B13940, Application for Amend to License NPF-49,changing TS Figure 3.1-2 to Accurately Reflect Correct Graph Location for Shutdown Margin,Esfas Instrumentation,Containment Sys & Control Room Emergency Ventilation

Application for Amend to License NPF-49,changing TS Figure 3.1-2 to Accurately Reflect Correct Graph Location for Shutdown Margin,Esfas Instrumentation,Containment Sys & Control Room Emergency Ventilation

ML20086M355
Person / Time
Site:	Millstone
Issue date:	12/11/1991
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086M359	List: B13940, Application for Amend to License NPF-49,changing TS Figure 3.1-2 to Accurately Reflect Correct Graph Location for Shutdown Margin,Esfas Instrumentation,Containment Sys & Control Room Emergency Ventilation ML20086M360
References
B13940, NUDOCS 9112170373
Download: ML20086M355 (4)

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NORTHEAST UTILITIES o.nmi Omca . s,ioen sir.ei. n.<nn conn.ci cui 1 U,$~C[dINOY2 P O DOX270

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L t a '"0 07 0 5 : R03N" December 11, 1991 Docket No. 5Q.R1 B13940 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Oesk Washington, DC 20555 Gentlemen: -

H111 stone Nuclear Power Station, Unit No. 3 Proposed Revision-to Technical-Specifications Shutdown Margin, ESFAS-Instrumentation, Containment Systems and Control Room Emeraency Yg.ntilation Pursuant to 10CFR50.00, Northeast Nuclear Energy Company (NNECO) hereby pro-poses to amend Operating L.icense NPF-49 by incorporating the changes identi-fied in- Attachment 1 into the Technical Specifications of- Millstone Unit  !

No. 3. ,

Description of Procosed Chanaes Figure 3.1-2 is being redrawn to accurately reflect the correct graph loca-tions. ;For Amendment 60, Figure 3.1-2 was -added to: specify : shutdown margin requirements for Mode 3 with three loops in operation. Upon receiving Amend-cent _60, it was discovered that, although the data points (actual value) were -

correct, the graph .did not accurately reflect. those data points (x-y coordi-nates). Therefore, a revised Figure 3.1-2-is being provided. ,

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- Table 3.3-4, Item 4d, is being- revised to be consistent with item le, steam line> pressure--low. Item le was' revised by Amendment 60; however, Item 4d was inadvertentif omitted. This change will make the two. items consistent for "Z" and " allowable value."

. Section 3/4.6.3 is being revised to delete a reference to Table 3.6-2.

Table 3.6-2 was deleted by Amendment 28; however, Section- 4.6.3.3 still con-tains a reference to the table. This proposed change will delete that refer-ence.

Section 3/4.7.7 is -being revised to clarify the wording of the Mode 5 and 6 action statement to enhance the operators understanding of required actions to be initiated during a plant condition in which (1) one control room emergency 9112170373 911211 n PDR 4 DOCK 05000423 Qv P PDR -t l( 'g \

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-U.S. Nuclear Regulatory Commission B13940/Page 2 December ll, 1991.

i air filtration system (CREAFS) is inoperable and (2) the operable CREAFS is not powered by the _ operable emergency _ power - source to ensure Millstone Unit

-No. 3 is placed in a limiting condition for operation requiring suspension of.

all operations involving core alterations or. positive reactivity changes.

-The design basis _ for the CREAFS is to maintain control' room environment for 30 days conundous occupancy _ without exceeding S rem whole-body dose per 10CFR50, Appendix A GDC 19. CREAFS operability in Modes 1 and -2 ensures .

control. room habitability during - and following a design basis _ accident.

-CREAFS operability in ' Modes--3, 4, 5, and 6 is to cope with a hypothetical release outside containment,.particularly in the case of multiunit sites where CREAFS must be' operable at all times.

NRC. Inspection Report 50-336/8905(I)identifiedasituationinvolvingcontrol room ventilation _ system operation. As a result of that inspection report, NNEC0 'has' reviewed the -Millstone Unit No -3 Technical Specifications -tc determine if any improvements to the Technical Specifications. are required.

