ML19291B582

Tech Spec Change 68 to DPR-50,App a Re Radioactive Matls Sources & Surveillance,Reporting Requirements & Record Retention.Certificate of Svc Encl

ML19291B582
Person / Time
Site:	Three Mile Island
Issue date:	01/09/1978
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19291B581	List: ML19291B580 ML19291B582
References
NUDOCS 7911080617
Download: ML19291B582 (8)

Text

METRCFCLITAN DISC COMPA'IY JERSEY CE:iTPJLL FO'JER & LIGHT CCIGA'iY A:TD PEN!!SYLL IIA ELEC"*P.IC COMPANY THREE MILE ISLAND IIUCLEAR STATION UNIT 1 Cperating License No. DFR-50 Docket No. 50-269 Technical Specification Change Beauest No. 63 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating Licer. a No. DFR-50 for Three Mile Island :Iuclear Station Unit 1. As a part of this request, preposed replacement pages for Appendix A are also included.

METROFCLITA'I DISCN CCMPANY By /

Vice President h

Sworn and subscribed to me this i day of 1973.

G /

Ow o WW y a . .

Notary Public /

r..r nv ount ;

Rei: : ,*:.- P2 Yf COCS 33TA E C.51 N0v 13.1373 1583 318 1911ogog,,

U'iITD STATES OF AMERICA

iUCLEAR REGULATORY CClo!ISSION I:I '"HE MATTER OF DCCKET II0. 50-289 LICE:ISE lio. DPR-50 ME"'ECPOLITMi EDISCN CCMPMtY This is to certify that a copy of Technical Specification Change Request lo. 68 to Appendix A of the Operating License for Three Mile Island

iuclear Station Unit 1, has, on the date given belev, been filed with the U. S. :Tuclear Regulatory Cc==issicn and been served en the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States = ail, addressed as follows:

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

Board of Supervisors of Board of County Cc=missicners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Fennsylvania 17057 Harrisburg, Pennsylvania 17120 METECPCLITA'I DIS 0 i COMPMIY Ey ,- 7

/ ~ VIce President Dated: 5,-,,, , y o ,o-a 1583 319

>v .

Three Mile Island nuclear Station, Unit 1 Operating License No. DpR-50 Docket No. 50-289 Technical S ecification Chance Recuest #68 The licensee requests that the attached changed pages replace pages 3 h6, L-56, 6-18, and 6-19.

Reasons for Chance Recuest This proposed change is an URO revision of our Technical Specification Change Request No. 21. The new limits are = ore restrictive than vere previously used.

Safety Analysis Justifying Chance Pecuest There is no new equipment or procedure such that the probability of occurrence or the consequences of an accident or =alfunction of equip =ent i=portant to safety previously evaluated in the safety analysis report is not increased.

There is no change to any equipment or procedures such that the possibility of an accident or =alfunction of a different type than any evaluated previously in the safety analysis report is not created. The margin of safety defined in the basis for any technical specification has not been reduced.

1583 320

39  ?.ADI0 ACTIVE MATERIALS This section has been included in the Environ = ental Technical Specifications.

3.10 MISCELLwEOUS RADI0 ACTIVE MATERIALS SOUP.CES Anulicability Appliec to byproduct, source, and special nuclear radioactive =aterial sources.

Objective To assure that leakage from byproduct, source, and special nuclear radioactive material sources does not exceed allovable limits.

Specification 3 10.1 The source leakage test perforced pursuant to Specification h.13 shall be capable of detecting the presence of 0.005 pCi of radioactive

=aterial on the test sa=ple. :f the test reveals the presence of 0.005 pCi or more of re=ovable centamination, it shall immediately be withdrawn frem use, decenta=inated, and repaired, or be disposed of in accordance with Cc==issica regulations. Sealed sources are exempt from such leak tests when the source contains 100 pCi or less of beta and/or ga=ma emitting =aterial or 5 pCi or less of alpha l emitting material.

3.10.2 A complete inventory of licensed radioactive =aterials in possescien shall be maintained current at all times.

Bases The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10CFR 70.39(c) limits for plutonium.

This limitation vill ensure that leakage from byproduct, source, and special nuclear material sources vill not exceed allevable intake values.

