ML20113A422

Application for Amend to License DPR-28,consisting of Proposed Change 127,updating Tech Specs to Reflect Changes in 10CFR50,correcting Typos & Revising Offsite Support Organization Chart & Trip Level Settings.Fee Paid

ML20113A422
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/27/1985
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20113A424	List: ML20113A422 ML20113A434
References
FVY-85-31, NUDOCS 8504100350
Download: ML20113A422 (6)

Text

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Propos d Change No. 127 VERMONT YANKEE NUCLEAR POWER CORPORATION

. RD 5, eox ,e9 Ferry Road, Brattleboro, VT 05301 ,, ply yg ENGINEERING OFFICE 16 71 WORCESTER ROAD

• FRAMINGHAM, MASSACHUSETTS 01701

• TELEPHONE 617-872-6100 March 27, 1985 FVY 85-31 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attentica: Office of Nuclear Reactor Regulation Mr. Harold R. Denton, Director

References:

a) License No. DPR-28 (Docket No. 50-271) b) Final Rule,10CFR50.54 (48FR3111), dated 7/11/83 c) Letter, USNRC to VYNPC, I&E Inspection Report No. 50-271/83-17, dated 8/3/83 d) Letter, USNRC to VYNPC, Amendment No. 63 to Facility Operating License No DPR-28, dated 3/2/81 e) Letter, USNRC to VYNPC, Amendment No. 64 to Facility Operating License No. DPR-28, dated 3/11/81 f) Letter, USNRC to VYNPC, I&E Inspection Report No.

50-271/84-10, dated 7/12/84

Subject:

Administrative Update to the Vermont Yankae Technical Specifications Pursuant to Section 50.59 of the Commission's Rules and Regulations, Verment Yankee Nuclear Power Corporation hereby proposes the follewing modifica-tions to Appendix A of the Operating License:

Proposed Change:

The proposed change involves administrative updates to the Vermont Yankee Technical Specifications to: (1) reflect recent changes to 10CFR Part 50; (2) correct for typographical errors; (3) remove certain provisions of Technical Specifications which are no longer applicable; (4) revise our off-site support organization chart to reflect recent organizational changes at the Nuclear Services Division of Yankee Atomic Electric Company; and (5) revise certain trip level settings necessary as a result of the installation of new instrumentation.

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-U.S. Nuclear Regulatory Commission ,

- March 27,1985 -

Paga 2 VERMONT YANKEE NUCLEAR POWER CORPORATION Specifically, the changes include:

Change (1)

The revision of pages 190, 192 and 193 to reflect shift staffing levels for licensed operators consistent with the provisions of 10CFR50.54 [Referer.ce b)]. In addition, these pages have been revised to reflect minor nomenclature changes so as to create consistency in Technical Specification terminology.

Change (2)

-The revision of pages 5b, 41, 49, 51, 176 and 1871 to correct typographical errors.

The change to'page 5b corrects the reference to Note number for Table 3.1.1 from'13 to 12.

The change to page 41 (Table 3.2.2) corrects the acceptable low vacuum set-point from "> 12" Hg absolute to "< 12" Hg absolute. This error was iden-tified in Reference c).

The change to page 49. adds a reference to Note 1 for torus wate.r tem-perature which was inadvertently deleted by the issuance of Amendment No.

63 [ Reference d)] to our Facility Operating License.

The change to page 51 corrects the calibration requirements for the Low Reactor Pressure Trip Functions #2 and #3.

The change to page 176 corrects specification 3.10.B to refer to Specification 3.10.A rather than 3.9.A.

The change to page 1871 corrects Specification 3.13.G.4 to refer to the foam system being " inoperable" rather than " operable".

Change (3)

The revision of pages 5, Sa, 5b, 6, 6a, 19, 21a, 47, 48, 110b, 110c (deleted), 180a, 180b, 180b1 (deleted).and 180-01. These 'pages have been revised to-reflect a deletion of the provision to conduct stability and recirculation pump trip tests at Vermont Yankee. These provisions were intended to be associated with Cycle 8 operation only [see Reference e)].

U.S. Nuclear Regulatory Commission March 27, 1985 VERMONT YANKEE NUCLEAR POWER CORPORATION Page 3 Change (4)

The revision of page 191 (Figure 6.1.1) to reflect a recent organizational change at Yankee Atomic Electric Company, our off-site engineering support organization. The chart has also been revised to depict Radiological Safety as a function of the Environmental Engineering Department.

Change (5)

The revision of page 38 (Table'3.2.1) to reflect a new trip level setting for low Condensate Storage Tank (CST) water level. This change is necessi-tated because the original float type level switches have been replaced by analog instruments which use a differential pressure transmitter with an electronic trip unit. The change also addresses Inspection Follow Item 84-10-02 which is detailed in I&E Inspection Report 50-271/84-10 [ Reference f)].

