ML19260A092

Tech Spec Change Request 51 Supporting Licensee Request to Change App a to License DPR-50 Re Methods of Containment Isolation During Refueling.Certificate of Svc Encl

ML19260A092
Person / Time
Site:	Three Mile Island
Issue date:	02/18/1977
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A085	List: ML19260A084 ML19260A092
References
NUDOCS 7910290712
Download: ML19260A092 (4)

Text

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METROPOLITA!i EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PEICISYLVA! IIA ELECTRIC CCMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DFR-50 Docket No. 50-289 Technical Scecification Change Recuest No. 51 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 By /s/ R. C. Arnold Vice President Sworn and subscribed to me this 18th day of February , 1977.

/s/ L. L. Lawyer Notary Public 1479 284 1793oggg 77 7 8

UNITED STATFE OF AMERICA NUCLEAR REGULATORY C0!GIISSION IN THE MA'I'IER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This ic to certify that a copy of Technical Specification Change Request No. 51 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 Commission and been served on 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 cf Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPAffl By /s/ R. C. Arnold Vice President Dated: Fe'oruary 18, 1977 1479 285

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Soecification Chance Reauest No. 51 The licensee requests that the attached revised page replace page 3-kh of the existing Technical Specifications.

Reason For Pronosed Change Technical Specification 3.8 7 requires that during fuel movements, " isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be closed." This specification does not allow consideration for other types of leakage control which would be a- reliable as a closed or operable automatic, containment isolation valve.

It is therefore requested that the present text of Technical Specification 3.8.7 be revised to read as the corresponding B&W Standard Technical Specification which gives more flexibility as to acceptable methods of containment isolation during refueling operations.

Safety Analysis Justifying Change This change does not involve any unreviewed safety questions in that the proposed containment isolation requirements provide more flexibility for containment isolation during refueling operations without sacrificing isola-tion effectiveness. The proposed requirements were extracted from the B&W Standard Technical Specifications and therefore meet the applicable 10 CFR 50 Appendix A General Design Criteria requirements.

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g 3.8 FUEL LOADING AND REFUELING Apolicability Applies to fuel loading and refueling operationc.

Objective To assure that fuel loading and refueling operations are performed in a responsible manner.

Specification 3.8.1 Radiation levels in the Reactor Building refueling area shall be monitored by RM-G6 and RM-GT. Radiation levels in the spent. fuel storage area shall be monitored by RM-G9 If any of these instru-ments become inoperable, portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect individuals involved in refueling operation, shall be used until the permanent instrumentation is returned to service.

3.8.2 Core suberitical neutron flux shall be continuously monitored by at least two neutron flux monitors, each wich continuous indication available, whenever core geomet ry is being changed. When core geometry ic not being changed, et least one neutron flux monitor shall be in service.

3.8.3 At least one decay heat removal pump and cooler shall be operable.

3.8.h During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shall be maintained at not less than that required for refueling shutdown.

3.8.5 Direct ecmmunications between the control room and the refueling personnel in the Reactor Building shall exist whenever changes in core geomatry are taking place.

3.8.6 During the handling of irradiated fuel in the Reactor Building at least one door on the personnel and emergency hatches shall be closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.

3.8.7 During the handling of irradiated fuel in the Reactor Building, each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:

1. Closed by an isolation valve, blind flange or manual valve, or

2. Be capable of being closed by an operable automatic containment purge and exhaust isolation valve.

3.8.8 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions co that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.

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