ML20082U678

Application for Amends to Licenses DPR-24 & DPR-27, Consisting of TS Change Request 147,changing Reactor Vessel Materials Surveillance Capsule Removal Schedules

ML20082U678
Person / Time
Site:	Point Beach
Issue date:	09/13/1991
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20082U680	List: ML20082U678 ML20082U693
References
CON-NRC-91-097, CON-NRC-91-97 VPNPD-91-315, NUDOCS 9109200296
Download: ML20082U678 (4)

Text

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m Wisconsin Electnc POWER COMPAtH m w McNuoc A m muwe mm W1m M VPHPD-91-315 10 CFR 50.4 HRC-91-097 10 CFR 50.90 September 13, 1991 Document Control Desk U.S. HUCLEAR REGULATORY COMMISSION Mail Station P1-137  :

Washington, D.C. 20555 Contlement DQCM:TS 50-266 AND 50-301 TEC11NICAL SPECIPLCATIoN CllANGE REQUEST 147 -

REMOVAL OF TiiE WITilDBAHAL. SCliEDULES FOR REACTOR _ VESSEL MATERIAL SPECIMEjlft TROM TECilNICAL SPECIFICATIONS POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 In accordance with the requirements of 10 CFR 50.4 and 50.90, Wisconsin Electric Power Company (Licensoo) hereby requests amendments to Facility Operating Licensos DPR-24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2 respectively, to incorporato changos to the plant Technical Specifications. The proposed changes will removo Tables 15.3.1-1 and 15.3.1-2, the reactor vossol materials survol11anco capsulo removal schedulos for Units 1 and 2, '

rospectively, from the Technical Specifications. These tables will bo subsequently incorporated into our Final Safety Analysis Report (FSAR) in its next revision. Corresponding changes to Technical Specification Section 15.3.1.D and the basis for this section are also proposed. Attached are marked-up Technical Specification pages with the proposed revisions included.

NRC Generic Letter 91-01, "Romoval of the Scnodule for the Withdrawal of Reactor Vossel Material Specimens from Technical Specifications,"

provides guidance on'the preparation of a roquest for a licenso amendment to perform this Technical Specification change. The information discussed below is consistent with the guidance in the anclosure of this Genoric Lotter. <

Appendix 11 to Part 50 of Title 10 of tho Code of Federal Regulations requires that a reactor vossel material surveillance program be maintained in order to prevent brittle fracture of the reactor vessel.Section II.B.3 of this appendix requires that the associated

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Document Control Desk September 13, 1991 Page 2 withdrawal schedules be approved prior to their implementation.

Having thoso schedulos in the Technical Specifications duplicates the regulatory controls placed on them by Appendix H. Surveillance requirements will still require that, following removal, those apocimens be examined to dotormino any changos in mator3*1 proporties. The results of thoso examinations will be used to updato temperature and pressure limits. Thetofore, there is no need for thoso schedulos to be included in the Technical Specifications.

Accordingly, we propose to removo Tables 15.3.1-1 and 15.3.1-2 from the Technical Specifications and incorporate them into our Final Safety Analysis Report (PSAR) in its next revision. Additionally, we propose to remove all referencos to those tablos in the Technical Specifications by modifying Specification 15.3.1.B, Paragraph 4, to road:

" Tao reactor vessel material irradiation surveillanco specimens are removed and examined, according to NRC approved schedulos, to datormino changes in material proporties. The results of thoso examinations shall be considered in the ovaluation of the prediction method to be used to updato Figuros 15.3.1-1 and 15.3.1-2.

Rovised figures shall be provided to the Commission at least sixty (60) days before the calculated exposure of the applicablo reactor 'vossol excoods the exposure for which the figures apply."

We also propose to modify the final paragraph of the " Basis" for Specification 15.3.1.B to road:

"The reactor vessel materials surveillance capsulo removal scheduler. have boon developed based upon the requirements of the Codo of Federal Regulations, Title 10, Part 50, Appendix H and with consideration of ASTM Standard E-185-82._ When the capsulo lead factors are considered, the scheduled removal dates accommodate the weld data noods of all participants in the Babcock and Wilcox Mastor Integrated Reactor Vessol Survoillanco Program. Additionally, the schedule will provido-plate / forging data as well as fluenco data corresponding.to tho_ expiration of the current licensos and of any futuro licenso extensions."

This proposed " Basis" change further changes a modification that has boon-proposed in Technical Specjfication change Request 138 dated March 30, 1990.

In accordance with the requirements of 10 CFR 50.91(a), wo have evaluated the above changes against the standards of 10 CFR 50.92 and l

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Document ';ontrol Dock September 13, 1991 Page 3 i

have determined that the operation of Point Beach Nuclear Power Plant Units 1 and 2 in accordance with the proposed amendments (ses not prosent a significant hazards consideration. Our analysis of the requirements of 10 CFR 50.92 and the basis for our conclusion are as follows:

(1) operation of this facility under the proposed Technical Specification change will not create a significant increase in the probability or consequencos of an accident previously ovaluated. This amendment only removes two tablos from the Technical Specifications, installs them into the Final Safety Analysis Report, and removes all references of those tables from the Technical Specifications. Rogulatory controls to provent changes to those withdrawal schedules is provided for in the Code of Fodoral Regulations, Title 10, Part 50, Appendix H. Additionally, the surveillanco requirements on pressure and temperaturo require that thoso specimens be removed and examined to determino changes in material proportion. The results of these examinations shall be considered in the ovaluation of the prediction method used to updato pressure and temperaturo limits. Thorofore, thero is no chango in the required actions that will be performed. There is no physical change to the facility, its systems, or its operation. Thus, an incroauod probability or consequences of an accident previously evaluated cannot occur.

(2) Operation of this facility under the proposed Technical Specification chango will not create the possibility of a new or different kind of accident from any accident previously evaluated. This amendment only removes two tables from the Technical Specifications and installs them into the Final Safoty Analysis Report. Controls to provent changos to those withdrawal schedules is provided for by the Code of Federal Regulations, Titio 10, Part 50, Appendix H. There is no physical change to the facility, its systems, or its operation.

Thus, a now or different kind of accident cannot occur.

(3) Operation of this facility under the proposed Technical Specification change will not croato a significant reduction l

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.in a margin of safety. -Under this proposed amendment, two tables will be removed from the Technical Specifications and installed into the Final Safety Analysis Report. Controls governing changes to these withdrawal schedules is provided

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Document Control Desk September 13, 1991 Page 4 for by the Code of Federal Regulations, Title 10, l' art 50, Appendix H. Thoroforo, this amendment will not result in any chango in specimen withdrawal schedules. Also, the actions to be taken subsequent to specimon withdrawal remain unchanged.

Since this amendment does not change the facility, its systems, or its operation, a significant reduction in a margin of safety cannot occur.

Pl?a.to contact us if thore are any questions.

Very 1.vuif fours,

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O. W. Fah

-Vice President Huclear Power Enclosures

, copios to Puplic Service commission of Wisconsin i NRC Regional Administrator, Region III NRC Resident Inspector Subscri]*odandsworntobeforeme this f 6 -day of Lg huf it 1991.

_ .4n;ca - 4p ' c l<.U Notary Public, State of Wisconsin My Commission expires E 2 ~2 ' W _.

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