ML19253B863
| ML19253B863 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/30/1978 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19253B862 | List: |
| References | |
| NUDOCS 7910310611 | |
| Download: ML19253B863 (5) | |
Text
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METECFCLIT!di DISC:s CCISA iY JERSEY CE:i~RAL FC'4ER S LIGHT CC GATI A'ID FE:CISYLVA: IIA ELECTRIC CCMPA'iY THREE MILE ISLA'iO NUCLE!J1 STATICI UNIT 1 Cperating License :!c. EPR-5C Docket Nc. 50-289 Technical Specificatien Chave Pequest !ic. 77 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating Licens 2 IIc. DFB-50 for
"'hree Mile Island Nuclear Station Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
METE 0FCLITA's DISCN CCMFATI By r.
1 Vice" Preiident
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Sworn and subscribed to me this b day of N 1978.
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1505 210 7910810 $/ /
U:IITED STATES OF A! ERICA iUCLEAR REGULATORY CGICIISSIC:I
77 to Appendix A of the Operating License for Three Mile Island :luelear Station Unit 1, has, cn the date given below, been filed with the U. S. ?!uclear Regulatory Cc=ission and been served en the chief executives of Lcndenderr/ Tcvnship, Dauphin County, Penr.sylvania and Dauphin County, Pennsylvania by deposit in the United States mil, addressed as follcvs :
Mr. Welden B. Arehart Mr. Harry 3. Reese, Jr.
Board of Superviscrs of Ecard of County Ccmissioners Londonderry Township of Dauphin County B. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITA I FDISCII CCMPA iY By, /
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Vice President
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Dated: August 30,1C76 1505 211
Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Request No. 77 The licensee requests that the attached changed pages replace pages 4-36c through 4-36g, figures 4.4-1 through 4.4-5 and page 6-18.
Reasons for Change This change request is based on the Commission's letter of December 29, 1977, which granted permission to modify the Ring Girder Surveillance Test.
Safety Evaluation Justifying Change In their letter of December 29, 1977, the Commission requested to be informed of the repairs committed to in our letter of June 3,1977. These repairs have been completed in strict accordance with the repair procedure for the cleaning, packing and curing of exposed concrete voids adjacent to dome bearing plates.
The Commission stated that, as a result of their review of the previous Reactor Containment Building Ring Girder Surveillance Tests, the safety cargins in the structure at the present time, are adequate.
The Commission has concluded that there is reasonable assurance that the containment structure will continue to perform its intended safety function.
F I
h.h.2.2 Ringer Girder Inspection Program The Ring Girder Inspection Pro' gram has been modified (per URC letter of Dece=ter 29, 1977) to consist of a visual inspection of the ring girder.
A.
Periodic Inspection Schedule The frequency of the =odified ring girder inspections shall be in conjunction with the Inservice Tendon Surveillance Program per T.S.
h.4.2.2.1.
B.
Inspection Method The concrete adjacent to each tendon bearing plate on the ring girder shall be inspected visually. Tha acceptance criteria shall be that all crack vidths greater than 0.010 inch shall be recorded and evaluated. Any crack vidth greater than 0.050 inch shall be cause for investigation to determine the amount of structural impairment upon the reactor building and its continued structural integrity.
Pages h-36d through h-36g and figures h.4-1 through h.h_5 deleted i
l 1505 213 i
h-36c
6.9 REPORTI!!G RECUIRDIENTS 6.9.3 Uniq7.e Reporting Requirements A.
Special reports shall be submitted to the Director of the Regulatory Operations Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below:
Tests Submittal Dates (1) Contain=ent Structural Integrity Test (al Tendon Surveillance Program Within 3 months after performance of surveillance program.
(2 ).
Containment Integrated Leak Within 6 months after Rate Test completion of test.
(3) Inservice Inspection Program Within 6 months after five years of operation.
FOOTNOTFS 1.
A single submittal may be made for a multiple unit station. The submittal should combine those sections that are coc=on to all units at the station.
2.
This tabulation supplements the requirements of 20.h07 of 10 CFR Part 20.
3.
These reporting requirements apply only to Appendix A technical specifications.
1505 214 6-18