ML20217P396

Proposed Change 202 to License DPR-28,changing Several Editorial Changes to Administrative Control Section of TSs

ML20217P396
Person / Time
Site:	Vermont Yankee
Issue date:	05/01/1998
From:	Reid D VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217P400	List: ML20217P396 ML20217P417
References
BVY-98-63, NUDOCS 9805060274
Download: ML20217P396 (6)

Text

,

VERMONT YANKEE

.(,.

(5 NUCLEAR POWER CORPORATION

• 185 Old Ferry Road, Brattleboro, VT 05301-7002 (802) 257-5271 May 1,1998 ,

BVY 98-63 U. S. Nuclear Regulatory Commission ,

ATTN: Document Control Desk i Washington, D.C. 20555

Reference:

(a) Letter, VYNPC to USNRC, Response to Request for Information Regarding Adherence to Quality Assurance Program Provisions, BVY 98-55, dated April 10, 1998.

I

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

Technical Specification Proposed Change No. 202 Administrative Chances to VY Technical Specifications In accordance with 10CFR50.90, Vermont Yankee Nuclear Power Corporation (VYNPC) requests that Appendix A of the Facility Operating License be amended to modify the Vermont Yankee Technical Specifications. This change will make several editorial changes to our Administrative Controls (6.0) section of Technical Specifications.

VYNPC has determined that the proposed license amendment does not involve a significant hazards consideration pursuant to 10CFR50.92. A description of the amendment is provided in Attachment 1. The no significant hazards determination is provided in Attachment 2. Attachment 3 provides marked up copies of the current Technical Specification pages. Attachment 4 prosides the revised new Technical Specification pages.

VYNPC requests review and approval of this proposed amendment by June 1998 with a thirty day l implementation schedule.

Should there be any questions regarding this submittal, please contact this office.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPCRATION

, *[

v * '# Donald A. Reid ~~ '

Senior Vice Presi/ent, Operations g}

@_O 9805060274 990501 PDR ADOCK 05000271 p PDR l.

VERMONT YANKEE NUCLEAR POWER CORPORATION BVY 98-63 4 b 8b' Y'c-Page 2 of 2 NOTAR't STATE OF VERMONT ) 793g0 gj WINDilAM COUNTY count y j l Then perscnally appeared before me, Donald A. Reid, who being duly sworn, did state that he is Senior Vice President, Operations of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

! l hbA s

Sally A. sandstrum, Notary Piiblic My Commission Expires February 10,1999 l

l Attachments cc: USNRC Region 1 Administrator i

USNRC Resident Inspector - VYNPS }

USNRC Project Manager - VYNPS 1 Vermont Department of Public Service l l

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I VERMONT YAN.KEE NUCLEAR POWER CORPORATION ATTACilMENT 1 Page1of2 DESCRIPTION OF TECHNICAL SPECIFICATIONS CilANGE REQUEST Page 255, revise the last sentence of section 6.1.A. to read "These requirements shall be documented in the Vermont Yankee quality assurance program."

Page 255-257, revise various paragraphs to reflect current titles of key supervisory personnel.

. Page 258, revise paragraph 6.2.A.1 to reflect current titles for PORC membership.

Page 260, revise the sentence in section 6.2.B.I.f to read "The Committee membership and its Chairman and Vice Chairman shall be appointed as specified in the Vermont Yankee quality assurance program."

Page 260, correct typographical error in paragraph 6.2.B.2.

Page 261-262, clarify title of" Manager of Operations."

Page 266, change the destination of several routine reports from " Director ofinspection and Enforcement" to " appropriate regional office."

Page 270, correct typographical error in the fourth paragraph and add statement that "the latest NRC approved version will be listed in the COLR" to paragraphs 7 and 8 to allow usage of NRC approved updates to this methodology without requiring TS change submittals be made .

Page 277, clarify title of" Manager of Operations."

Page 278, clarify title and correct footnote to correctly reflect that the FSAR update in not submitted annually, but periodically.

REASON / BASIS FOR CHANGES .

Reference (a) declared the Yankee Atomic Operational Quality Assurance Program, Revision 27 to be the Vermont Operational Quality Assurance Manual, Revision 0. This action has the effect of severing the Vermont Yankee QA program from the Yankee Rowe QA program. This request will capture that change in the VYNPS Technical Specifications.

Reference to General Electric methodology NEDO-31960, will be qualified to state that the latest NRC-approved version will be listed in the Core Operating Limits Report (COLR). This will allow use of approved updates to the methodology without submitting additional Technical Specification changes.

' Additionally, several editorial changes are proposed to correct typographical errors and modifyjob titles as a result of organizational changes. All of the changes are editorial in nature.

VERMONT YANKEE NUCLEAR POWER CORPORATION ATTACilMENT I Page 2 of 2 i

SAFETY CONSIDERATIONS The changes proposed on the attached Technical Specification pages do not impact any plant hardware, FSAR safety analysis or change the function of any equipment. These changes are strictly administrative in nature and approval of these changes will have no effect on plant safety.

ENVIRONMENTAL CONSIDERATIONS The Vermont Yankee Nuclear Power Corporation (VYNPC) has evaluated the proposed changes and has determined that the changes do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amount of any effluent that may be discharged off-site, or (iii) a ,

significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in S I.22(c). Therefore, pursuant to 10CFR51.22(b), an environmental assessment of the proposed change is not required.

l VERMONT YANKEE NUCLEAR POWER CORPORATION

! ATTACllMENT 2 Page1of1 SIGNIFICANT HAZARDS CONSIDERATIONS The standards used to arrive at a determination that a request for amendment involves no significant hazards l considerations are included in 10CFR50.92 of the Commission's rules and regulations. These standards state that the operation of the facility in accordance with the proposed amendment will 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 i

significant reduction in a margin of safety. The discussion below addresses each of these criteria and -I l demonstrates that the proposed amendment does not constitute a significant hazard.

F l 1. Will the proposed channes involve a sinnincant increase in the probability or conscauences of an accident

! oreviousiv evaluated?

The administrative change proposed herein will have no effect on plant hardware, plant design, safety limit setting or plant system operation and therefore do not modify or add any initiating parameters that would significantly increase the probability or consequences of any previously analyzed accident. The proposed amendment changes the reference to the VYNPS QA program and makes other administrative changes, such j as title changes and correction / clarification of errors. Therefore, there is no increase in the probability or consequence of an accident previously evaluated. ,

I l, 2. Will the nronosed chances create the possibility of a new or different kind of accident from any accident previously evaluated?

This change does not affect any equipment nor does it involve any potential initiating events that would create.any new or different kind of accident. The proposed change involves a wording changes in the Technical Specifications identifying the name of the QA program and makes other administrative changes, such as title changes and correction / clarification of errors. Therefore no new or different kind of accident has been introduced.

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3. Will the proposed channes involve a significant reduction in a marcin of safety?

This change does not affect any equipment involved in potential initiating events or safety limits. The proposed change has no significant impact on margin of safety, as it is comprised of only administrative changes.

VERMONT Y ANKEE NUCLEAR POWER CORPORATION Vermont Yankee Nuclear Power Corporation TS Proposed Change No. 202 (BVY 98-63)

ATTACHMENT 3 I

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