NLS8800225, Application for Amend to License DPR-46,revising Tech Specs Re Containment Purge & Vent Valves as Part of Final Closeout of Multi-Plant Action Item B-24, Venting & Purging Containment While at Full Power & Effect of Loca. Fee Paid

Application for Amend to License DPR-46,revising Tech Specs Re Containment Purge & Vent Valves as Part of Final Closeout of Multi-Plant Action Item B-24, Venting & Purging Containment While at Full Power & Effect of Loca. Fee Paid

ML20151N780
Person / Time
Site:	Cooper
Issue date:	04/19/1988
From:	Parris H NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20151N784	List: ML20151N797 NLS8800225, Application for Amend to License DPR-46,revising Tech Specs Re Containment Purge & Vent Valves as Part of Final Closeout of Multi-Plant Action Item B-24, Venting & Purging Containment While at Full Power & Effect of Loca. Fee Paid
References
NLS8800225, NUDOCS 8804260013
Download: ML20151N780 (6)

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NLS8800225 April 19, 1988 Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Proposed Change No. 31 to Technical Specifications Cooper Nuclear Station NRC Docket No. 50-298, DDR-46 Gentlemen:

In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that the Technical Spccifications for Cooper Nuclear Station (CNS) be revised to incorporate the change listed below:

Attachment Subject 1 Containment Purge and Vent Valves A discussion and the applicable revised Technical Specification pages are contained in the attachment. The modification to the Technical Specifications within this proposed change has been evaluated Nith respect to the requirements of 10CFR50.92. The results of the evaluation are included in the attachment.

By copy of this letter and the attachment the appropriate State of Nebraska Official is being notified in accordance with 10CFR50.91(b).

This prc .J change incorporates all amendments to the CNS Facility Operating License through Amendment 118 issued April 1, 1988.

This change H.s been reviewed by the necessary Safety Review Committees and payment of $150 is submitted in accordance with 10CFR170.12.

W 8804260013 8804t9 PDR ADOCK 05000298 Mk P DCD

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NL58800225 1

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In addition to the signed original, 37 copies of this submittal l are also submitted for your use. Copies to the NRC Region IV ,

Office and the CNS Resident inspector are also being sent in accordance with 10CFR50.4(b)(2). 1 Sincerely, ePu H. G. Parris Vice-President, Production LGK/grs:dmr16/2 Attachment cc: H. R. Borchert  !

Department of Health

• State of Nebraska NRC Regional Office Region IV Arlington, TX NRC Resident Inspector Cooper Nuclear Station l

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, NLS8800225

. Page 3 April 19, 1988 STATE OF LJRASKA)

)ss PLATTE COUNTY )

H. G. Parris, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebrcska; that he is duly authorized to submit this request on behalf of Nebraska Public Power District; and that the '

statements contained herein are true to the best of his knowledge and belief.

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1. 1FI I MAM

' H'. G. Parri s Subscribed in m presance and sworn to before me this Mday of (7di i

, 1988 d!1 L NOTARY PUpl.lC/ h$$k[M l

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Attcchm:nt 1 Revised Technical Specifications for Containment Vent and Purge Valves Revised Pages: 165a 173 174 175 180 184

Reference:

1) Letter from W. O. Long to G. A. Trevors dated July 10, 1987, "Containment Vent and Purge Issues"

2) Lette. from J. M. Pilant to D. B. Vassallo dated December 15, 1983, "Operability of Purge Valves (B-24) Response"

3) Letter from J. M. Pilant to D. B. Vassallo dated July 19, 1984, "Containment i'arge and Vent System Unresolved Issues"

4) Letter from J. M. Pilant to D. B. Vassallo dated December 7, 1984, "Containment Purge and Vent System Unresolved Issues" Nebraska Public Power District is submitting this proposed Technical Specification change,as part of the final close u of Multiplant Action Item B-24 "Venting and Purging Containment while at Full Power and Effcet of LOCA" for Cooper Nuclear Station. Reference 1 listed the remaining open issues regarding containment vent and purge and provided the staff's comments on those items. A discussion of these items follows:

1. Debris Strainers - These have been installed over the drywell purge / vent inlet and outlet penetrations during the 1986 refueling outage at CNS.

