ML20148J177

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Application for Amend to License DPR-28,changing TSs to Update Section 6.0 to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Validate or Generate cycle-specific Thermal Hydraulic Stability
ML20148J177
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 06/09/1997
From: Reid D
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20148J182 List:
References
BVY-97-77, NUDOCS 9706170016
Download: ML20148J177 (3)


Text

. . . . -- - . - . _ - . ..- - . , . . . - - . - . .. .

VERMONT YANKEE

' NUCLEAR POWER CORPORATION

~; ~

Ferry Road. Brattleboro, VT 05301-7002 l ENGINE IN OFFICE i

, 580 MAIN STREET )

, BOLTON. M A 01740 l (508) 779-6711 June 9,1997  :

BW 97-77 l United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter, USNRC to VYNPC, NW 88 224, Generic Letter 8816, dated 10/4/88.

(c) Letter, USNRC to WNPC, NW 96-175, Safety Evaluation of the Power / Flow Exclusion Region Calculation Method Using the LAPURS Computer Code and Implementation of the SOLOMON Stability Monitor for Vermont Yankee Nuclear Power Station (TAC NO. M94207), dated 11/5/96.

(d) Report, YAEC-1926, Method for Power / Flow Exclusion Region Calculation i Using the LAPURS Computer Code, dated 9/22/95.

l

Subject:

Proposed Technical Specification Change No.191 to Update Section 6.0

" Administrative Controls"  ;

l Pursuant to Section 50.90 of the Commission's rules and regulations, Vermont Yankee Nuclear Power Corporation (VYNPC) hereby proposes the following change to Appendix A of the Vermont Yankee operating license (Reference a).

Proposed Chance Vermont Yankee proposes to change the Technical Specifications to update Section 6.0 to add and revise reference to NRC approved methodologies which will be used to validate or generate the cycle-specific thermal hydraulic stability based operating limits in the Vermont Yankee Core Operating Limits Report (COLR).

i Specifically, the change proposed is as follows:

? \ I l Page 270 of the Vermont Yankee Technical Specifications has been modified to incorporate the j stability methods reference.

Reuson for Chance f/))

in accordance with the guidelines provided by the NRC in Reference (b), Section 6.0 of the Vermont Yankee Technical Specifications contains a list of methods approved by the NRC to generate the thermal limits specified in the Vermont Yankee COLR. Additional methods developed by Yankee 9706170016 970609 PDR ADOCK 05000' 1 g,,,

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. June 9,1997 VERMONT YANKEE NUCLEAR POWER CORPORATION Page 2 Atomic Electric Company, approved by the NRC in Reference (c), are to be used in the thermal hydraulic stability analysis. These methods are described in Reference (d). It is necessary that these methods be added to the list appearing in Section 6.7.A.4 of the Technical Specifications.

Basis for Chanae in accordance with guidance provided in Reference (b), Technical Specification 6.7.A.4 lists the NRC-approved methods which can be used to generate the cycle specific limits in the COLR, Additional methods not currently in this list have been approved by the NRC. Vermont Yankee intends to use these approved methods to validate or determine the thermal hydraulic stability limits for future reloads.

This change adds the reference for the stability analysis to the Specification 6.7.A.4 references.

Safetv Considerations The proposed change does not constitute an unreviewed safety question as defined in )

10CT R50.59(a)(2) since it is administrative in nature, serving only to update the Administrative Controls section of the Technical Specifications. All the methods referenced herein have been previously j approved by the NRC. '

This Proposed Change has been reviewed by the Vermont Yankee Plant Operations Review Committee (PORC) and the Nuclear Safety Audit and Review Committee (NSARC). l

)

Slanificant Hazards Consideration The Standards used to arrive at a determination that a request for amendment involves no significant hazards are included in the Commission's regulations (10CFR50.92) which state that the operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. In addition, the Commission has provided guidance in the practical application of these criteria in 51FR7751, dated March 6,1986.

The discussion below addresses each of these criteria and demonstrates that the proposed amendment involves no significant hazards consideration.

1. The proposed change will not involve any significant increase in the probability or <

consequences of an accident. The change updates the Technical Specifications to include a NRC approved method reference to allow calculation of thermal hydraulic stability limits. It does not affect plant operation and will not weaken or degrade the facility.

2. The proposed change will not create the possibility of a new or different kind of accident since the change is administrative. No physical alterations of the plant, setpoint changes, or operating conditions are proposed.
3. The proposed change will not involve a significant reduction in a margin of safety. The change involves an update to the Administrative Controls in Section 6.0 of the Technical Specifications by adding a reference to NRC approved methods. This administrative change does not alter plant safety margins.

U uci ar Regulatory Commission V RMONT YANKEE NUCLEAR POWER CORl' ORATION Page 3 The implementation of the proposed change willinclude an update to the Core Operating Limits Report as required by Section 6.7.A 4 of the Technical Specifications to include the reference to the subject  ;

approved methods.

Based on the above discussion, we have determined that this proposed license amendment does not constitute a significant hazard as defined in 10CFR50.92.

Environmental Imoact Consideration:

Vermont Yankee has reviewed this request against the criteria of 10CFR51.22 for categorical exclusion '

from environmentalimpact considerations. The proposed changes do not involve a significant hazards i consideration or significantly increase the amounts or change the types of effluents that may be released offsite, nor do they significantly increase individual or cumulative occupational radiation exposure. Based on the foregoing, Vermont Yankee concludes that the proposed change meets the -

criteria given in 10CFR51.22(c)(9) for categorical exclusion from the requirement for an Environmental Impact Statement. i Schedule for Chanae We request that your review and approval of the proposed change be completed by October 15,1997 in order to include this method in the generation of the Cycle 20 Core Operating Limits Report. This l change will be incorporated into the Vermont Yankee Technical Specifications as soon as practical i following receipt of your approval.  ;

We trust that the information above adequately supports our request; however, should you have any l questions in this matter, please contact us.  ;

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION ,

Donald A. Reid Sr. Vice President, Operations

,4 N cc: USNRC Region 1 Administrator v - Ogh USNRC Project Manager, VYNPS USNRC Resident inspector, VYNPS [/ ,

k STATE OF VERMONT ) g y

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WINDHAM COUNTY )

  • v Then personally appeared before me, Donald A. Reid, who, being duly sworn, ice President, Operations, of Vermont Yankee Nuclear Power Corporation, that he is duly authort .

ile the foregoing document in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, ano mm me statements therein are true to the best of his knowledge and belief.

Sally A. Sa6dstrum, Notary Public My Commission expires February 10,1999