ML20029B300

Application for Amends to Licenses NFP-76 & NFP-80,revising Tech Spec Surveillance 4.6.1.2 Re Containment Leakage Rates

ML20029B300
Person / Time
Site:	South Texas
Issue date:	02/26/1991
From:	Kinsey W HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20029B301	List: ML20029B300 ML20029B302
References
ST-HL-AE-3708, NUDOCS 9103070022
Download: ML20029B300 (8)

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February 26, 1991 ST HL AE 3708 File No,. 09.06 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 2055)

South Texas Project Electric Cenerating Station Units 1 and 2 Docket Nos. STN 50 498, STN 50 499 Proposed Amendment to the Unit 1 and 2 Technical Speci. fica tion Surveillapee 4. 6.1,,,,2 The purpose of this submittal is to propose a change to South Texas Proj ect Electric Generating Station (STPEGS) Technical Specification Surveillance 4.6.1.2. Surveillance 4,6.1.2 currently specifies that the methods of American National Standard Institute (ANSI) 45.4-1972 be used to verify containnent leakage rates. The proposed change will allow the enhancements of Appendix J of 10CFR50 to be used to satisfy Surveillance 4.6.1.2.

Houston Lighting & Power Company (llL&P) has reviewed the attached

. p.oposed amendment pursuant to 10CFR50.92 and determined that it does not involve a significant hazards consideration. The basis for this determination is provided in the attachments. In addition, based on the information contained in this submittal and the NRC Final Environmental Assessment for STPEGS Units 1 and 2, H14P has concluded that, pursuant to 10CFR51, there are no significant radiological or non-radiolot,1 cal impacts associated with the proposed action, and the proposed license .imondment will not have a ignificant effect on ti e quality of the e wironment.

The STPEGS Nuclear Safety keview Botrd has reviewed and approved the proposed changus.

In accordance with 10CFR50.91(b), II.4P is providing the State of Texas with a copy of this proposed amendment.

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. South Texas Project Electric Generating Station ST llL AE-3708 File No.. G9.06 10CFR50.90 If you should have any questions concerning this matter, plcaso contact Mr. A. W. liarrison at (512) 9/2 7290 or myself at (512) 972 7921.

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liarren 11. Kinr,ey, J Vice President Nuc1 car Generation GCS/sgs Attachments: 1. Significant Hazards Evaluation for a Proposed Change to Technical Specification Surveillance 4.6.1.2

2. Proposed Change to Technical Specif! cation Surveillance 4.6.1.2

3. Proposed Change to Updated Final Safety Anr21ysis Report A t / 011.N'.0

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' , licuston hth TexasLighting & Powcr Project Electric Ga. Compny crating Statw.

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Regional Admit istrator, Region IV Rufus S. Secett Nuclear Regulatory Commission Associate Ceneral Counsel (11 Ryan Plata Drive, Suite 1000 Houston Lighting 6 Power Company I Arlington, TX 76011 P. O. Box 61867 Houston, TX 77208 Coorge 1 ck, Project Manager U.S. Nutlear Reguistory Commission INPO Washington, D tuj55 Records Center 1100 circle 75 Parkway  !

J. 1. Tapia Atlanta. CA 30339 3064 l Senior Resident inspector I c/o U. O. Wuclear Reg.ulatory Dr. Josep., M. Hendrie Comnission 50 Be11 port Lac.S P. 0 Pox 910 Be11 port, NY 11713 Lay City, TX 77414 O. K. Lacher l J. R. Newman, Esquire Buresu of Radiation Control Newman 6 Holtzinger, P.C. Texas Deportment c.C Health 1615 L Street, tl.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756#1189 D. E. Uard/T. M. Puckett dantral Power and Light Company F.- O. Box 2121 Corpus Christi, TX 78403 J. C. Lanier/M. B. Lee City of Austin' p Electric Utility Department P.O. Box 1088 Austin, TX 78767 ,

R. J. Costello/M. T. Hardt City Public Servico Board P. O. Box 1771 San Antonio. TX 78296 Revised 01/29/91 L4/NRC/

UNITED STATES OF AiERICA NUCLEAR REGUI.ATORY .0MMI S S IO!1 Ir. the Matter )

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Hoveton Lighting & Power ) Docket Nos. 50 493 Company, et al., ) 50 499

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South Texas Project )

Units 1 and 2 )

Al21 DAVIT Warren 11. Kinsey, Jr. being duly sworr hereby deposen and says that he is Vice President, Nucicar Generation, of 11 . ton Lighting 6 Power Cc.rpany; that he is duly cuthorized to sign and file with the Nuclear Regulatory Comrnission the attached proposed changes to the South Texas Project Electric Generating Station Technical Specification Surveillance 4.6.1.2; is f,uniliar with the content thereci; and that the matters set forth thrrein are true and currect to the best of his knowledge and belief.

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Warren 11. Kinsey, J5 . q, Vice President, Nuclha Generation STATE OF TE%S )

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Cubscribed and sworn to before me, a Notary Public in and for The State of Texas this db day of Fe.brua.rg ,1991.