Pages 3-hT to 3-5h deleted

} )b 3-h6

.o h.13 RADICACTrlZ MA'ERIALS SCURCES SURVEILIE!CE Apolicability Applies to leakage testing of byproduct, source, and special nuclear radioactive material sources.

Objective To assure that leakage from byproduct, source, and special nuclear radioactive

=aterial sources does not exceed allevable li=its.

Specification Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Consission or any agreement State, as follows :

1. Each sealed source, except startup sources previously subject to core l flux, containing radioactive caterial, other than Rydrogen 3, with a half-life greater than 30 days and in any form, other than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.

2. The periodic leak test required does not apply to sealed sources that are stored and not being used. The sources accepted frc= this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer or indicating that a test has been made within six months prior tc the transfer, sealed scurces shall not be put into use until tested.

3 Each sealed startup source shall be tested within 31 days prior to being subjected to core flux and following repair or naintenance to the source.

,_, 1583 322

~6 9 REPORTI!G REOUIRE E ITS (cent'd) 6.9 3 Unique Reporting Requirements A. A section in the Annual Exposure Report shall include infor=ation on aircraft movements at the Harrisburg International Airport. This additional infor ation shall include the total nu=ber of aircraft =ovements. (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-conth period. Also included shall be the total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager.

B. Special reports shall be submitted to the Director of the Regulatory Operatiens Regional Office within the ti=e period specified for each report. These reports shall be submitted covering the activities identified belev:

Tests Submittal Cates (1) Containment Stru:tural Integrity Test (a) Tendon Surveillance Progra: Within 3 months after performance of surveillance program.

(_b ) Ring Girder Inspection Within 3 months Progrs: after performance of each inspection.

(2) Containment Integrated Leak Within 6 months Rate Test after ec=pletien of test.

(3) Inservice Inspection Program within 6 months after five years of operation.

(h) Radioactive Sealed Source Leakage Within 90 days after Test Revealing the Presence of ecmpletion of test.

> 0.005 microcuries of Re=cvable Contamination.

FOOTNCTES

1. These reporting require =ents apply only to Appendix A technical speci-fications.

2. A single submittal may be made for a multiple unit station. The sub-mittal should ecmbine those sections that are common te all units at the station.

1583 323 6-18

3. The term " forced reduction in pcver" is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend. Note that routine preventive maintenance, surveillance and calibration activities requiring power reductions are not covered by this section.

h. The term " forced outage" is nor ally defined in the electric power industry as the occurrence of a ecmponent failure or other condition which requires that the unit be removed from service for corrective action i==ediately or up to and including the very next weekend.

5 This tabulation supplements the requirements of 520.h07 of 10 CFR Part 20.

1583 324 6-18A

6.10 RECORD RETENTICN 6.10.1 The following records shall be retained for at least five years:

a. Records of normal station operation including power levels and periods of operation at each power levels.

b. Records of principal maintenance activities, including inspection, reports, substitution, or replacement of principal ite=s of equipment pertaining to nuclear safety.

c. Records of reportable occurrences and safety limits exceeded.

d. Records of periodic checks, tests, and calibration.

e. Records of reactor physics tests and other special tests pertaining to nuclear safety.

f. Changes to nuclear safety related operating procedures.

g. Records of solid radicactive shi; ents.

h. Test results, in units of microcuries, for leak tests perfor=ed on licensed sealed sources.

i. Results of annual physical inventcry verifying accountability of licensed sources on record.

J. Control Room Log Book.

k. Shift Fore =an's Log.

6.10.2 The following records shall be retained for the duration of Operating License DPR-50:

a. Record and drawing changes reflecting facility design modifications made to syste=s and equip =ent described in the Final Safety Analysis Report,

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Routine station radiation surveys and =enitoring records.

d. Records of radiation exposure history and radiation exposure status of personnel, including all contractors and station visitors who enter radioactive material area.

e. Records of radioactive liquid and gaseous vastes released to the environment, and records of environnental =cnitoring surveys,

f. Records of transient or operational cycles for those nuclear safety related facility ecmponents designed for a limited number of transient or cycles as defined in the Final Safety Analysis Report.

1583 325 6-19