ML19206A758

License DPR-73

ML19206A758
Person / Time
Site:	Crane  (DPR-73)
Issue date:	02/08/1978
From:	Boyd R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19206A757	List: ML19206A756 ML19206A758 ML19206A759
References
TM-0167, TM-167, NUDOCS 7904210163
Download: ML19206A758 (15)

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Tne ;;uclear Regulatcry Cc=ision (tne Commission) having found tnat:

A.

The applicaticn for license filed by Metrccolitan Eaison Cccpany, Jersey Central Pcwer i Licnt Comoan"t, and Pennsylvania Electric ecmcan' (tne licensees) ccm.olies with t.ne stancarcs anc rec.uire-ments of the Atomic Enerc.v. Act of 1954, as a: ended (tne Act),

anc tne Cc=issicn's rules and regulaticns set forth in 10 C.22 Chapter I, and all recuired notifications to other agencies cr codies have teen duly made; B.

Construction of the Tnree Mile Island :;uclear Station, Unit 2 ( ne facility), has been substantially comoleted in confccmity witn Ccnstruction Permit So. CPPR-66 anc the applicaticn, as a endea, tne erovisicns at tne e,.ct and tne ru.,es and regulations of tne wcruission;

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Ine licensees have satisfied.ne applicabla cccvisions of 1.; CFR Part 140, " Financial Protection Requirements and Indemity Agreements", of tne Ccccission's regulaticns:

H.

The issuance of this Operating license will not be inimical to tne.:c=cn cefense anc. secur].ty or to tne nealtn and sar ty or.

e the puolic; I.

After weigning the anvironmental, econctic, technical, and otner benefits of tne facility against environmental and other costs and considering availacle alternatives, the issuance of Facility Operating License No. CPR-73 sucject to the conditions for protection of tne envircrnent set for-h herein is in accordance witn Apcendix D to 10 CFR Part 50 (currently known as 10 CFR Part 51) of One Ccanission's regulations and all applicable recuirements have been satisfied; and J.

Tne receipt, possessicn, and use of source, bycroduct and soecial nuclear material as authoriced cy this license will be in accordance with the Concission's regula.:icns in 10 CFR Part 30, 40, ard 70, including 10 CFR Sections 30.33, 40.32, 70.23 and 70.31.

2.

Pursuant to the Initial Cecision of the Atomic Safety and Licensing Board dated Deceder 19, 1977, Facility Operating License.!O. OPR-73 is nerebv. issued to I!etrooolitan Ediscn Cccpany, Jersev. Central Power

& Licht Coac.any, and Pennsylvania Electric Cc=cany to read as follws:

A.

This 12 cense applies to the Three Mile Island Nuclear Station, Unit 2, a pressuri::ed water nuclear reactor and associated equipment (the facility), cwned by the Metroc.olitan Edisen Comc.any, Jersey Central Pcwer & Lic.ht Comc.any, and Pennsylvania Electric Comc.any, and ccerated cv the Metroc.olitan Ediscn Comc.anv.. The faciliev. is locatec cn

.Inree Mile Island in the Suscuehanna River, in Lcndenderry Townsnip, u

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as supplemented and a ended (.'cendments 17 enrougn 62) anc tr.e Envircr ental Report as supple:4nted and amended.

3.

Subject to the conditions and recuirements incorpcratec herein, -he Ccanission nereby licenses:

(1) tietropolitan Ediscn Cc=any, pursuant to Sectica 103 of ne C,

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. (2) Ine licensees to possess the facility at the designated location in Dauphin County, Pennsylvania, in accordance vita tne peccedures and limitations set forth in tnis license; (3) 'letrcpolitan Edison Ccmpany, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance witn the limitations for storage and amounts required for reactor cperation, as described in the Iinal Safety Analysis Report, as supplemented and amended; (4) Metrcyclitan Edison Comcany, pursuant to tne Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byprocuct, source and special nuclear material as sealed neutrcn sources for reactor startup, sealed sources for reactor instrumentation and radiation acnitoring ecuic.ent calibration, and as fission detectors in amounts as required; (5) Metrcpolitan Edison Comcany, pursuant to tne Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as rec.uired an"1 o.veroduct, scurce or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Metropolitan Edison Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, ' cut not separate, sucn cyproduct and special nuclear materials as may be produced cy the Operation of the facility:

