Replacement Page & Class III Fee Encl

ML19316A648
Person / Time
Site:	Oconee
Issue date:	06/22/1978
From:	Thies A DUKE POWER CO.
To:	Case E Office of Nuclear Reactor Regulation
Shared Package
ML19316A649	List: ML19316A648 ML19316A650
References
NUDOCS 8001130189
Download: ML19316A648 (4)

Text

6& N Oh (RIDS)

REGULATORY INFORMATION DISTRIBUTION SYSTEM 50-270 DISTRIBUTION FOR INCOMING MATERIAL ORG: THIES A C DOCDATE: 06/22/78 IC: REID R W DATE RCVD: 06/26/78 NRC DUKE PWR COPIES RECEIVED 3CTYPE: LETTER NOTARIZED: YES LTR 3 ENCL 40 JBJECT:

3RWARDING LIC NO DPR-47 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE, JNCERNING REQUEST FOR EMERGENCY ~ REVISION TO~ AUTHORIZE EXTEN 1XIMUM ALLOWABLE SURVEILLANCE INTERVAL ASSOC WITH SURV TEST CONT ECTION 4.1, TABLE 4.1--2 , ITEM 1, durrot 60 #c#enwp-REVIEWER INITI AL: XJM

_ ANT NAME:OCONEE - UNIT 2 DISTRIBUTOR INITI AL:

nooo************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************

OTES:

M. CUNNINGHAM - ALL AMENDMENTS TO FSAR AND CHANGES TO TECH SPECS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE AOO1)

FOR ACTION: BR CH ORB #4 BC**W/7 ENCL G E**W/ ENCL NRC PDR**W/ ENCL INTERNAL: OELD**LTR ONLY

& E**W/2 ENCL HANAUER**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J. MCGOUGH**W/ ENCL i

EXTERNAL: LPDR'S  ;

WALHALLA. SC**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL

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C0$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $ l CHECK NBR: 196,135 )

$4,000.00 $

AMOUNT: $

CHECK AND COPY OF TRANSMITTAL LTR ADVANCED $

TO W. MILLER (LFMB) (06/26/78) UPON RECIEPT C00$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$

CONTROL NBR: 7CC,7v#55- l

'ISTRIBUTION: LTR 40 ENCL 39

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• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4 oco******************************* THE END 1 ,1 + _ ,

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Dcxz' POWER COMPANY Powsm Burtonr3 ese Sours Cmcaca Srmart, C= A=rewrra,N. C. sesos A. c. tmas P. o. Box 237s season veca Possioem?

PeoOUCTeose AND TRA8seulesecas June 22, 1978 i

Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Connaission Washington, D. C. 20555 Attention: Mr. R. Reid, Chief I Operating Reactors Branch #4

Reference:

Oconee Nuclear Station, Unit'2 Docket No. 50-270

Dear Mr. Case:

Oconee Nuclear Station, Unit 2, is currently operating at full rated power with a shorted stator on rod 6 of safety group 4. The rod is being maintained in the fully withdrawn position by phase C-C. Any loss of power to the phase will cause the rod to drop. There is one surveillance test which is required to be performed and, if conducted, will result in momentary loss of power to the stator causing the rod to drop. Wit *. this rod inserted into the core, the unit will be required to be shut down in order to repair the stator. A forced unit shutdown at this time would have a significant and adverse effect on the generating capability of Duke Power's grid system.

In this regard, an emergency revision to the Oconee Nuclear Station Technical Specifications is requested to authorize an extension of seven days to the maximum allowable surveillance interval associated with this survaillance test. This test is based on the requirements contained in Specification 4.1, Table 4.1-2, Item 1, Control Rod Movement. It is required to be performed bi-weekly, and is due by June 27, 1978. If performed, it will result in dropping rod 6 of safety group 4 into the core. With the seven-day extension, this surveillance test would be performed by July 4, 1978. At this later date, the effect of a Unit 2 shutdown would be less severe than earlier in the week. It is proposed that only the portion of this test that directly affects rod 6 of safety group 4 be delayed. The control rod movement test would be performed on all control rods other than rod 6 of group 4 by June 27, 1978. This would provide added assurance that the remaining portions of the rod control system are fully operational, and that the probability of malfunction occurring to any rod control system component during the requested extension period is minimal.

Ol NG O

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Mr. Edson G. Case Page 2 June 22, 1978 This request has.been reviewed by the Nuclear Safety Review Board and the station Technical Review Committee and approved based on the low probability of an occurrence causing a failure of the control rod drive system to perform its design function during this extension period.

This license amendment request is considered to involve a single safety issue relating to a single Oconee unit. Accordingly, please find attached a check, in the amount of $4,000, representing one Class III license fee.

Very truly yours, A.*C. Thies

• ACT:vr Attachment 3

Mr. Edson G. Case Page 3 June 22, 1978 A. C. THIES, being duly sworn, states that he is Senior Vice President of Duke Power Company; that he-is authorized on the part of said Company

~

to sign and file with the Nuclear Regulatory Commission this request for

, amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, DPR-47 and DPR-55; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

A. C. Thies, Senior Vice President Subscribed and sworn to before me this 22nd day of June, 1978.

Yka -

Cd4ac Notary Public My Commission Expires:

February 15, 1982 I

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