ML19270H569

Forwards Draft Tech Spec Change Request 36 to DPR-50.Final Submittal Expected by 760707

ML19270H569
Person / Time
Site:	Crane
Issue date:	06/18/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:	Reid R Office of Nuclear Reactor Regulation
Shared Package
ML19270H570	List: ML19270H569 ML19270H572
References
GQL-0891, GQL-891, NUDOCS 7911110181
Download: ML19270H569 (2)

Text

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I tJ AC ronu 195 e U.s. NUCLE AR REGUL ATORY " MMISSION DOCKET NUMBE A 50-289

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NRC DISTRIGUTION rom PART 50 DOCKET MATERI AL FNOM:

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Metropolitan Edison Company 6/13/76 Mr. R. W. Reid Reading, Pa. -

04Te neceiveo Mr. R. C. Arnold 6/21/76 N ETTER ONoTonizeo PRCP INPUT FO AM NUMBER OF COPIES RECEIVEC peniciN AL K Nc L4ssi,,s o Ocoev One signed cescairTioN snetoSUne,,..

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Furnishing a draf t copy of tech spec change request No. 36 concerning the elimination of the reactor interval vent valve flow penalty & the incorporation of correct. fuel densification penalty.

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Three Mile Island #1

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Dear Mr. Reid:

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

Dceket No. 50-289 Operating License No. DPR-50' Enclesed, for your information, is a draft copy of Technical Specification Change Request No. 36, which is now under internal reviev. This change request addresses elimination of the reacter internal ent valve ficv penalty and the incorporatien cf correct fuel densifica'. ion penalty.

21us far, internal review has indicated that niner changes may be necessary.

However, we anticipate final submittal of this change request, essentially as enclosed, by July 7,1976.

If you have any further questions regarding thic matter, please centact me.

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TARLE OF CO:ITE:iTS Section Page k.6 E!ERGE' ICY PO'JER SYSTEf PESIODIC TFSTS h-h6 4.7 REACTOR CONTROL ROD SYSTDI TESTS h-h8 h.7 1 CONTROL ROD DRIVE SYSTEM FU iCTIO:!AL TESTS h-48 h.7 2 CONTROL RCD PRCCRAM VERIFICATION h-50 4.8 MAIN STEX4 ISOLATION VALVES h-51 h.9 a'ERGE::CY FEE 74ATER FWPS PERIODIC TESTI IG h-52 h.9 1 TEST h-52 h.9.2 ACCEPTA';CE CRITERIA h-52 4.10 REACTIVITY ANOMALIES h-53 h.ll SITE E:iVIRO:I'4E' ITAL RADIOACTIVITY SURVEY h-Sh 4.12 CONTROL RCCM FILTERI iG SYSTDI h-55 h.12.1 OPERATING TESTS k-55 4.12.2 FILTER TESTS h-55 h.13 RADICACTIVE MATERIALS SOURCES SURVEILLANCE h-56 h.lh REACTOR BUILDING PURGE EXHAUST SYSTDI h-57 4.15 MAIN STEAM SYSTDI INSERVICE INSPECTION h-58 h.16 RZACTOR INTERNALS VENT VALVES SURVEILLANCE h-59 5

DESIGN FEATURES 5-1 51 SITE 5-1 52 CO:rrAINMENT 5-2 5.2.1 REACTOR EUILDING 5-2 5 2.2 REACTOR EUILDING ISOLATION SYSTDi 5-3 53 REACTOR 5-4 5 3.1 REACTOR CORE 5-4 5 3.2 REACTOR COOIRIT SYSTD1 5-L 5.h NFJ AND SPENT FUEL S0TRAGE FACILITIES 5-6 5.4.1 NE'd FUEL STORAGE 5-6 5.h.2 SPE'iT FUEL STORA3E 5-6 5.5 AIR INTAEE TUN'!EL FIRE PROTECTION SYSTD!S 5-8 6

ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-2 6.2.1 0FFSITE 6-2 6.2.2 FACILITY STAFF q7nq 1[O 6-2 6-3 6.3 STATION STAFF CUALIFICATIONS J

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6.h TRAINING 6-3 6.5 REVIrd & AUDIT 6-3 6.5.1 PLANT OPERATIONS REVIE'd COMMITTEE (PORC) 6-3 6.5 2.A MET-ED CORPCRATE TECHNICAL SUPPORT STAFF 6-5 6.5.2.B GE'IERAL OFFICE REVIE'd E0ARD (GORB) 6-7 6.6 RE"CRTARLE OCCUPREiCF ACTICN 6-10 6.7 OCCURRENCES INv0LVI::G A SAFETY LIMIT VIOLATION 6-I0a 6.8 FROCEDURES 6-11 iii