ML19291B578

Tech Spec Change Request 67 to DPR-50,App a Re Deletion of Unnecessary Items from Annual Operating Rept.Certificate of Svc Encl

ML19291B578
Person / Time
Site:	Three Mile Island
Issue date:	01/13/1978
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19291B577	List: ML19291B576 ML19291B578
References
NUDOCS 7911080614
Download: ML19291B578 (6)

Text

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METROPOLITAN EDISON CCMPANY JERSEY CENTRAL PCWER & LIGHT CCMPANY A'iD PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLA'ID NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chance Recuest No. 67 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.

METROPOLITMI EDISCN COMPMiY

,57 I Vice President Sworn and subscribed to ::e this f3 day of , 1978 a /

Notary Publi f r.c.- , t .:;

Rn q.Er-s auny,pi D Q:m.ss.on baras xv.13,1;;3 1583 308 79110808/f

UNITED STA23 CF A'4 ERICA iUCLEAR REGULATCRY CC:"4IS3IO:i I:I THE MA'I""ER OF DOCKET NO. 50-2S9 LICENSE NO. DFR-50 METROPOLIT%I EDISCN CCtGANY This is to certify that a copy of Technical Specification Change Request

io. 67 to Appendix A of the Operating License for Three Mile Island

Tuclear Statien Unit 1, has, en the date given belov, been filed with the U. S. Nuclear Regulatory Cecnission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by depesit in the United States mail, addressed as follevs:

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

Board of Supervisors of Beard of County Cec =issicners Lcndenderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin Ccunty Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITXI EDISCN COMPANY

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By, . '

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/ Vice President Dated: Jermrt 17.1078 1583 309

Three Mile Ialand Nuclear Statien, Unit 1 Operating License No. DPR-50 Locket No. 50-289 Technical Specification Chsnee Retuest #67 The licensee requests that the attached changed pages replace pages 6-12, 6-e 13, 6-lk, and 6-18 of the existing Technical Specifications.

Peasons for Change Recuest The Cc==ission has concluded that =uch of the infer =ation new included in the Annual Operating Report (ACR) can be deleted and still =eet the desired objectives.

Therefore, the Cc==ission requesta that the require =ents for the AOR be deleted frc= the Technical Specifications.

Safety Analysis Justifyin the Chinze This change request deletes the reporting require =ents for the AOR and includes a section for the Monthly Operating Report. All required data concerning the operation of the unit vill be supplied in the Menthly C;erating Report. The change does not affect the operatica or equipment of Unit 1. Therefore,(i) the probability of occurrence or the consequences of an accident or =alfunction of equipment important to safety previously evaluated in the safety analysis report is not increased; (ii) the possibility of an accident or =alfunction of a different type than any evaluated previcusly in the safety analysis report is not created; (iii) the margin of safety defined in the basis of any technical specification is not reduced. ,

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.6.9 REPCRT!:IG RECUIRMITL In addition to the applicable reporting requirements of Title 10. Code of Federal *legulations, the following identified reports shall be sub=itted to the Director of the appropriate Regional Office of Inspection and Enforce =ent unless otherwise noted.

6.9 1 Routine Reports A. Startuo Recort. A su==ary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been =anufactured by a different fuel supplier, and (h) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditiens or characteristics obtained during the test progrs= and a ec=parison of these values with design predictions and specifications. Any corrective actions that vere required to obtain satisfactory operation shall also te described. Any additional specific details required in license ccnditions based on other co==ittents shall be included in this report.

Startup reports shall be sub=itted within (1) 90 days folleving ec=pletien of the startup test progra=, (2) 90 days folleving resu=ptien or ec =ence=ent of ec==ercial power operation, or (3) ? =enths fc11cving initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, ec=pletion of startup test progrs=, and resu=ption or cc==ence=ent of co==ercial power operaticn), supple =entary reports shall be sub=itted at least every three =onths until all three eventu have been ec=pleted.

B. Annual Recorts. ~/ Annual reporta covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be sut=itted prior to March 1 of the year following initial criticality. Reports required l on an annual basis shall include: j

1. A tabulation on an annual basis of the number of 'I station, utility and other persennel (including contractors) receiving exposures greater than 100 nre=/yr and their associated =an re: exposure ac-cording to work and job functions , 2/ (e.g. , reactor  ;

operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe

=aintenance), vaste processing, and refueling). The dose assign =ent to various duty functions may be esti=ates based on pocket dosimeter, TLD, or film badge measure =ents. S=all exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 805 of the total whole body dose received frc= external sources shall be assigned to specific =ajor work functions.

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2. The following information on aircraft movements at l the Harrisburg International Airport:

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a. The total number of aircraft movements (takeoffs and landings) at the Harrisburg International Airport for the previous tvelve-month period.

b. The total nu=ber of movements of aircraft larger than 200,000 pounds, based on a current per- ,

centage estimate provided by the airport manager.  ;

C. Menthly Oterstine Retort. Routine reports of operating statistica and shutdown experience shall be subsitted en a conthly basis to the Office of Inspection and Enforce-ment , U.S. Nuclear Regulatery Ccesission, Washington, D.C.

20555, with a copy to the Regional Office, no later than I the fifteenth (15th) day of each =enth following the  !

calendar =cnth covered by the repert.

6.9.2 Reportable Occurrences / i Reportable Occurrences, including corrective actions and =casures to prevent recurrence, shall te reported to the NRC. Supplemental reports say be required to fully describe final resolution of an occurrence. In case of ccrrected or supplemental reports, reference shall be made to the original report date.

Delete Page 6-lk 6- 3 1583 312

6.9 REPORTIUG RE^UIRDETTS (cont'd) 6.9 3 Unique Reporting Require =ents 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 (a) Tendon Surveillance Fregra Within 3 conths after perfo. ance of surveillance progrk3.

(b) Ring Girder Inspectica Within 3 months Progra= after perfor:ance each inspection.

(2) Containment Integrated leak Within 6 months Rate Test after completion of test.

(3) Inservice Inspe: tion Program Within 6 months after five years of operation.

FOOT::0 TIS

1. A single sutsittal ca/ te made for a multiple unit station. The sub-mittal should combine those sections that are cetron to all units at the station.

2. This tabulation supplements the requirements of $20.L07 of 10 CRF Part 20.

3. These reporting requirements apply only to Appendix A technical speci-fications.

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