Based -upon that. review and a to ' avoid any- potential noncompliance, NNECO is proposing- this technical specification -change to clarify the action ' require-ments in Modes 5 and 6 for operation of the control room emergency air filtra-

tion systems. Under the proposed change, any system failure which renders one or both CREAFS inoperable will invoke the - LCO in an- identical manner as the' existing 3/4~.7.7. The proposed change simply clarifies. the existing require-ment.

Sionification Hazards Consideration

'NNECO has reviewed the proposed changes in accordance with 10CFR50.90, and'has

- concluded that the- changes do-not involve a significant hazards consideration.

The basist for this conclusion is that the'three criteria of 10CFR50.92(c)-are not compromis6d. The L proposed changes do not . involve a significant hazards consideration because~the changes would not:

1. - Involve a significant increase in the probability or consequences of an

accident previously analyzed.

The proposed changes to Figure 3.1-2, Table 3.3-4, and Section 3/4.6.3 are intended to clarify -the Technical Specifications and ensure consis-tency.- The changes do not increase in.the probability or consequences of an accident previously analyzed.

The proposed changes.to Section 3/4.'7.7 simply provide clarification and increased understanding- of the existing Technical Specifications. and (1) J. P. Durr letter to .E. J. Mroczka, " Millstone 2 Resident

. Inspection 50-336/89-05 (2/11/89-3/23/89)," dated May 4, 1989. .

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U.S. huclear Regulatory Commission B13940/Page 3 December 11, 1991 therefore do not increase the probatility or consequences of an accident previously analyzed.

2.. Create the possibility of a new or different kind of accident from any previously analyzed.

The proposed changes to figure 3.1-2, Table 3.3-4, and Section 3/4.6.3 are to parameters included in existing design basis accidents. All affected plant systems will continue to function as designed.

The proposed changes do not affect any plant operations, the potential for an unanalyzed accident is not created, and no new failure modes are introduced.

The proposed changes to Section 3/4.7.7 provide clarification and ensure understanding of existing Technical Specification requirements. No physical modifications to equipment or equipment operation have been made. All other surveillance requirements and bases remain unchanged.

3. . Involve a . significant reduction in the margin of safety. Since all design basis accidents are unaffected by these changes, there is no reduction in the margin of safety.

Moreover, the Commission has provided guidance concerning the application of standards- in 10CFR50.92 by providing certain examples (March 6, 1986,

- SlFR7751) . of: hmendments that are considered not likely to involve a signifi-cant hazards consideration. Although the proposed changes are not enveloped by a specific example, the changes would not involve a significant increase in the probability or_ consequences of an accident previously analyzed. No physi-cal modifications to equipment -or equipment operation have been made. The proposed changes are intended to enhanc_e the existing Technical Specifications by ensuring consistency and increasing clarity.

Based upon- the information contained in this submittal and the environmental assessment for Hillstone Unit No. 3, there are no significant radiological or nonradiological . impacts associated with the proposed action, and the proposed license amendment will not have a significant effect on the quality of the human environment.

The Hillstone ' Unit No. 3 Nuclear Review Board has reviewed and approved the proposed changes and has concurred with the above determinations.

Regarding our proposed schedule for this amendment, we request issuance at your earliest convenience with the amendment effective within- 30 days of issuance.

In accordance -with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment.

U.S. Nuclear- Regulatory Commission B13940/Page 4 December 11, 1991 Should you require any additional information, please contact our Licensing representative.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY J. f'3b6dka f[Ukbv Executive Vice President cc: T. T. Martin, Region 1 Administrator i V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 STATE OF CONNECTICUT)

) ss. Berlin COUNTY Of_ HARTFORD )

Then personally appeared before me, J. F. Opeka, who being duly sworn, did state that he is Executive Vice. President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information art . rue and correct to the best of his knowledge and belief. -

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