ML19260A078

Tech Spec Change Request 48 Supporting Licensee Request to Change App a of License DPR-50 Re Integrated Leakage Rate Tests Pretest Requirements.Certificate of Svc Encl

ML19260A078
Person / Time
Site:	Three Mile Island
Issue date:	02/18/1977
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A075	List: ML19260A074 ML19260A078
References
NUDOCS 7910290701
Download: ML19260A078 (5)

Text

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METROPOLITAII EDISON COMPAIIY JERSEY CENTRAL POWER & LIGHT COMPMIY MID PEmiSYLVANIA ELECTRIC COMPA'IY TPREE MILE ISLAND NUCLEAR STATION UNIT 1 Cperating License No. DPR-50 Docket !!o. 50-289 Technical Stecification Chance Recuest No. h8 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON CCMPANY 3 r, f Ey  : CILw .

Vice ?-esident d

Sworn and subscribed to me this day of Y , 1977.

f Notary Pub fc 1479 252 4910290 b

UNITED STATES OF AMERICA NUCLEAR REGULATORY CCIC4ISSION IN THE MA' ITER OF ,

DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. L8 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Comission and been served on the chiet' executives of Londonderry Township, Dauphin County, Penncylvania und Dauphin County, Pennsylvania by deposit in the Uni ted States mail, addrecsed as follows:

Mr. Weldon 3. Arehart Mr. Harry B. Reese, Jr.

Board of Supervisors of Board of County Comissioners Londonderry Township of Dauphin County R. D. 51, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Earrisburg, Pennsylvania 17120 METROPOLITAN EDISON C0!'PANY By /s / R . C . Arnold Vice President Dated: February 18, lo~7 1479 253

'Ihree Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DRP-50 Docket No. 50-289 Technical Snecification Change Recuest No. h8 The licensee requests that the attached revised pages replace pages h-30 and L-3h.a of the existing Technical Specifications, Appendix A.

Reasons for Pronosed Change The reason for this proposed change is to revise the text of Technical Specification h.h.l.l.h.a to make it consistent with 10CFR50, Appendix J as it relates to Integrated Leakage Rate Tests pretest requirements.

Cafety Analysin Justifying Change This proposed change doec not involve any unreviewed safety questions in that the intent of the existing Technical Specifications will not be modified with the revision. The specifications will still be in conformance with the Integrated Leakage Rate Tests pretest requirements of 10CFR50, Appendix J.

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h.h.l.l.h Conduct of Tests

2. After the preliminary containment inspection, no repairs or adjustments shall be made unless the inspection uncovers deterioration which could significantly affect the structural integrity of the containment or which could be increased in severity during the performance of the test.

b. The containment test pressure shall be allowed to stabilize for a period of not less than four hours prior to the start of a leakage rate test.

c. The test duration shall be at least 2h hours unless experience from at least two prior tests provides evidence of the adequacy of a shorter test duration.

d. Test accuracy shall be verified by supplementary means, such as measuring the quantity of air required to return to the starting point or by imposing a known leak rate to demonstrate the validity of meacurements.

e. Closure of containment isolation valves for tne purpose of the test shall be accomplished by the means provided for normal operation of the valves without preliminary exercises or adjustment.

f. Portions of the following fluid systems will be drained and vented to containment atmosphere prior to and during the integrated leakage rate tests:

1. Parts of the reactor coolant pressure boundary open directly to containment atmosphere under post acci$ent conditions. (become an extension of containment boundary)

2. Portions of closed systems inside containment that penetrate containment and rupture as a result of a loss of coolant accident.

I;0TE: Systems that are required to maintain the plant in a safe condition during the tests and systems that are normally filled with water and operating under post-accident conditions need not be vented. In addition, missile shielded lines outside the secondary shield will not be vented.

g. The fluid block system shall be deactivated prior to and during the integrated leakage rate tests,

h. All containment components normally pressurized by the penetration pressurization system shall be at atmospheric pressure during the integrated leakage rate tests.

s_,

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4.4.1 5 P.eacter Building Modifications Any major modification or replacement of components affecting the reactor building integrity shall be followed by either an integrated leak rate test or a icen1 leak test, as appropriate, and shall meet the acceptance criteria of h.h.l.1 5 and h.h.l.2 3, respectively.

Saces(l)

The reactor building is designed for an internal pressure of 55 psig and a stea=-air ~=ixture temperature of 231 F. Prior to initial operation, the containment vill be strength tested at 115 percent of design pressure and leak rate tested at the design pressure. The containment will also be leak tested prior to initial operation at approximately 50 percent of the design pressure.

These tests will verify that the leakege rate from reactor building pressurization satisfies the relationships given in the specifications.

The performance of periodic integrated and local leakage rate tests during the l Plant life provides a current assessment of potential leakage from the containment in case of an accident that would pressurice the interior of 'he containment.

In arder to provide a realiatic appraisal of the integrity of the contain=ent uncer accident conditions "as found" local leakage results =ust be documented for correction of the integrated leakage rate test results. Containment isolation valves are to be closed in the normal manner prior to local or integrated leakage rate tests.

The minimum test pressure of 27 5 psig for the periodic integrated leakage rate test is sufficiently high to provide an accurate =casurement of the Icakage rate and it duplicates the pre-operational leakage rate test at the raduced pressure. The specification provides a relationship for relating the measured leakage of air at the reduced pressure to the potential leakage of 55 poig. The minicus of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was specified for the integrated leakage rate test to help stabill:e conditions and thus improve accuracy and to better evcluate data scatter. The frequency of the periodic integrated leakage rate test is keyed to the refueling schedule for the reactor, because these tests can best be performed during refueling shutdowns.

The specified frequency of periodic integrated leakage rate tests is based on three major considerations. First is the low probability of leaks in the liner, because of conformance of the ec=plete containment to a C.10 percent leakage rate at 55 psig during pre-operational testing and the absence of any significant stresses in the liner during reactor operation. Second is the more frequent testing, at design pressure, of those portions of the containment envelope that are =ost likely to develop leaks during reactor operatien (;enetrations and icolation valves which are not continuously pressurized by the penetration pressurizatien syste= or are not fluid blocked post-accident by the fluid block system) and the low value (0.06 percent) of leakage that is specified as acceptable frc= penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that an important part of the structural integrity of the containment is maintained.

h-3ha 1479 256