NRC-90-0182, Application for Amend to License NPF-43,modifying Valve Numbers in Tech Spec Table 3.6.3-1, Primary Containment Isolation Valves, for Two remote-manual Containment Isolation Valves

Application for Amend to License NPF-43,modifying Valve Numbers in Tech Spec Table 3.6.3-1, Primary Containment Isolation Valves, for Two remote-manual Containment Isolation Valves

ML20070B462
Person / Time
Site:	Fermi
Issue date:	01/28/1991
From:	Orser W DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070B464	List: ML20070B467 NRC-90-0182, Application for Amend to License NPF-43,modifying Valve Numbers in Tech Spec Table 3.6.3-1, Primary Containment Isolation Valves, for Two remote-manual Containment Isolation Valves
References
CON-NRC-90-0182, CON-NRC-90-182 NUDOCS 9101310148
Download: ML20070B462 (5)

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Janua ry 28, 1991 NRC-90-0182 U. S. Nuclear Regulatory Ccamission Attnt Document Control Deck Washingt on, D. C. 20$$5

Reference:

Fermi 2 NRC Docket No. 50-341 NRC Licence No. NPF-43

Subject:

Proposed Technical Specification Change (Licence Amendment) - Primary Containment Isolation Valves (3/4.6.3) _

1 Pursuant to 10CFR50.90, Detroit Edison Company hereby proposen to amend Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specificationc. The propoced change modifies valve numbers in Technical Specification j Table 3.6.3-1 Primary Containment Isolation Valves, f or two l remote-nanual cont ainment isolation valves. The valve numbers will be changed as part of the Contiol Room human engineering improvetaents scheduled for Fermi 2's second refueling outage, which io currently scheduled to begin in March 1991.

Detroit Edison has evaluated the proposed Technical Specifications i against the criteria of 10CFR$0.92 and determined that no significant hazards consideration in involved. The Fermi 2 Onsite Review Organization has approved and the Nucicar Safety Review Group hac reviewed the proposed Technical Specifications and concurs with the enclosed determinations. In accordance with 10CFR50.91, Detroit i Edison has provided a copy of thic letter to the State of Michigan.

7 If you have any questions, please contact Mr. Glen D. Ohlemacher at gg (313) 586-4275.

.co o (pM Sincerely 00 4 '

0~ 0 co x Q00 Enclosure

[ cc: A. B. Davis gg R. W. DeFayette

-a W. G. Rogers N J. F. St ang h Supervisor, Electric Operators, Michigan Public Service Ccemission - J. R. Padgett (

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. USHRC January 28. 1991 1;RC-90-0182 ,

Page 2 l l

I. WILLI AM S. ORSER, do hc reby af firm that the f oregoing statements ate baned on facts and circumstances which are true and accurate to the best of my knowledge and belief.

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• WILLI AM S. ORSER Senior Vice President On this eM day of ut eta 4f- .

1991, before me personally appeared William S. J'frser, be(Jig first duly sworn and says that he executed the foregoing (au his f ree act and deed.

fil tltllt e h.bTTST&)

Notary Public (10*/ US A Am,10.3 Notc7y Pub!5, Mr.ws ccunty. Mi f4Comm!ssion Exp!rosJon.it.1992

. Enclosure to

. NRC-90-0182 Page 1 INTRODUCTION Technical Specification (TS) Table 3.6.3-1. Primary Containment Isolation Valves, contains a listing of isolation valves which includes the valve function and the valve number. The purpore of this proposal is to change this TS Table consistent with a planned change in valve number for two isolation valves. The two af f ected valves aret the Division I Emergency Equipment Cooling Water (EECW) Supply to Drywell Equipment Isolation Valve, which will be renumbered f rom P44-F607A to P44-F606A; and the Division I EECW Return f rom Drywell Equipment Isolation Valve, which will be renumbered from P44-F606A to F44-F607A. These two valves appear as remote-manual containment isolation valves in items B.24 and B.25, respectively, of Table 3.6.3-1.