C, Tnis license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 7-o= t 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicacle provisions of the Act and to the rules, regulaticns, and orders of the Comcission now or hereaf ter in effect; and is sucject to the adcitional conditions specified or incorporated belo..-

(1).'!axi:m;m Power Level Metropolitan Edison Ccc any is autnorized to c.erate the f acilit, at a core power level of 2772 regawatts thermal. Prior to attaining nat pcwer level, Metrccolitan Edison Ccccany snall comely wi n the apptcgriate conditions identified in Paragrapn (2) celos and n _e_ co.. = ~ 4 -ru= ' - s s

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--n identified in Attacnment 2 to this license in the sequence spe:ified.

Attacarent 2 is an integral part of nis license.

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(2) T_ecnnical Specifications Ine Tecnnical Specifications contained in Appendices A and 3 attacned hereto are hereby incorporated in tnis license.

Metrccclitan Edison Cccpany shall operate the facility in accordance with the Technical Specifications, except where speciFically exempted below.

(3) Additional Ccnditions Tne matters specified in the follcwing conditions shall ce completed to tne satisfaction of tne Commission witnin the stated time periods following the issuance of the license or witnin the operational restrictions indicated. Tne reccval of tnese conditions shall be made cy an amendment to the license supported by a favoracle evaluation by the Ccamission:

a.

Metropolitan Edison Company shall not Operate the reactcr in operational Modes 1 and 2 with less than three reactor coclant pumps in operation.

Prior to initial entry into Mode 4, Metroc_olitan Ediscn Comcany snali cc tne follcwing:

b.

Submit propcsed allcwaale voltage and frequency variations for a 500-ki10 watt lead rejectica frca tne emergency diesel generators for inclusion in Tecnnical Specification 4.3.1.1.2.c.3.

Prior to initial entry into Mcde 2, '!etrocolitar. Edison Comnany snall co tne follcwing:

c.

Provide for Commission review appropriate dccumentation of

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cooling becster pumps until August 7,1973. Ccntingent on approval of inat documentaticn, the requirement of 3000 gallens per minute ficw for each pump in Technical Specification 4.6.2.3.b, Centainment Cccling Systems, is waived and a requirement of 2100 gallons per minute snall be met until that date.

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Provide documentation for Cc mission review regarding

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Provide analyses for Cc mission review :cvering the containment temperature and pressure respcase foi.lcwing a postulated main steam line break accident and tne respense of safety-related equipment in containment to the resultant enviren=ent.

Prior to August 3,1978, ".e:rcoolitan Edison Comcany snall co tne follcwing:

f.

Provide the f.,11 swing information for eacn Reactor

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-a instrumentation cnannel for incorporation in ene Tecnnical Scecifications:

1.

Tne technical specification trip setpoint value, 2.

The technical specification allowable value (i.e.

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3.

Tne instrument drift assumed to occur during the interval oetween technical specification surveillance tests, 4.

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instrument calibration error, instrument drif t, instr rent error, etc. ), and 5.

Tne minirum margin between the technical specificatica trip setpcint and tne trip value assumed in the accident ana.,ysis.

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Provide a second level of voltac.e.crotection for tne cnsite power system.

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w-itecs (1) and ( 2 ) above, including test requirements to demonstrate the full functional oceracility and independence of tne ensite pcuer sources.

h.

Install an environmental temperature acnitorinv sv. stem to assure that the envircnment at the location of Class IE equipment in buildings outside containment is maintained within tne temperature range for wnich tne ecuirment is designed to operate.

1.

Submit approcriate descriptions and analyses and mcdify the secondary (main steam and feedwater) systems so that the consequences of a spcntaneous break anywhere in a secondary system line will be mitigated only by safety grade equipment, with ncn-safety grade equipment permitted to serve as a backup for the assumed single f ailure of safety grade equicc.ent.

