ST-HL-AE-5402, Application for Amends to Licenses NPF-76 & NPF-80, Clarifying Surveillance Interval for Surge Tank Level Instrumentation

Application for Amends to Licenses NPF-76 & NPF-80, Clarifying Surveillance Interval for Surge Tank Level Instrumentation

ML20115C414
Person / Time
Site:	South Texas
Issue date:	07/08/1996
From:	Cloninger T HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20115C417	List: ML20115C418 ST-HL-AE-5402, Application for Amends to Licenses NPF-76 & NPF-80, Clarifying Surveillance Interval for Surge Tank Level Instrumentation
References
ST-HL-AE-5402, NUDOCS 9607110327
Download: ML20115C414 (9)

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l The Light c o mp a n y out h Tezu Project Dectric Generating Station P. & Box m Wadmorth, Texas 77483 l Houston Lighting & Power July 8, 1996 ST-HL-AE-5402 File No.: G20.01 G21.01 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Proposed Revision to Technical Specific' tions Clarifyine Surveillance Interval for Surce Tank Level Instrumentation The South Texas Project proposes to amend its Operating License NPF-76 and NPF-80 for Units I and 2, respectively, by incorporating the attached proposed changes to the Technical Specifications. The purpose of this amendment is to clarify the interval for completing surveillance requirement 4.7.3.b.3 of the South Texas Project Technical Specifications.

The South Texas Project has reviewed the attached proposed amendment pursuant to 10CFR50.92 and determined that the changes do not involve a significant hazards consideration. In addition, the proposed amendment satisfies the criteria of 10CFR51.22(c)(9) for categorical exclusion from the requirement for environmental review. This determination is based on the conclusion that the proposed change does not involve a significant hazards consideration, will not involve significant changes in the types or amounts of radioactive effluent, does not affect any of the permitted release paths, and does not involve a significant increase in individual or cumulative occupational exposure.

The South Texas Project Nuclear Safety Review Board has reviewed and approved the proposed change.

I l The required affidavit, along with a Safety Evaluation and statement of No Significant Hazards

Consideration Determination associated with the proposed changes, and the marked-up affected page of the Technical Specifications and the Bases are included as attachments to this letter. Ah In accordance with 10CFR50.91(b), the South Texas Project is providing the State of Texas with a copy of this proposed amendment.

9607110327 960708 PDR ADOCK 05000498 P PDR

• 1. 1. Project Manager on Behalf of the Participants in the south Texas Project

Houston Lighting & Power Company South Texas Project Electric Generating Station ST-HL-AE-5402 l

File No.: G20.01 G21.01 Page 2 l If there are any questions, please contact either Mr. P. L. Walker at (512) 972-8392 or me at l l (512) 972-8787. i l

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Attachments: 1) Affidavit l 2) Safety Evaluation and No Signifi ant Hazards Consideration

3) Markups of Proposed Changes to Technical Specifications i

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l TSC-995402

Houston Lighting & Power Company ST-HL-AE-5402 -

South Texas Pmject Electric Generating Station File No.: G20.01 G21.01 Page 3 Leonard J. Callan Rufus S. Scott Regional Administrator, Region IV Associate General Counsel U. S. Nuclear Regulatory Commission Houston Lighting & Power Company.

611 Ryan Plaza Drive, Suite 400 P. O. Box 61067 Arlington, TX 76011-8064 Houston, TX 77208 Thomas W. Alexion Institute of Nuclear Power Project Manager, Mail Code 13H3 Operations - Records Center .

U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 Atlanta, GA 30339-5957 David P. Loveless Dr. Joseph M. Hendrie Sr. Resident Inspector 50 Bellport Lane c/o U. S. Nuclear Regulatory Comm. Bellport, NY 11713 P. O. Box 910 Bay City, TX 77404-0910 Richard A. Ratliff Bureau of Radiation Control J. R. Newman, Esquire _ Texas Department of Health Morgan, Lewis & Bockius 1100 West 49th Street Austin, TX 78756-3189 1800 M Street, N.W.

Washington, DC 20036-5869 U. S. Nuclear Regulatory Comm.

M. T. Hardt/W. C. Gunst Attn: Document Control Desk City Public Service Washington, D. C. 20555-0001 P. O. Box 1771 San Antonio, TX 78296 J. C. Lanier/M. B. Lee J. R. Egan, esquire City of Austin Egan & Associates, P.C.

Electric Utility Department 2300 N Street, N.W.

721 Barton Sprmgs Road Washington, D.C. 20037 Austin, TX 78704 Central Power and Light Company J. W. Beck ATTN: G. E. Vaughn/C. A. Johnson Little Harbor Consultants, Inc. I

' P. O. Box 289, Mail Code: N5012 44 Nichols Road Wadsworth, TX 77483 Cohassett, MA 02025-1166 1

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TSC-96/5402 I

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )  !

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Houston Lighting & Power ) Docket Nos. 50-498  !

l . Company, et al., ) 50-499 i l- )

l South Texas Project )

Units 1 and 2 )

AFFIDAVIT l

j I, T. H. Cloninger, being duly sworn, hereby depose and say that I am Vice President, Nuclear Engineering, of Houston Lighting & Power Company; that I am duly authorized to sign and file with the Nuclear Regulatory Commission the attached proposed revision to Technical Specification 3/4.7.3; that I am familiar with the content thereof; and that the matters set forth therein are true and correct to the best of my knowledge and belief.

