ML20093H556

From kanterella
Revision as of 22:30, 24 September 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Application to Amend License DPR-50,consisting of Rev 2 to Tech Spec Change Request 104 to Reflect New Schedule for Withdrawal,Testing & Evaluation of Capsule TMI-1C,per Integrated Relief Valve Matl Surveillance Program
ML20093H556
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 07/10/1984
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20093H546 List:
References
NUDOCS 8407250191
Download: ML20093H556 (4)


Text

- . .. ..

i METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY j AND PENNSYLVANIA ELECTRIC COMPANY THREI ~ MILE ISLAND NUCLEAR STATION, UNIT 1 1

Operating License No. DPR-50 Docket No. 50-289 Technical S;Iecification Change Request No. 104, Rev. 2 i

This Technical Speclfication Change Request is submitted in support of Licensee's reque'it to change Appendix A to Operating License No.

DPR-50 for Three Mij.e Island Nuclear Station, Unit 1. As a part of this request, proposjedreplacementpagesforAppendixAarealso included.

CPU NUCLEAR CORPORATION A

BY Director, TMI-l Sworn and Subscribed  ;

this tobefore[m day of <Jf. /4h[984.

,(

dMg d Notary Public 1

, JuuA L,-m. PAnit, m,.Netwy n hh

  • My Cansmission Empiros Nov. 3,1986 u,. . ,

\ ,,

O P

b - .-

I UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Ill THE MATTER OF DOCKET No. 50-289 LICENSE NO. DPR-50

.GFU NUCLEAR CORPORATION This is It'o certify that a copy of Technical Specification Change Request' No 104, Rev. 2 to Appendix - A of the Operating License for Three Mile Island

. Nuclear. Station Unit 1, has, on the date given below, been filled with-executives.of-Londonderry Township, Dauphin County, Pennsylvania; Dauphin

County, Pennsylvania; and the Pennsylvania Department: of Environmental Resources, Bureau of' Radiation Protection, by deposit in the United States

'-cail, addressed as follows:

Mr. Jay H. Kopp, Chairman Mr. John E. Minnich, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County

~

R. D. #1, Ceyers Church Road. Dapuhin County Courthouse Middletown, PA. 17057 Harrisburg, PA. 17120

.Mr. Thomas Gerusky, Director PA. Dept. of 1nvironmental Resources Bureau of Radiation Protection P.O.' Box 2063 Harrisburg, PA._17120 GPU NUCLEAR CORPORATION BY l Director, TMI-1 DATE: July 10,1984

lT-I. TECHNICAL SPECIFICATION CHANGE REQUEST NO. 104, REV. 2 Yhe Licensee requests the attached changed pages replace the following pages of the existing Technical Specifications:

Appendix A Replace 4-11, 4-12, 4-13 and 4-27a II.- REASON FOR CHANGE REQUEST As part of the Integrated RV Material Surveillance Program (RVMSP) of the B&W Owners Group (B&W OG), TMI-l Capsule TMI-lC, which is -

presently being irradiated at CR-3, is proposed to be withdrawn, tested and evaluated in accordance with a recommended new withdrawal schedule. Implementation of this new schedule will require a change to the Technical Specification for TMI-1, particularly Table 4.2-2.

III. SAFETY EVALUATION JUSTIFYING CHANGE The following reasons provide the technical basis for the change:

1. The implementation of low leakage fuel cycles at most B&W designed plants, including Three Mile Island Unit 1, caused a corresponding decrease in the estimated end-of-life (E0L) fluences for affected reactor vessels. If capsule withdrawal continues according tc the current schedule, a major portion of the capsule currently under-going irradiation will accumulate fluences well in excess of estimated vessel EOL. Consequently, the data obtained from evalu-ation of these capsules will not be useful for evaluation of corresponding vessel integrity. The attached Table 1 for TMI-l illustrates the impact of this fuel cycle design change. The revised schedule will assure acquisition of representative capsule data which can be related to the irradiated construction of the vessel.
2. The withdrawa'l schedule, as specified in ASTM Spec. E-185-79 referenced in 10CFR50, Appendix H. requires that capsules be withdrawn at designated intervals such that the capsule fluence will correspond to specific conditions of the reactor vessel with respect to irradiation damage. Although the B&W OG Integrated RVMSP was designed prior to E-185-79, restlations required that the program be maintained, to the extent practical, with the updated requirements. Therefore, to insure that capsules are withdrawn in a manner consistent with the required compatibility of capsule fluence and RV fluence, it is necessary to revise the current withdrawal sequence.

e 5 .- A

~

~

[ .

The attached Table 4.2-2 shcus the proposed change. Tnis d ie, d.ich is part of de T:C-1 Tech Spec should ccr/er the reccmended new . id-drawal schedule of the B&WO3. B&W and the :~aterials Ca=ittee chair .:n

- have contacted the NRC and obtained Staff concurrence that the prep: sed capsule renoval schedule is acceptable.

Additionally, Sections 4.2.5 and 4.2.6 have been deleted. Section 4.2.5 currently requires submission of a special report or an application for a License Amendnent should Crystal River - Unit 3 cumulative reacter utilization factor (CRUF) drop belcw 65%. The original TSCR No.104 requested to change the method in which CRUF was to be calculated.

'Ihe integrated RVMSP is continuously being updated to reflect actual ,

fluence accumulations in the operating host reactors. Since the B&dDG-Integrated Reactor Vessel MaterialSurveillance program has been revised, there is no longer a need for either a'special report or an application for a license amendment based on Crystal River - Unit 3 CRUF. Tne special report requested in 4.2.6 was submitted September 17, 1982 (5211-82-255) so this requirement has been fulfilled and need not remain in the TM1-1 Technical Specifications.

IV. NO SIGIFICET HAZARDS CONSIDERATICN The proposed change to the Technical Specifications for TtE-1 revices the insertion and withdrawal schedule for Capsule TIE-1C. This will refine our methodology to satisfy the requirements of 10 T R 50 Appendix G and H, and also results in a more realistic evaluation of vessel integrity.

V. AMENINENT CIASSIFICATICN (10 GR 170.22)

Check No. 034612 was provided with Technical Specification Change Request No.104, Rev. O dated June 8,1981. ,

VI. IMPIEMENTATION PERIOD 2t is requested that this amendment be trade effective imediately upon issuance.

O t

a