BECO-84-044, Application to Amend License DPR-35,consisting of Proposed Change 84-01,changing Tech Specs to Remove Details of Section XI Inservice Insp Program

Application to Amend License DPR-35,consisting of Proposed Change 84-01,changing Tech Specs to Remove Details of Section XI Inservice Insp Program

ML20087L147
Person / Time
Site:	Pilgrim
Issue date:	03/20/1984
From:	Harrington W BOSTON EDISON CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20087L149	List: BECO-84-044, Application to Amend License DPR-35,consisting of Proposed Change 84-01,changing Tech Specs to Remove Details of Section XI Inservice Insp Program ML20087L329
References
BECO-84-044, BECO-84-44, NUDOCS 8403270055
Download: ML20087L147 (4)

Text

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n a a..a 50BTON EDISON COMPANY B00 BOYLSTON BTREET BOSTON, MAssACHUGETTs 02199 WILLIAM D. HARRINGTON

...... .. ....... , March 20, 1984 ar== BECo 84-044 Proposed Change 84-01 l

Mr. D. B. Vassallo, Chief Operating Reactors Branch #2 .

Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 License No. DPR-35 l Docket No. 50-293 Pilarim Station Propose 6 Technical Specification Chance

Dear Sir:

Pursuant to 10 CFR 50.90, Boston Edison Company hereby proposes the modifications to Facility Operating License No. DPR-35 as described in Attachment A to this letter. In accordance with 10 CFR 170.22 a check in the amount of $4,000 is enclosed with this submittal.

Should you have any questions concerning this submittal, please do not hesitate to contact us.

Very truly yours, TFF/kmc C Attachment

-3 signed originals and 37 copies Commonwealth of Massachusetts)

County of Suffolk )

Then-personally appeared before me W. D. Harrington, who, being duly sworn, did state that he is Senior Vice President - Nuclear of the Boston Edison Company, the applicant herein, and that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of the Boston Edison' Company and that the statements in said submittal are true to the best of his knowledge and belief.

My Commission expires:dJ/;/f68 OA/k

]- NotarfPublic 0

cc: - Mr. Robert M. Hallisey, Director  !

L Radiation Control Program L Massachusetts Dept. of Public Health h '

600 Washington Street, Room 770 Boston, MA- 02111 g@g 1 8403270055 840320 PDR ADOCK 05000293-

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I Attachment Proposed Technical Specification Change Proposed Change This proposed Technical Specification change removes the details of the Section XI Inservice Inspection (ISI) Program. The requirement to implement the ISI Program at the required intervals will not be removed. The details of

.the ISI Program will be administratively handled as a controlled document.

Snubber inspection requirements are left in the Technical Specifications but the table listing snubbers on Code Class 1, 2, and 3 systems will be removed and become part of the controlled ISI Program document.

Reference -is made to the following Pilgrim Nuclear Power Station Technical Specification Sections, Tables, and Bases:

Section 3.6.G " Structural Integrity" Section 4.6.G " Structural Integrity" Section 4.6.H "High Energy Piping (Outside Containment)"

Tablo 4.6.1 " Inservice Inspection Requ" ments for Pilgrim Station Nuclear Power Station" Section 3.6.I " Shock Suppressors (Snubbers)"

Section 4.6.I " Shock Suppressors (Snubbers)"

Table 3.6.I(a) " Safety Related Hydraulic Shock Suppressors (Snubbers)"

Bases 3.6.G & 4.6.G " Structural Integrity"

-Bases 3.6.I & 4.6.I " Shock Suppressors (Snubbers)"

Section 3.6.G The reference to the ASME Boiler and Pressure Vessel Code has been changed from the 1974 Edition to the 1980 Edition, Winter 1980 Addenda. The remainder of this section has been deleted.

Section 4.6.G The reference to " Table 4.6.I" has been replaced with " Pilgrim Station Inservice Inspection Program". Conforming changes have been made to reflect the ten year interval requirements.

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Section 4.6.H The reference to the ASME Boiler and Pressure Vessel Code has been changedEfrom the 1974 Edition to the 1980 Edition, Winter 1980 Addenda.

Table 4.6.1 This table has been deleted.

Section~3.6.I The reference to:" Table 3.6.I(a)" has been replaced with

" Pilgrim Station Inservice Inspection Program".

, Section 4.6.I The reference to " Table 3.6.I(a)" has been replaced with

" Pilgrim Station Inservice Inspection Program".

Table 3.6.I(a) This table has been deleted.

Bases'3.6.G & Refer to marked up pages for extent of changes.

4.6.G Bases 3.6.I & Refer to marked up pages for extent of changes.

4.6.I Reason-for Change i3 This proposed Technical Specification will allow ISI' changes to Code Class systems without a subsequent Technical Specification Change, but does not remove the comr.itment to-perform ISI per Section XI nor does it remove the commitment to test Code Class Snubbers at the. required intervals. The details of the.ISI Program will be kept as a controlled document so Section XI

- modifications, repairs, or ' replacements can be accurately captured in the program.

This approach is similar to the BWR Generic Technical Specifications in the area of ISI on Code Class 1, 2, and 3 components. The Generic Technical Specifications do not require a detailed table outlining the entire ISI program by system, weld, pump, etc.

Safety Considerations This change does not present an unreviewed safety question as defined in 10 CFR-50.59. It has been reviewed and approved by the Operations Review Committee and_ reviewed by the Nuclear Safety Review and Audit Committee.

Sionificant Hazards Considerations It has been determined that this amendment request involves no significant hazards consideration. Under the NRC's regulations in 10 CFR 50.92, this means that operation of the Pilgrim Nuclear Power Station in accordance with

.the proposed amendment would not.(1) involve a significant increase in the probability or consequences of an accident 'previously evaluated; or (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.

. V The NRC has provided guidance concerning the application of standards for

. determining whether license amendments involve significant hazards considerations by providing certain examples (48 FR 14870). One example of an amendment that is considered not likely to involve a significant hazards consideration is "...(vii) A change to make a license conform to changes in the regulations, where the . license change results in very minor changes to facility operations clearly in keeping with the regulations."

Changes to the ASNE Boiler.and Pressure Vessel Code, which is incorporated by reference in 10 CFR 50.55a, have necessitated changes to the Pilgrim Station

- Inservice Inspection Program, as implemented in the Pilgrim Station Technical

~ Specifications. Therefore this proposed Technical -Specification will conform to reflect these changes. Facility operations will not be impacted because

- the ISI requirements will still be satisfied. The methodology for implementation of'the ISI requirements is satisfactory in that it conforms with the BWR Generic Technical Specifications.

Schedule of Chance.

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- This change will be put into effect in 30 days upon receipt of approval from NRC.

Fee Determination Pursuant to 10 CFR 170.22 Boston Edison Company proposes this change as Class III. The sum of $4,000 is submitted and should be applied toward this proposed change and for the related review of our proposed Second Ten Year Inservice Inspection Program.

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