2. Valve operability under LOCA conditions - During the 1986 CNS refueling outage the configuration of valves PC-238AV, PC-246AV, and PC-231MV were changed as follows:

1) Valvo 238AV is in a configuration that corresponds with Figure 11 and Test 30 of Allis-Chalmers Report VER-0209.

2) Valve 231MV is in a configuration that corresponds with Figure 10, Test 32.

3) Valve 240AV is in a configuration that corresponds with Figure 9, Test 29.

Torque switch settings for Val"es PC-230MV, 23 tMV, 232MV, and 233 MV have been adjusted per the vendor's reco==endation.

I Reference 1 also addressed certain Technical Specification issues that remained for resolution. These issues are addressed by this change request in the following manner.

a. Specification 3.7.B.5 has been added to page 165a to limit I venting / purging of the primary containment through both 24 inch j inboard and outboard vent valves through one Standby Cas l

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Trea tment (SBGT) System to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per calendar year with coolant temperature greater than 212*F. Time spent venting through the 2 inch bypass around the closed inboard vent valves will not count against this time limitation since an evaluation contained in Reference 4 concludes the SBGT System will remain operable after a design basis accident in this configuration.

b. Note 1 has been added to Table 3.7.4 on pages 173, 174, and 175 to verify once per cycle that the devices which limit the maximum opening angle to 60 degrees for the motor operated purge and vent isolation valves are functional.

Evaluation of this Revision with Respect to 10CFR50.92 The enclosed Technical Specification change is judged to involve no significant hazards based upon the following:

1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Evaluation:

The previously evaluated accident under consideration here is the Loss of Coolant Design Basis Accident discussed in Section XIV of the CNS Updated Safety Analysis Report. This a=endment request deals with the vent and purge containment isolation valves and conduct of vent / purge operations at power. This af f ects containment integrity and the fission product release to the secondary containment in the above-mentioneu accident.

The proposed amendment does not involve any hardware modifications or allow any plant operations that will increase the probability of the Design Basis Loss of Coolant Accident (LOCA). The proposed amendment will decrease the consequences of this accident by

a. Restricting the amount of purging / venting of the primary containment through both 24 inch containment isolation valves to a SEGT System when coolant temperatures are above 212*F. This decreases the probability of a LOCA damaging a SBGT System by excessive differential pressure across its filter units. Also, the other SBGT System ia requifed to be operational at the time and not to be used in the purge / vent operation. These additional requirements will better ensure at least one SEGT System is available to mitigate the fission product activity released to the environs as assumed in the previously evaluated accident.

b. Requiring that once every cycle the devices which limit the maximum )

opening angle for the motor operated isolation valves are verified l to be functional. This ensures that the valves can close against l the force of the LOCA and, hence, perform their isolation function.

Based on the above, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. l I

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2. Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?

Evaluation:

The proposed amendment places additional restrictions on vent / purging operations and the vent / purge isolation valves as described above and does not permit any new mode of operation that would create the possibility for a new of different kind of accident from any previously evaluated.

3. Does the proposed amendment involve a significant reduction in the margin of safety?

Evaluatio_n:

The proposed amendment places additional restrictions on plant components and operations. It does not affect any operating limits or trip setpoints so there is no change in the margin of safety.

4. Additional basis for proposed no sign.ficant hazards consideration determination:

The connission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48CFR14870).

"(i1)' A change that constitutes an additional The examples include:

limitation, restriction, or control not presently included in the  !

Technical Specifications. . ." It is the District's belief that the i proposed change is encompassed by the above example, l l

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