ML19270H569

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

ML19270H569
Person / Time
Site:	Three Mile Island
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

.

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

. 50-289

< 2as e , ,

NRC DISTRIGUTION rom PART 50 DOCKET MATERI AL FNOM: oATE OF oOCUMENT

' TO:

- Metropolitan Edison Company 6/13/76 Mr. R. W. Reid Reading, Pa. - 04Te neceiveo Mr. R. C. Arnold 6/21/76 ONoTonizeo PRCP INPUT FO AM NUMBER OF COPIES RECEIVEC N ETTER peniciN AL K Nc L4ssi,,s o Ocoev One signed cescairTioN ,

snetoSUne ,, ..

Ltr. trans the following: 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 e densification penalty.  %

a (1-P) (9-P)

PIANT NAME:

Three Mile Island #1 -) 7 n q j /i Q

c. . - , , s SAFETY FOR ACTION /INFORMATION ENVTRO 6/23/76 RJL ASSIGNED AD: ASSIGNED AD!

h_ BRANCH C] LIEF: Reid (6) BRANrH cFTrF-

! PROJECT MANAGER: PROJECT MANAGER:

h LIC, ASST.: Ingram LIC. ASST.!

I

{, 3 INTERNAL DISTRIBUTION l K ?_rn rTTri 4 SYSTEMS SAFETY pTANT qYSTEMS SITE SATETY &

NRC PDR _

HEINEMAN Tr ne st'n ENVIRO ANALYSIS I I&E [A) SCHROEDER .BENAROYA DENTON & mnieR pgI,D LAINAS COSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH _ i LJCPC MACCARRY KIRK000 eiNST CASE KNIGHT I B41,12RD 6 HANAUER SIHWEIL OPERATING REACTORS i SPANCTTR PAWLICKI ' i l{A,'UISS STELLO qTTr TFf*M _ I PROJECT MANAQ_EMENT REACTOR SAFETY OPERATINC TECH. CAPMTTL l BOYD ROSS M EISENHUT [4~9fd STEPP f

l P. COLLINS NOVAK M SHA0 HUT VAN I HOUSTON ROSZTOCZY X BAER  !

PETERSON CHECK K B1T,1ER SITE ANALYSIS VOY T wR MELTZ 'V GaIMES '

HELTEMES AT & I l BUNCH SKOVHOLT SALTZMAN X 3. COLLTNS RUTBERG v"rCr9 '

i i EXTERN AL OISTRIBUTION CONTROL NUMBER ,

' LPDR: Harrisburg, Pa. NAT LAB: I BROCKHAVEN NAT 1AB TIC: REC. VIE l ULRIKSON(ORNL) jlSIc.

ASLB; ,

LA PDR CONSULTANTS

[ j

%AQRS /6CYS "CLMNC/SENT ! Ad 60,M I 1 i ' I Nnc ronM iss #2act - "w

~

' ,~L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

e - OfSI ky?::.. mea nw raoc.am METHOPOLI FAN EDISON COMPANY POST OFFICE BOX 542 RE ADING, PENNSYLV ANI A 10CO3 TELEPHONE 215 - 929C601

' Gi N'/em-Junela,19~h GQL 0891 p c a iL@A.l tb i L \

M L JUN21197cd i

r uccmss u .s. nun

,,z,u.,.,,

e

,?

Director of Nuclear Reactor Regulation b *w Attn: R. '4. Reid, Director M Operating-Reactor Branch No. L U.S. Nuclear Regulatory Co.~ ission k f ,({. r

. ~ - -

~

'4ashingt on, D. C. 20555

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.

Sincerely, t'

.7(')s /!

\

R. C. A/ rncid Vice President ECA:JJ>f:sft z.nc10sure 9701 1/Q .,

_ Q W-

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 STATION STAFF CUALIFICATIONS o- - J 6-3 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