Reason and Basis for Change:

The reason and basis for change for each revision described above are as follows:

Change (1)

In the aftermath of Three Mile Island (TMI), a number of studies and investigations were conducted by the NRC, the industry and others, recom-mended changes in the numbers, qualifications, and organization of nuclear power plant personnel. NUREG 0660 and NUREG 0737 were issued to provide interim shift staffing criteria to all licensees of operating units, all applicants for operating licenses and all holders of construction permits.

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To ensure that all operating nuclear power reactors are adequately staffed

- with licensed personnel, the NRC promulgated a revision to 10CFR50.54

%[ Reference b)], which applied these NUREG 0737 criteria to all operating nuclisar power reactors effective January 1, 1984.

The changes proposed herein will bring the Vermont Yankee Technical Specifications into compliance with the revised regulations and eliminate possible contradiction between the requirements of Technical Specifications and the provisions of 10CFR50.54. In addition, minor word changes were made to these pages so as to create terminology consistency.

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m U.S. Nuclear R;:gulatery Commission -

. March.27, 1985 VERMONT YANKEE NUCLEAR POWER CORPORATION Page 4 Change-(2).

These changes correct existing Technical Specifications for typographical errors.

Change (3)

These changes correct existing Technical Specifications to delete the pro-visions to conduct stability and recirculation pump trip tests during Cycle 8 operation. By Amendment No. 64 [ Reference e)], the NRC amended our operating license to allow these tests for the purpose of obtaining data for licensing support of Vermont Yankee stability performance, and for qualification of our stability.and operational transient models.

Since conduct of these tests was limited a seven day period during Cycle 8,

.these changes remove provisions of our Technical Specifications which are not applicable to the current cycle of operation.

Change (4)

This change merely reflects a recent organizational change implemented by the Nuclear Services Division of Yankee Atomic Electric Company, our off-site engineering support organization. The change reflects a shift of the plant engineering requirements from Vice President of Operations to Vice President. The former position, in title, has been deleted. This change does not affect the scope of engineering support presently provided by Yankee Atomic Electric Company.

Change (5)

This change reflects the installation of analog instruments in place of float-type level switches that were originally installed. The new trip level setting is necessary to reflect the different zero reference for the analog instruments and is effectively the same trip level setting presently required by Technical Specifications.

Safety Considerations:

The proposed change is administrative in nature and has no safety or environmental significance.

i This change has been reviewed by the Vermont Yankee Nuclear Safety Audit and Review Comittee (NSARC). ,

U.S..Nucl:ar R:gulatory Commission

• March 27, 1985 VERMONT YANKEE NUCLEAR POWER CORPORATION Page S Significant Hazards Considerations:

The Commission has provided guidance concerning the application of the standards for determining whether a "significant hazards" consideration exists by certain examples (see 48FR14870). The examples of actions involving no significant hazards include: (i) a change to make a license conform to changes and regulations, where the change results in a very minor change to facility operations clearly in keeping with the regulations; and (ii) a purely administra-tive change to Technical Specifications; for example, a change to achieve con-sistency throughout the Technical Specifications, correction of an error, or a change in nomenclature.

Based on the above, we have concluded that Change 1) does not constitute a significant hazards consideration, as defined in 50.92(c), since it merely updates our Technical Specifications to agree with recently promulgated changes to 10CFR Part 50, consistent with Example (1).

We have concluded that Changes 2), 3) and 4) do not constitute signifi-cant hazards considerations, as defined in 10CFR50.92(c), since they are purely administrative changes to correct for errors and assure consistency throughout the Technical Specifications, consistent with Example (ii).

We have' concluded that Change 5) does not constitute a significant hazards consideration, as defined in 10CFR50.92(c). Because a new trip level setting is in essence equivalent to the existing setting, this change is a correction to Technical Specifications, consistent with the intent of Example (ii).

Fee Determination:

In accordance with the provisions of 10CFR170.12, we are enclosing an application fee of $150.00.

Schedule of_ Change:

The proposed change will be incorporated into the Vermont Yankee Technical Specifications as soon as practicable upon receipt of your approval. It should be noted that although our existing Technical Specifications are not consistent l

with the provisions of 10CFR50.54, " Shift Staffing Criteria," we presently meet the requirements of this regulation.

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U.S. Nuclear R:gulatory Commission

• March 27, 1985 VERMONT YANKEE NUCLEAR POWER CORPORATION Page 6 We trust that the information provided is sufficient for your review and subseqiient issuance of a license amendment; however, should you have any questions regarding these changes, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

- gu Warren P. Murphy Vice President and Manager of Operations Enclosure WPM /dm cc: U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk (40 copies)

Vermont Department of Public Services 120 State Street Montpelier, VT 05602 Attn: Mr. Gerald Tarrant STATE OF VERMONT)

)ss WINDHAM COUNTY )

Then personally appeared before me, Warren P. Murphy, who, being duly sworn, did state that he is Vice President and Manager of 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 knowledgeand;bpl,jgp g '

j Diane M. McCue '

Notary Public MyCommissionExpires/ebruary F 10, 1987 f gg i l S

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