The renumbering of these valvec is planned in conjunction with the resolution of Human Engineering Discrepancy (HED) 1150, which resulted from the Fermi 2 Detailed Control Room Design Review. HED 1150 deals with improving the layout of EECW ant. Reactor Building Closed Cooling Water (RBCCW) controls in the Control Room. The new layout will be more logical in arrangement and consistent between the two divisions, which are on dif ferent Control Room panels.

In reviewing the controls layout, it was determined that an inconsistency cainto between divisions in the uce of valve numbers.

Typically, valves with the same number except for the final letter perform the same function in dif ferent divisions. In the case of these two valves this general rule was not followed. It was determined to be beneficial to change the valve numbering to conf orm to the general practice. This proposal makes this numbering change in the TS.

The proposed TS page change is attached. The new controls layout, and the associated change in valve numbers, is scheduled to be implemented during Fermi 2's second refueling outage. Approval of this proposal is necessary for the subsequent plant startup, currently scheduled for June, 1991.

EVALUATION The proposal is strictly limited to the administrative detail of valve numbering. The functions of each valve, including the containment isolation function, are not af fected and the change has no physical effect except for plant labelling. As discussed above, the renumbering enhances the Control Room design by implementing a human engineering improvement which will improve the man / machine interface

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Enclosurt to l (C-90-0182 l

'e 2 by eliminating t he valve nut bering inconclut ency. Therefore, the change is accept able.

SIGNIF1CAltr HAZARDS CONSIDEPATION In accordance with 10CrR50.92 Detroit Edicen han inade e detertrination that the proposed amendment involves no significant hatatue considerations. To make thic determination, Detroit Edison must establiah that operation in accordatice with the propored ernendment would not: 1) involve a significant increar:e in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or dif ferent kind of accident f rotu any accident previously evaluated, or 3) involve a cignificant r eduction in a tuargin of cafety.

The proposed change modifiec the valve numbero listed in Technical Specification Table 3.6.3-1, Primary Containment loolation Valyco, ascociated with two primary conte.itirnent isolation valveo. The two valves are manually operated from the Fermi 2 Control Room and are located in the Emergency Equipment Cooling Water supply and return to drywell equipinent. The valves are being renumbered to enhance the Control Room design by making the valve numbering consistent between divisions. The change is strictly administrative end does not af fect any of the f unctionn of the two valves, including t he containmerit isolation function. Therefore, the prranermd change does not:

1) Involve a significant 1,.c ace in tha orobability or consequenceu of an accident previoCly evaluatec .

2) Create the possibility of a new or dif ferent kind of accident from any accident previously evaluated.

3) Involve a significant reduction in a margin of safety.

The Commission has provided a listing of examples of licensee amendments that are not likely to involve significant hazards considerations in 51 FR 7751. This change is like example (i) of thin listing in that it is a purely administrative change to Technical Specifications made to make a change in nomenclature.

Based on the above. Detroit Edison han determined that the proposed amendment does not involve a significant hazards consideration.

ENVIRONMEEAh_ IMPACT Det roit Edison has reviewed the proposed Technical Specification changes against the criteria of 10CFR51.22 for environmental i

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. Enclosure to HRC-90-0182 Page 3 concide r a ti ons. The proposed change does not involve a significant hazards consideration, nor significantly change the types or significantly increase the amounts of effluents that may be released of fsite, nor significantly increase individual or cumulative 2

occupational radiation exposures. Based on the f oregoing. Detroit Edison concludes that the proposed Technical Specifications do nieet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion f rom the requirements for en Environmental Impact Statement.

CONCLUS!b'1 Based on the evaluation abover 1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and 2) such activities will be conducted in compliance with the Commission's regulations. and the proposed amendment will not be inimical to the common defense and socurity or to the health and safety of the public.

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