.rce anose pcrtions of the seccndary systems wnere a break mi-ht be caused by a seismic event, Metropolitan Edison Cc=c. anv. shall mcdify the systems so that accident consec.uences will be mitigated only by seismic Category I components after assuming single f ailure in any seismic Category I cc=ponent.

j. Suirit and i. plement a respcnse time testing program for the protection systems.

k.

Modify the reactor coolant pressure boundary overpressure protection system to satisfy Commission requir'ments regarding credit for operator action, single failure criteria,

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Revise the fire hazards analysis to excluce the assumption that cacles inside conduits will not ce damaged oy a.

desic.n,, asis fire and L. ecoose anv. rec.uired mcc,lu,ications.

v 4.

Complete an analysis deconstrating the cacaciity of sarely shutting down the plant independent of ca'cting and equipment in the cacle spreading roc: and prcpose any ocuirea acci.,icaticns.

By January 15, 1979 5.

Provide fully developed and documented fire fignting

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By Startur Following the First Regularly Screduled Refueling Outac.e_

6.

Cccplete acdifications necessary to acnieve the capacility of safelv shutting down the clant indecendent of caclinc anc eculpment in tne cable spresc..ing roca, anc acc eitner of the following:

a.

a manually operated fixed water system in tne caole spreading room, or c.

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For all fire dccrs, provide electrical fire dccr supervisicn with time-delayed alat=s in a constantly manned area, or lcck the dccrs clcsed, or provide acceptable hold-open

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y aa to Cperaticna. Mode 6 (initial fuel 10adina), and cav. subsec.uentiv..croceed to Cperational Mode 5 ( cold shutd wn).

3.

The following items must ce cc. cleted prior to proceeding to Cperaticnal ticde 4 (hot shutdown):

1.

A.c.reval of the followin"3 must be obtained:

TP 160/3 R2 actor Building F.mergency Cccling Functional Test Results TP.3 60/4 Reactor Buildine Hydrccen Control Functional Test Results TP 160/6 Peactor Building Purge Su' ply and Exhaust Functional Test R'esults IP 210/12 ::uclear Chemical Addition System functional Test Results TP 267/4 :iuclear Service Clcsed Ccclin-System F;nctional Test Results e

TP 350/2 Cc=puter Software 7erification TP 350/10 Cc=puter Inputs 7erification

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. TP 273/3 Emergency Feedsater Functional Test results TP 301/2 NI Detector Cabling anc Respcnse Test results TP 230/3, 231/3, 232/1 Padwaste Disposal Functional Test results TP360/lA, B, C, Radiation Mcnitoring System Functicnal Test results TP 370/1 Heat Tracing Functional Test results TP 600/14, 29 Piping Expansion Functional Test results SP-2 Filter Efficiency Test results TP 200/2 Survillance and Fadiation Specimen Handling TP 173/2 Auxiliary Building Heating and Ventilation Test results TP 177/2 Fuel Handling Building Heating and Ventilation Test results.

2.

Install redundant non-nuclear instrumentation indications for post accident shutdown monitoring.

3.

Cceplete environmental /administrat.ive procedures.

4.

Complete Significant Inccmolete Work List Items wnich affect cperability of the following systems:

Control Building Area Ventilaticn Centrol Suilding ventilation Control acd Drive System Fuel Handling Building Ventilation Heat Traci:33 Hydrogen System Incore Mcnitoring Syste1 Instrument Air System Nuclear Instru entaticn Radiaticn Mcniteting System

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'adwaste Disposal - Gas, Solid, Liquid Reactor Protection System Spent Fuel Cooling System 5.

Modify the hydrogen charging line to the Makeup Tank to include redundant safety grade hydrogen isolation valves, and revise their cperating procedures to require apcropriate Makeup Tank charging levels and pressures. In addition, the hich pressure injection pumps shall be aligned so that one pumo functions as a spare, and that no.mcre than two pumps will, under accident ccnditions, take suction from the Makeup Tank.

D.

The following items must be completed prior to initial entry into Cperational Mcde 1 (cower cperation):

1.

