ML19210B416

Tech Spec Change Request 65 to DPR-50,App A,Re Mods to Reactor Bldg Personnel & Emergency Hatches.Certificate of Svc Encl

ML19210B416
Person / Time
Site:	Three Mile Island
Issue date:	10/28/1977
From:	Herbein J METROPOLITAN EDISON CO.
To:
References
NUDOCS 7911080630
Download: ML19210B416 (4)

Text

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IF:'ROPOLITAN EDISO:I CCMPATf JERSEY CE'ITRAL POWER & LIGHT CCMPE!Y KID PE'INSYLVANIA ELECTRIC COMPEIY THREE ICLE ISLAIID NUCIS.AR STATIO:s U'iIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chance Recuest No. 65 This Technical Specificatica Change Request is sub=itted 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.

I M OPOLITA'I EDISON CCMPAIrf

/ s I-/ Vice i0 President &

Sworn and subscribed to =e this 28th day of October , 1977, o Nl 5 aw Notary Public RITA M powggg NC*2ry Putlic. W:Menterg Twp. Berks Ca 4, Ccem:ss.on Ecres Se;:areer 30,19N T Cs, uv Cb \U

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UNITED STATES OF AERICA NUCLEAR REGULATORY CCr4ISSICN IN THE MATTER OF DCCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISCN CCIPANY This is to certify that a copy of Technical Specification Change Request No. 65 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 Cc= mission and been served en the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

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

Board of Supervisors of Board of County Cc==issioners Londonderry Township af Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 ETECPOLITAN EDISCH COMPANY l

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/ Vice President Dated: October 28, 1977 m

Ihree Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 Technical Seecification Chance Recuest No. 65 The licensee requests that the attached change page replace page 1-5 of lhe existing Technical Specification, Appendix A.

Reasons for Change Recuest This change has been proposed to clarify Section 1 7 allowing a modification to be performed on the Reactor Building personnel hatch and emergency hatch.

This modification vill increase the effectiveness of the door interlock.

Safety Analysis Justifying Chance The possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report is not created in that, maintenance is permitted for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> on the personnel hatch and the emergency hatch according to T.S. Section 4.h.1.2.hb in the event corrective action is required by local leak rate test results.

The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report is not increased in that the other door vill be leak tested and meet the local leak rate criteria for door seals prior to performing any maintenance.

The margin of safety deff ned in the bases for any technical specification is not reduced in that this change vill clarify Section 1 7 to allow a h8 hour maintenance time for preventive or corrective maintenance other Jum that corrective maintenance required by local leak rate test results

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1.6 POWER DISTRIBUTION 1.6.1 QUADRAUT PC'4ER TILT Quadrant power tilt is defined by the following equation and is expressed in percent.

100 Power in any core quadrant Average power of all quadrants -1 The quadrant tilt limits are stated in Specification 3.5 2.h.

1.6.2 REACTOR PCWF.,R IMEALANCE Reactor power imbalance is the power in the top half of the core minus the power in the bottom half of the core expressed as a percentage of rated power. Imbalance is monitored continuously by the RPS using input from the power range channels. Imbalance limits are defined in Specification 2.1 and imbalance setpoints are defined in Specification 2.3 17 CONTAIDENT INTEGRITY Containment integrity exists when the following conditions are satisfied:

a. The equipment hatch is closed and sealed and both doors of the personnel hatch and emergency hatch are closed and sealed except as in "b" or "f" below, p

b. At least one door on each of the personnel hatch and emergency hatch is closed and sealed during refueling or personnel passage through these hatches.

c. All nonautomatic containment isolation valves and blind flanges are closed as required by the " Containment Integrity Check List" attached to the operating procedure " Containment Integrity and Access Limits".

d. All automatic containment isolation valves are operable or locked closed,

u. The containment leakage determined at the last testing interval satisfies Specification h.h.1.

f. Maintenance which requires that one door be open is permitted on the personnel hatch or emergency hatch for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the other dooi of the hatch is leak tested and meets the local leak rate criteria for door seals prior to maintenance.

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POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 TELEPHONE 215 - 929-3601 October 28, 1977 OQL 1h66 I-A r..s n. ,::

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Director of Nuclear Reactor Regulaticn f  ?,b /) 1977 'L -

Attn: R. W. Reid, Chief N;' D s D3 'O Operating Reactors Branch No. k ;d MW '

U.S. Nuclear Regulatory Com:aission A Washington, D.C. 20555 \'6,V<

Dear Sir:

N' Three Mile Island Nuclear Station, Unit 1 (D1I-1)

Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Request No. 65 Enclosed are three signed originalc (sixty conformed copies sent separately) of Technical Specification Change Request No. 65 requesting amentaent to Appendix A of Operating License No. DFR-50.

Also enclosed is one signed copy of Certificate of Service for proposed Technical Specification Change Request No. 65 to the chief executives of the township and county in which the facility is located.

. cerely

,J. G./'

/ j Herbein

/ / Vice President

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Enclosures:

1) Technical Specification Change Request No. 65

2) Certificate of Service for Technical Specification Change Request No. 65

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