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. . El'onin co Presi nt, uclear gin ng STATE OF TEXAS )

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COUNTY OF MATAGORDA )  !

Subscribed pnd sworn to before me, a Notary Public in and for the State of Texas, this 8g day of Jo l[ IS 9 4.

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(('d1 f wcm.m hawa10/9/97 : l Notary Public in and fci the f State of Texas l- Ip . _

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ST-HL-AE-5402 File No.: G20.01, G21.01 Page 1 of 3 ATTACHMENT 2 No Significant Hmrds Consideration Determination Description of the Proposed Change:

The South Texas Project requests an amendment to Technical Specification Surveillance Requirement 4.7.3.b.3 to clarify when the Component Cooling Water System surge tank level instrumentation is to be demonstrated operable by performance of a channel calibration test. This change will clarify the interval for completing this surveillance requirement.

The proposed changes are indicated on the Technical Specification page provided as Attachment 3 to this submittal.

Description of Current Requirement:

The Technical Specification Surveillance Requirement 4.7.3.b.3 states that at least three component cooling water loops shall be demonstrated operable at least once per 18 months during shutdown, by verifying that the surge tank level instrumentation which provides automatic isolation of portions of the system is demonstrated operable by performance of a charnel calibration test.

Safety Analysis:

The South Texas Project requests a revision to Technical Specification 4.7.3.b.3 to clarify the interval for completing the channel calibration test for the Component Cooling Water System surge tank level instrumentation. This calibration can be performed during any plant mode since three-train redundancy ensures sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The Component Cooling Water System surge tank is partitioned into three equal volumes by internal baffles. Each compartment is monitored by level instrumentation which provide automatic isolation at about 9 inches and about 12 inches above the tank centerline in the open, undivided portion of the surge tank. The associated Component Cooling Water train is taken out of service prior to performing the calibration. Calibration of the 9-inch instrumentation is done on a train basis, when the subject Component Cooling Water train is out-of-service and isolated. If level decreases to 9 inches above the tank centerline, the other two trains will isolate. Because the train in calibration is already out of service, the automatic isolation function of this instrumentation is not needed regardless of the plant mode. The 12-inch instrumentation which provides for isolation of non-safety cooling loads is disabled for the channel being calibrated. However, redundant isolation capability is provided by the two remaining 12-inch level instruments and, if surge tank level continues to decrease, from the 9-inch level instrumentation.

rsc.96/5402 1

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ST-HL-AE-5402 File No.: G20.01, G21.01 Page 2 of 3 The worst credible challenge to the plant during this evolution is one additional Component Cooling Water train rendered inoperable with one train initially out of service. Should this occur, the third Component l Cooling Water train would actuate, supplying water to the common header. Therefore, there is no l sigmficant increase in the probability or consequences of an accident previously evaluated.

i Bues of the Proposed Amendment: t Clarification of the statement will remove an ambiguity concerning the plant conditions required for ,

performing this calibration. The calibration will be performed in plant operational modes consistent with the continued safe operation of the plant. The frequency of this channel calibration is intended to be at least once per 18 months.

Impact of the Proposed Change: ,

Implementation of the proposed change to the surveillance criteria does not introduce significant or adverse changes to the plant design basis. The required intervals between surveillances, where specified, will continue to be met.

Based upon the above, the proposed amendment request has no significant negative impact on any system 1 or operating mode. l Implementation:

The South Texas Project requests that this proposed amendment be given an expeditious review to support approval by September 16,1996, and that the effective date for the change be 30 days after approval by the Nuclear Regulatory Commission.

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l NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION 1 l

Pursuant to 10CFR50.91, thi.s analysis provides a determination that the proposed change to the Tecimical Specifications does not involve any significant hazards consideration as defined in 10CFR50.92, as described below:

1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change to Technical Specification Surveillance Requirement 4.7.3.b.3 will not affect any accident initiators or precursors and will not alter the design assumptions for the systems or components used to mitigate the consequences of an accident. Calibration is performed on level instrumentation of l Component Cooling Water System trains that r.re out of servica for scheduled maintenance. Isolation redundancy is provided by instrumentation associated with the trains that are in service during the )

calibration. Since the surveillance will continue to be performed at the specified interval, this proposed l change will not increase the probability of occurrence of an accident previously evaluated. The ,

surveillance does not differ from those previously performed; theufore, there is no impact on the i consequences of an accident previously evaluated.

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2. The proposed change does not create the possibility of a new or different kind of accident from ,

any accident previously evaluated. )

Clarifying the surveillance interval for surge tank level instrumentation does not involve installation or operation of new or different kinds of equipment. There is no change in the procedure as described in the i Technical Specifications. The change only clarifies the interval at which the subject calibration will be i I

performed. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. The proposed change does not involve a significant reduction in a margin of safety. I The specified surveillance will remain as stated in the Technical Specifications. Consequently, there is j no reduction in the effectiveness of the surveillance in ensuring equipment operability. Calibration is I performed on level instrumentation of Component Cooling Water System trains that are out of service for scheduled maintenance. Isolation redundancy is provided by instrumentation associated with the trains that are in service during the calibration. Consequently, clarifying the interval at which the calibration l is performed will have no significant impact on the margin of safety.

Based upon this evaluation, the South Texas Project has concluded that these changes do not involve any j significant hazards considerations.

TsC-96/5402