BECO-87-118, Application for Amend to License DPR-35,consisting of Proposed Change 87-13,revising Tech Spec Table 4.2.A Re Change in Min Test & Calibr Frequency for Reactor High Pressure Instrument Channel to Once Every 3 Months.Fee Paid

Application for Amend to License DPR-35,consisting of Proposed Change 87-13,revising Tech Spec Table 4.2.A Re Change in Min Test & Calibr Frequency for Reactor High Pressure Instrument Channel to Once Every 3 Months.Fee Paid

ML20236K537
Person / Time
Site:	Pilgrim
Issue date:	07/28/1987
From:	Bird R BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236K540	List: BECO-87-118, Application for Amend to License DPR-35,consisting of Proposed Change 87-13,revising Tech Spec Table 4.2.A Re Change in Min Test & Calibr Frequency for Reactor High Pressure Instrument Channel to Once Every 3 Months.Fee Paid ML20236K549
References
BECO-87-118, NUDOCS 8708070154
Download: ML20236K537 (4)

Text

f 10CFR50.90

y. g y Executive Offices 800 Boylston Street Boston, Massachusetts 07199 Ralph G. Bird Senior Vice President - Nuclear 4

July 28, 1987 '

1 U.S. Nuclear Regulatory Commission BECo 87-118 i Document Control Desk Proposed Change 8713 )

Hashington, DC 20555 License DPR-35 j Docket 50-293

)

Proposed Technica1' Specification Change to Table 4.2. A:

Minimum Test and Calibration Frecuency for_theJeactor Hioh Pressure Instrument 1hannel in the PCIS 1

Dear Sir:

l Pursuant to 10CFR50.90, Boston Edison Company (BECo) requests NRC review and j

approval for Appendix a proposed A, Table 4.2.A.change to Facility Operating License No. DPR-35, 1 The requested change is described in Attachment A, '

and the' revised Technical Specification page is contained in Attachment B.

The _10CFR170.12(c) required $150.00 application fee will be electronically transferred to the NRC.

)

l.

.G.'tnM l TFF/jcp l Attachments 1 signed original and 37 copies cc: See next page Commonwealth of Massachusetts) \

County of Suffolk - )

Then personally appeared before me, Ralph G. Bird, who, being duly sworn, 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 behalf of. Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.

My commission expires: // U >&dd .

(

/ P6TE '7 NO PUBLIC (

8708070154'870728 f PDR gp P ADOCK 05000293 v PDR

BOSTON EDISON COMPANY

," U.S. Nuclear. Regulatory Commission Page 2

.l cc: U. S. Nuclear Regulatory Commission Region I >

631 Park Avenue King of Prussia, PA 19406 R. H. Nessman, Project Manager Division of. Reactor Projects I/II Office of Nuclear Reactor Regulation U.-S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda,- MD 20814 Senior NRC Resident Inspector Pilgrim Nuclear Power Station Mr. Robert M. Hallisey, Director

. Radiation Control Program Massachusetts Dept. of Health 150 Tremont Street F-7 Boston, MA 02111 i

l l

1 1

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Attachment A Procosed Change This revision to Technical Specification Table 4.2.A changes the calibration frequency for Reactor High Pressure to what it was before Amendment No. 99 was granted by the NRC.

The proposed change returns the Calibration Frequency to "Once/3 months",

returns the Instrument Check Frequency to "None", and removes the reference to note (7) in the Instrument Functional Test column.

Reason for Chanae The installation of an Analog Trip System (ATS) at Pilgrim Station (PNPS) required a change to Technical Specifications. The change was granted by the NRC as Mendment No. 99, which became effective on April 2,1987. Incorrectly incluied in both the proposal and Amendment No. 99 was a change to the surveillance frequency of the Reactor High Pressure instrument channel for PCIS. This instrument channel was not part of the ATS modification, and its ,

Technical 59 edification surveillance requirements should not have been changed. l He submit this request to correct the error. Safety was not compromised because plant conditions which require Reactor High Pressure instrumentation have not existed since the issuance of Amendment No. 99.

Safety Evaluation and Determination of No Significant Hazards Considerations This amendment involves an administrative change to PNPS Technical Specifications. It corrects a previous error intraduced in Amendment No. 99.

The Crde of Federal Regulations, 10CFR50.91 requires that at the time a licensee requests an amendment, it must provide to the Commission its analysis, using the standards in 10CFR50.92, about the issue of no significant hazards consideration. Therfore, in accordance with 10CFR50.91 and 10CFR50.92 the following analysis has been performed.

1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. l l

The proposed change returns the minimum test and calibration freauency for the Reactor High Pressure instrument channel in the PCIS to tne frequency specified before Technical Specification Amendment No. 99 was l issued. Since the change made to Reactor High Pressure by Amendment No. I 99 should not have been made, this change returns the surveillance frequency requirements to values that have been previously ev:luated and accepted. Therefore this change will not increase the probability or consequences of an accident. I l

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

Since this proposed change will correct a past change to the Technical Specifications by reestablishing the original requirements, there is no possibility of creating a new or different kind of accident from any accident previously evaluated. J

-3. The proposed amendment will not involve a significant reduction in a 1 margin of safety. l l

The margin of safety for this instrument channel will be unchanged since I the minimum test and calibration frequency will be restored to the original frequency.

As shown above, this proposed Technical Specification has no significant hazards considerations.

This change has been reviewed and approved by the PNPS Operations Review Committee, and reviewed by the Nuclear Safety Review and Audit Committee. ,

Schedule ot' Change This change will be put into effect within 30 days of receipt of approval by the NRC.

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