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• T ,i ATTAClutENT 1 SIGNIFICANT llAZARDS EVALUATION FOR A PROPOSED C'-!ANGE TO TECilNICAL SPECIFICATION SURVEILIANCE 4.6.1 ?

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Attachincnt 1 ST 1tL AE 3708 Page 1 of 3 SIGNIFICANT llAZARDS EVALUATION FOR A l'ROPOSED CllANCE TO TECHNICAL SPECIFICATION SURVEILLANCE 4.6.1.2

Background

In 1973, when the Cormnission initially promulgated its requirements concerning containment integrated leakage rate testing (10CFR50 Appendix Ji, the Commission required licensees to use state of the art leakage test methodology and specifically called for Type A test methods described in ANSI d45.4 1972, " Leakage Rate Testing of Containment Structure for Nuclear Reactors" (Appendir.J. Sec. III.A.3). This standard accepted two techniques for ovaluating test results: the Total Time data analysis technique and t.he Point to Point data analysis technique.

Subsequent advances in Icakage rate testing technology have provided improved test methods, including the Mass Point method. The Mass Point method was incorporated in a newer standard, ANSI /ANS 56.8 1987, " Containment System Leakage Testing Requirements" .

The STPECS Technical Specifications were written using he Standard Technical Specifications as a model, The Standard Technical Specifications state that the methods and provisions of ANSI N45.4 1972 must be used. STPECS Technical Specifications as approved on August 21, 1987 state that the methods and provisions of ANSI N45.41972 are to be used to satisfy the containment Leakage Curveillance (4.6.1.2).

In Federal Register $3FR45890, November 15. 1988, the NRC amended Appendix J to explicitly permit 2se of the Mass Point method. The NRC staff had accepted the Mass Point method as an improved alternative method of calculating containment leakage rates. Strict interpretation of Appendix J had previously prevented use of thi; method.

Although Appendix J was revised, the requirements of STPECS Technical Specification Survei1}ance 4.6.1.2 continue to endorse the methods and provisions of ANSI N45.4 1972. This prevents STPECS from using the state of the art leakage test methodology of ANSI /ANS 56.8 1987 to oatisfy Technical Specification Surveillance 4.6.1.2 requirements. Both methods were used durin6 the Type A test performed in the Unit 1 third refueling outage and the advantages of the enhanced methodology of ANSI /ANS 56,8 1987 vere demonstrated.

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ST.HL AE 3708 .'

Page 2 of 3 Proposed Change Modify Technical Specification Surveillance 4.6.1.2 to delete the reference.to ANSI 45.2 1972 and reference the .nethods and provisions endorseo This will prevent future administrative Technical in 10CTR50 Appendix J.

Specification changes if 10CTR50 Appendix J is revised.

Safety Evaluation Based on the above, the proposed change is administrative in nature, lilAP has reviewed ANS1/ANS.56.8 1987 and determined that the methods and provisions.are an enhanced calculational method appropriate for use at STPECS..

Since the proposed method has been reviewed, approved and incorporated into

! _10CTR50 Appendix J. there is no safety significanct associated with the proposed change, qciermination of Significant Hazards Pursuant to 10CTR50.91 this analysis provides a determination that '

.the proposed change.to Technical Specifications does not involve a significant hasards consideration as defined in 10CTR50.92.

l '. The proposed change does not involve a significant increase.in the probability or consequences of a previously evaluated accident. The purpose of an Integrated Leak Rate Test is to determine the leakage rate of containment. Therefore, changing the method of evaluating test data will have no.cffect on the probability of an accident previously evalTated. The i consequerwes of a previously e <lunted accident remain unchanged because the new method of evaluating test data has been reviewed and approved by the NRC staff .ind determined to be~an improved alternative method of calculating containment leakage rates.

lil4P has reviewed ANSI /ANS.56.81987 and agrees with the NRC determination.

2. . The proposed. change'does not create the possibility of a new or different accident from any previously evaluated. There are no changes to the design or operation of STPECS as a result of the-proposed change. Therefore, a new or different accident from a

-previously evaluated accident is not created.

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ST llL.AE.3708 Page 3 of 3 Determination of Gignificant linrards (cont'd)

3. The proposed change does not involve a significant reduct. ion in the margin of t.afety. The methods and provisions of 10CFR$0 Appendix J are state.cf the art for calculation of containment leakage rates. These methods and provisions have been reviewed and approved by the NRC staff as not involving a significant reduction in the margin of safety. HL6P has reviewed ANSI /ANS.56.8 1987 and determined that the enhanced calculational methods are appropriate for use at STPECS.

conclusion The proposed change-is administrative in nature and is consistent with the requirements of 10CPR$0 Appendix J. !!!AP has reviewed ANSI /ANS 56.8 1987 and determined that the inethods and provisions are an enhanced calculational method appropriete for use at STPEOS. lilAP requests that the proposed change be approved.

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