Cptimize voltage levels at the safety-related buses for tne full and mini:mm lead conditions excected throughout the anticipated range of voltage variations of the offsite pcwer source by adjustment of the voltage tap settings of the intervening transformers. Prior to initial entry into Mode 1, this cetimi-zation shall be wrified by actual measurement and by correlation of measured values with analytical results, and a description of the methed for performing the verification and documentation establishing dat 2e verification

• has ceen accoglished shall be provided.

2.

Modify the cc: pressed air starting system for each diesel generator so that the system, centaining two independenc and redurdant trains, is capable of providing 10 starts wiecut recharging from the diesel generator compressors.

3.

Modify the intermediate closed cooling water heat exchangers so that their design conforms with seismic Category I regaire-ments. Revise the Final Safety Analysis Report accordingly.

E.

The follcwing items must be cogleted prior to August 8,1978:

1.

Install new i=ellers in each of the reactor building emergency cooling booster pumps and demonstrate a flow of 3000 gallons per minute each. Ucen completion of all the tests, the system shall be returned to the configuration described in the Final Safety Analysis Report. When these tests are cecclete, the waiver of de ficw requirements of Technical Specificaticn 4.6.2.3.b, Centainment Cooling Systems, g:: anted acove shall be wi2 drawn, and the requirements of dat Technical Specification shall be in force.

c 4.. -9 59 u

4

' F.

The following must be completed prior to startup follcwing the first regularly seneduled refueling outage:

1.

Provide redund'.nt autcmatic safety grade Makeup Tank isolation valves (yU-V-12) actuated by an Engineered Safety Features signal.

2.

Replace the chcrcoal in the filters in the folicwing systems so that the recuirements of the indicated Appendix A Technical Specificaticns will be met.

System Technical Srecification Hydrogen Purge Air Cleanup 4.6.4.3.b.2 and 4.6.4.3.d Centrol Rocm Emergency Air Cleanup 4.7.7.1.c.2 and 4.7.7.1.d Fuel Handling Building Air Cleanup 4.9.12.b.2 and 4.9.12.c Pending such charcoal repla-ament, Metrepclitan Edison Company snall be exempted from cc:mliance with the above Technical S,oecifications.

G.

The folicwing must be completed by the time indicated to i:mrove the capability of the fire protection system:

By March 1, ;978 1.

Verify by Underwriters Laboratory certificate or equivalent, the tire rating of fire doors, frames, and hardware as corrensurate with the barrier in which they are located.

Bv Initial Entry into Mode 2 2.

Relocate existing fire detectors in the centrol rocm.

3.

In the control rocm kitchen area, provide a grease filter over the range and an additional Class a certable extinguisher.

and remove a wooden cabinet.

4.

Prohibit sreking in the following fire areas:

Fuel Handling Building (FA-007)

Auxiliary Suildding (FA-009)

River Water Pump House (FA-020)

Ccntrol Building (FA-033)

Carle Room (FA-045)

Service Building and Control Building Area (FA-047)

H&V CCC'" AND CABLE TRAY AEA (FA-041)

Diesel Oil Storage Area (FA-032)

Fuel Handling Building Cil Drum Storage Area (FA-008)

, veo u

s t By May 1, 1973 5.

Develop precedures for the semi-annual inspection of outdect fire hydrants, and complete the initial inspection.

6.

Provide fire fighters protective clotning for at least eight men.

7.

Implement. appropriate modifications to prevent overflow of ccchustible liquid into the diesel rocms via ventilation cpenings.

Sv July 31, 1973 8.

Provide three fire fighter tyce smoke ejectors with a corbined capability of 15,000 cubic feet per minute.

9.

Provide additional fixed sealed-beam erergency lights to facilitate ercrgency operations at remote shutdown panels and facilities, and provide a minirum five-hour battery power supoly for each erergency light.

By Startuo Following the First Recularly Scheduled Refueling Cutage

10. Modify manual hose static., to conform to the requirements of National Fire Protection Association 14, perform hose stretch tests, and provide any necessary additional hose stations to reach any location in safety-related areas and areas containing major fire hazards with at least one effective hose streart.

11.

Seal the opening in the ccrancn wall cetween the diesel rocca at the air intake area with a three-hour concrete masonry structure. Add ramced curbs at the decr cpenings in that wall.

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