2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2

Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2

ML20132G318
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/19/1996
From:	Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20132G323	List: 2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2 ML20132G325
References
2CAN129604, NUDOCS 9612260233
Download: ML20132G318 (5)

Text

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. s Ent:rgy oper:tions,Inc.

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Tel 501-8%4888 C. Randy Hutchinson Vce Presaw O(Watuis ANO December 19,1996 2CAN129604 U. S. Nuclear Regulatory Commission ,

Document Control Desk Mail Station PI-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specification Change Request Concerning Reactor Coolant System Volume Gentlemen:

Attached for your review and approval is a proposed amendment to the Arkansas Nuclear .

One, Unit 2 (ANO-2) Technical Specifications. The proposed amendment deletes the specific l value for the total reactor coolant system (RCS) volume in specification 5.4.2. This l information is currently included in the ANO-2 Safety Analysis Report (SAR). This change is l needed to support a steam generator tube plugging limit above 13%. This change is consistent with NUREG-1432, Revision 1, improved " Standard Technical Specifications for Combustion Engineering Plants" (ISTS).

The proposed change has been evaluated in accordance with 10CFR50.91(a)(1) using criteria j in 10CFR50.92(c) and it has been determined that this cherce involves no significant hazards considerations. The bases for these determinations are inc~ Med in the attached submittal.

This was one of several changes previously requested in correspondence dated August 23,  ;

1996 (2CAN089609). By letter dated October 28,1996 (2CNA109604), the Staffinformed Entergy Operations that the requested review schedule could not be met and requested that ,

the specific changes needed to support the upcoming refueling outage be submitted separately.

Entergy Operations requests that the effective date for this change be within 30 days of issuance. Although this request is neither exigent nor emergency, your prompt review is requested prior to the next ANO-2 refueling outage (2R12) which is currently scheduled to begin April 25,1997.

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U. S. NRC December 19,1996 2CAN129604 Page 2 Ve ly - rs, /A

/ r A4 CRH/nb Attaciunents To the best of my knowledge and belief, the statements contained in this submittal are true.

SUBSCRIBED AND SWORN TO before me, a Notary Public in and fo m County and the State of Arkansas, this lC) day of Owode ,19967 Aum #B JUb$.$PP 80 uneveuauc.umse Notary Pubig My Commission Expires /I 4 M% u,d,"$ ,, ,

cc: Mr. Leonard J. Callan Regional Administrator i U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 l Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman i NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3  ;

One White Flint North 1 11555 Rockville Pike i Rockville, MD 20852 Mr. Bernard Bevill Acting Director, Division of Radiation Control and Emergency Management Arkansas Department ofHealth 4815 West Markham Street Little Rock, AR 72205

t ATTACHMENT IO__ ,

2CAN129604 i

PROPOSED TECHNICAL SPECIFICATION AND RESPECTIVE SAFETY ANALYSES IN THE MATTER OF AMENDING LICENSE NO. NPF-6 ENTERGY OPERATIONS. INC.

ARKANSAS NUCLEAR ONE. UNIT TWO DOCKET NO. 50-368 I

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! ' Attachment to  ;

2CAN129604 Page 1 of 2 q

. l DESCRIPTION OF PROPOSED CHANGES j l

Specification 5.4.2 which specifies the total water and steam volume of the RCS is being  ;

deleted from the technical specifications.

BACKGROUND I This change was one of several changes that was previously requested in correspondence l dated August 23,1996 (2CAN089609). In this correspondence, ANO had proposed

! relocating a major portion of the design features section of the technical specifications to  ;

l licensing basis documents controlled under the provisions of 10CFR50.59. This proposal was

. consistent with the format of the ISTS which ANO-2 has committed to convert to in )

correspondence dated June 21,1995 (0CAN069502). By letter dated October 28, 1996 i (2CNA109604), the Staffinformed Entergy Operations that the requested review schedule could not be met and requested that the specific changes needed to support the upcommg l 2R12 refueling outage be submitted separately. l DISCUSSION OF CHANGE  !

The proposed amendment request deletes the total RCS volume from the technical  !

specifications in accordance with the ISTS. The ANO-2 SAR currently contains the RCS volume information. The technical specification information with respect to RCS volume is being removed because it is already controlled in a licensee controlled document under the requirements of10CFR50.59.

The RCS volume in the design features section of the technical specifications is a nominal hot zero power value with a tolerance for uncertainties. RCS volumes consistent with standard rsfety analysis methodologies which appropriately account for plugged steam generator tubes are used in the ANO-2 safety analyses. The RCS volume design information is currently given in SAR Tables 5.1-1, 5.1-2, 5.5-2, 5.5-6, and 6.2-8 which is controlled via the 10CFR50.59 process.

The technical specification nominal value for RCS volunse contains no allowance for steam  ;

generator tube plugging. The technical specification nominal value for RCS volume minus j uncertainties corresponds to having approximately 13% average length steam generator tubes i plugged. This change is needed to support a steam generator tube plugging limit above i approximately 13%. In order to ecconunodate greater than 13% steam generator tube plugging,' a change to RCS volume would be necessary. Future changes to the RCS volume would then be evaluated under 10CFR50.59.

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Attachment to 2CAN129604 Page 2 of 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION An evaluation of the proposed change has been performed in accordance with 4

10CFR50.91(a)(1) regarding no significant hazards considerations using the standards in 10CFR50.92(c). A discussion of these standards as they relate to this amendment request follows:

Criterion 1 - Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated.

This propo;ed change allows the relocation of the reactor coolant system volume in the design features section of technical specifications to the safety analysis report. Future changes will be controlled under 10CFR50.59. This change is considered administrative in nature.

Appropriate values of reactor coolant system volume are used in the safety analyses. This 4 change does not affect any system or component functional requirements. The operation of the plant is not affected by this change.

Therefore, this change does not involve a significant increase in the probability or consequences of any accident previously evaluated.

Criterion 2 - Does Not Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated.

The relocation of existing requirements from the technical specifications to another licensee l controlled document is administrative in nature. This change does not modify or remove any i plant design requirement. The proposed change will not affect any plant system or structure, j nor will it affect any system functional or operability requirements. Therefore, no new failure  ;

modes are introduced as a result of this change.

Therefore, this change does not create the possibility of a new or different kind of accident from any previously evaluated.

Criterion 3 - Does Not Involve a Significant Reduction in the Margin of Safety.

The proposed amendment request relocates the coolant system volume located in the technical specifications design feature section to another licensee controlled document, the ANO-2 Safety Analysis Report, which is controlled under 10CFR50.59. The proposed change is administrative in nature because the design requirements for the facility remain the same. The proposed change does not represent a change in the configuration or operation of the plant.

Therefore, this change does no_1 involve a significant reduction in the margin of safety.

Therefore, based upon the reasoning presented above and the previous discussion of the amendment request, Entergy Operations has determined that the requested change does not involve a significant hazards consideration.