BECO-LTR-84-102, Application for Amend to License DPR-35,changing Tech Specs to Delete Condition 3.D. Equalizer Valve Restriction. Fee Encl

Application for Amend to License DPR-35,changing Tech Specs to Delete Condition 3.D. Equalizer Valve Restriction. Fee Encl

ML20093D584
Person / Time
Site:	Pilgrim
Issue date:	07/12/1984
From:	Harrington W BOSTON EDISON CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20093D586	List: BECO-LTR-84-102, Application for Amend to License DPR-35,changing Tech Specs to Delete Condition 3.D. Equalizer Valve Restriction. Fee Encl ML20093D596
References
BECO-LTR-84-102, NUDOCS 8407170076
Download: ML20093D584 (3)

Text

,.a s EOSTON EDISON COMPANY l 000 SovLaTON STmst? I

, BQsTON. M AssAcHustTTs 02199 l WILLIAM O. HANNINGTO N

',/',,",*"""'"" BEco Letter No.84-102 July 12, 1984 s e4

'ir. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission Washington, D.C. 20555 h& License No. DPR-35 Docket No. 50-293 3' Proposed Amendraent to Facility Operating Licensel E3 ualizer Valve Restriction

' ". b Dear Sir; IU pursuant to 10 CFR 50.90, Boston Edison Company (BECo) hereby proposes the i following amendment to facility Operating License No. DPR-35.

ga proposed Change This change deletes Condition 3.0, " Equalizer Valve Restriction", in its entirety. Condition 3.0 currently reads "The valves in the equalizer piping

-? between the recirculation loops shall be closed at all times during reactor i operation". See the Attachment to this letter for revised Facility Operating

( License page 3.

Reason For Change k ,

As a result of NRC Order titled "IGSCC Inspection Order Confirming Shut-down" dated August 26, 1983, BEco initiated the Recirculation System Piping Replacement Project. This 3roject includes the removal of the 22" equalizer valves located between t1e recirculation loops. The replacement

% piping design specifies that the piping on both sides of the removed valves is to be capped. Therefore, the present license condition that the equalizer valves remain closed at all times is moot.

Safety Considerations This change does not present an unroviewed safety question as defined in 10 CFR 50.59. It has been reviewed and approved by the Operations Review Conmittee and reviewed by the Nucicar Safety koview and Audit Committee.

0407170076 040712 gon noon o3o002,3 h, t von ' ($

q g spp$

enerow toisaw comwr July 12. L984 Mr. Domenac B. Vassallo, Chief Page 2 Significant 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 theproposedamendmentwouldnot(1)involveasignificantincreaseinthe 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.

The NRC has provided guidance concernino the opplication of stardards 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 "...(i) a purely administrative change to technical speci-fications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."

Removal of the 22" equalizer valves and subsequent capaing of the lines does not impact existing safety analyses. The pur)ose of t1e equalizing line was to interconnect the pump discharge lines so t1at one recirculation pump could deliver flow to the discharge lines if the other recirculation aump was shut-down. The present license condition prevents either valve in tie equalizer l line from being open during reactor operation. If these valves were open  !

while a design basis LOCA were to occur LpCI flow from both RHR loo)s would be prevented from reaching the core at design quantities due to disciarge '

out of the break through the equalizing valves. The removal of these valves l and the capping of the lines therefore does not constitute an unreviewed l safety question. Since the equalizing valves will not exist in the replace-ment design, the license condition restriction on valve operation is no l longer needed. This amendment request is an administrative change in that i it deletes obsolete conditions from the facility operating license.  ;

l Schedule of Change l This change will be out into effect upon receipt of npproval from the NRC.

i Applica_ tion Fee Pursuant to 10 CFR 110.21 an application fee of $150 is submitted with this amendment request.

Very truly yours, TFF:pjd md Attachment 3 signed originals and 37 copies l

CE,T O N EDCON COM PANY July 12, 1984 I l Mr. Domenic B. Vassallo, Chief

( Page 3 i

Commonwealth of Massachusetts l County of Suffolk f

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

My Commission expires:p g pg jfLM r

' / .' v't.C..b. C ,

cc: Mr. Robert M. Hallisey, Director [ t.? *'

1?f h' i )[e Radiation Control Program Massachusetts Dept. of Public Health b -

j i$:ff

- s 600 Washington Street, Room 770 ' ' - '-

Boston, MA 02111 '.*. *; "

's %. . ~-

4 1

A

-l

• .' g , 3

, < -