ML20249C708

Application for Amend to License DPR-35,correcting Typos & Updating Bases.Changes Are Considered Administrative

ML20249C708
Person / Time
Site:	Pilgrim
Issue date:	06/26/1998
From:	Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20249C709	List: ML20249C708 ML20249C710
References
BECO-2.98.028, NUDOCS 9807010071
Download: ML20249C708 (4)

Text

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k h 10CFR50.90 Boston Edhnon Pilgrirn Nuclear Power Station 600 Rocky Hd; Road 4 , Plyrnouth, Massachusetts 02360 LJ. Olivier Senior Voe President Nuclear June 26, 1998 BECo Ltr. #2.98.028 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 -

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Docket No. 50-293 l.icense No. DPR-35 l

Proposed Administra'ive Technical Specification Chanoes in accordance with the requirements of 10CFR50.90, Boston Edison Company proposes several administrative changes to the Pilgrim Station Technical Specifications.

The description of the proposed changes is included in Attachw. t A. Attachment B contains the amended Technical Specification pages. Attachment C cc'.tcins a marked-up copy of the /[/

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existing Technical Specification pages.

Should you have any questions, please contact M. Lenhart at 508-830-7937 in our Regulatory Affairs Department.

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J. Olivier

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Commonwealth of Massachusetts)

County of Plymouth )

Then personally appeared before me, L. J. Olivier, who being duly swom, did state that he is Senior Vice President - Nuclear of Boston Edison Company and that he is duly authorized to execute and file the submittal contained herein in the name and on "ehalf of Boston Edison )

Company and that the statements in said submittal are true to the best of his knowledge and belief. -

l My commission expires: A L /w_; M M.2_ -

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• I y 'l-BOSTON EDISON COMPANY Proposed Technical Specification Changes Page 2

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Attachment A: Description of Proposed Changes Attachment B: Amended Technical Specification Pages Attachment C: Marked-up Technical Specification Pages cc: Mr. Alan B. Wang, Project Manager Mr. Peter LaPorte, Director Project Directorate I-3 Massachusetts Emergency Mangment Office of Nuclear Reactor Regulation Office of Emergency Preparedness Mail Stop: OWFN 14B2 400 Worcester Road U. S. Nuc!aar Regulatory Commission P.O. Box 1495 1 White Flint North Frarningham, MA 01701-0317 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Mr. Jim Muckerheide Region'l 400 Worcester Road 475 Allendale Road P.O Box 1496 King of Prussia, PA 19406 Framingham, MA 01701-0317 Senior Resident inspector Pilgrim Nuclear Power Station Mr. Robert Hallisey, Director

' Radiation Control Program Massachusetts Department of Public Health 305 South Street Jamaica Plain, MA 02130 i

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BOSTON EDISON COMPANY Proposed Administrative Technical Specification Changes Attachment A Description of Proposed Chanaes Proposed Chanaes and Reason for Chanae:

i Table 3.1.1 was corrected. For the item " Turbine Control Valve Fast Closure", a typographical  ;

error of "psit" was introduced in Amendment 169. It has been corrected to read "psig". j

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Table 3.2.C.1 is modified for the " Mode Switch in Shutdown" item. This resolves a typographical error that occurred when it was added in Amendment 169. This item was incorrectly added to both pages of the table instead of only on one page. Because there are  ;

two channels per trip function, the "one and one"is deleted on page 3/4.2-20. 1

• Section 3.3.B.3.b.1 has been changed to read "when the reactor is critical and below 20%...". l This change was approved by the NRC in Amendment 39 but was inadvertently not revised in l our current copy of Technical Specifications. I e Bases Section 3/4.7.A has been revised per Boston Edison Safety Evaluation 2983. This Safety Evaluation was written to evaluate the results of a design verification for safety-related cooling systems using the FSAR site maximum salt service water temperature of 75 F. The CSAR was previously updated in Revision 19 to include this information. This safety evaluation was also reviewed by the NRC under license Amendment 173.

. Bases Section 3/4.7.A has been revised to correct an error that occurred in Amendment 172.

Revision 172 inadvertently deleted information inserted into the Bases for the containment testing program in accordance with 10CFR50, Appendix J, Option B that was added in Amendment 167. In this section we are also deleting "high radiation" from the Group I definition in page B3/4.7-5. This change was approved in Amendment 172.

. Also, the inadvertent replication of Group 1,2 and 3 isolation signals is deleted from page B 3/4.7-4 because identical information is provided on page B 3/4.7-5.

Discussion:

These changes are proposed to correct typographical errors and update the Bases. These changes are considered administrative. These changes will make the Technical Specifications consistent with information already reviewed and approved by the NRC in previous license amendments.

Schedule of Chanoe:

L l These changes will b9come effective 30 days following Boston Edison's receipt of the I Commission's approval. ,

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BOSTON EDISON COMPANY l

Proposed Administrative Technical Specification Changes Attachment A Desc~iption of Proposed Chancos Determination of No Significant Hazards Considerations:

The Code of Federal Regulations (10CFR50.91) requires licensees requesting an amendment to provide an analysis, using the standards in 10CFR50.92, that determines whether a significant hazards consideration exists. The following analysis is provided in accordance with 10CFR50.91 and 10CFR50.92 for the proposed amendment.

1. The proposed arnendment dues not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed administrative changes involving typographical errors and updating the Bases reflect plant design, safety limit settings, and plant system operation previously reviewed and approved by the NRC. These changes, therefore, do not modify or add any initiating parameters that would significantly increase the probability or consequences of any previously analyzed accident.

2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

These proposed changes do not involve any potential initiating events that would create a i new or different kind of accident. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

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3. The proposed amendment does not involve a significant reduction in a margin of safety.

l These changes reflect information previously reviewed and approved by the NRC. The {

proposed changes will make the information in the Technical Specifications consistent with j that already approved by the NRC. Therefore, it is concluded that the proposed '

amendment does not involve a significant reduction in a margin of safety.

The proposed changes have been reviewed and recommended for approval by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.

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