ML19260A034

Tech Spec Change Request 49 Supporting Licensee Request to Change App a to License DPR-50 Re Deletion of Vessel Cladding Insp Requirements.Certificate of Svc Encl

ML19260A034
Person / Time
Site:	Three Mile Island
Issue date:	02/18/1977
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A027	List: ML19260A026 ML19260A034
References
NUDOCS 7910290667
Download: ML19260A034 (9)

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chanste Recuest No. ho This Technical Specification Change Request is submitted in support of Licensee's request to chan,e e Appendix A to Operating License No. DPR-50 for Tnree Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON COMPANY By -

71ce President Sworn and subscribed to me this f day of 977 J'

e4/

Notar/' Pu W e VCer I ,

3910290 $

1479 003

UIIITED STATES OF AMERICA IiUCLEAR REGULATORY COMMISSI0IT III THE MATTER OF DOCKET 1i0 50-289 LICEfISE I!0. DPR-50 METROPOLITAII EDISOII COMPANY This is to certify that a copy of Technical Specification Change Request Iio. h9 to Appendix A of +N Operating License for Three Mile Island Iluelear Station Unit 1, has, on the date given below, been filed with the U. S. Iluclear Regulatory Ccmission and been served er the chief executives of Londonderr/ Township, Da1phin County, Pv.nsylvania and Dauphin County, Pennsylvania by deposit in the United States :: ail, addressed as follows:

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

Board of Supervisors of Board of County Co=issioners Londonderr-/ Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAIT EDISOII COMPAIIY k

By rY Vice' President Dated: _Februarr 18, 1077 1479 004

Three Mile Is.'and Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Reauest No. h9 The licensee requests that the attached revised pages replace pages 4-17, h-19 and h-21 of 'che existing Technical Specifications, Appendix A.

Reasons for Proposed Change The reason for this revision is to delete the vessel cladding inspection requirements from the TMI-l Technical Specifications. The requirement to inspect vessel cladding was included in the 197h Edition of Sectior C of the ASME Code as Examination Categories B-I-1 and B-I-2. Both of these categories were deleted by the Summer 1976 Addenda.

Safety Analysis Justifying Change The high radi ation exposure involved in these inspections should be avoided now that the ASME, a competent authority, no longer feels that they are necessary from a technical point of view. Deleting these requirements will not adversely affect the health and safety of the public and will, on the other hand, reduce the amount of exposure incurred during inservice inspections. The proposed change does not involve any unreviewed safety questions in that the basis for the deleted inspection requirements wasSection XI of the I.SME Ccde which, as revised by the 1976 Summer Addenda, no longer requires these inspections.

1479 005

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TA512 4.21 (Contiswed) Sheet b or 13 Item Examination Dtamination IS - 261 Category-YS - 051 Areas to be 2xanined Methode Inspection Schedule and Extent Remarks d

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Y Interior surfacae Visual Normally accessible areas will be 1.15 N and internals aM visually insg,ected st the first re-fuelins and every third refueling (W

c CR integrally velded internal supports thereafter. The cere barrel vill C~~O cot be removed soley to permit in-spections. If the core barrel is Eh

$-p removed for other reasons, addi- tr C tional *nspections or the inter- 6C nals and vessel interior vill be T performed. Once every 10 year in-spection interval. the region below

- the reactor core vill be inspected to the extent feasible through the access holes in the internals.

Pressurteer 2.1 B longitwiinal and cir- Visus 1 and '.humGstive of 100% of the circum- This veld is subjected to a cunferential velde Volumetric ferential veld from the outside at much higher stress range the lower head to shell juncture. than any other shell veld in

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• vith 1/3 of this weld beins in- the pressuriter'.

specte4 about every 3-1/3 yests.

4 Also, one foot or each lon6 1tudinal q veld which intersects this weld will D be inspected during the 10 year in-spection interval.

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TAst2 4.2-1 (Continued) sheet $ or 13 Ites lisasirsstom Zzaninstice IS - 261 Category-IS - 2 g Areas to be S erineq Nthods Ist reetion Schedule and htent Rema-ks 2.2 D Nostle to wwoesi veldr Volumet*ie Toe erge netz*e veld vill be The nrge nozzle veld le vol':Tttrically inspected from subjected to a much higher the ostelde esce about every usage factor than any other 3-1/3 years. weld in the pressurtser.

The surg- notale is r.ot accessitie from inetz- the pressuriter.

23 E-1 Rester coinectiera rvat Reo -evarkn See ressarke Heatere meet esclueicat nesting exclueton criteria of IS - 121'.

criteria 2.b E-2 Mester and ir.strument flami A v!wal examination for 1-s2mge conrectione vil'. te perfermed during hydro-e statte tests.

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$ 2.5 0-1 Pressure retaining tvait-ing 2 inches me.d greater Visual and volur.etric or The bolting for the zapvay e.nd one beater tundle vill be inspec-Note 2 lo diameter sw face ted Suring the 10 year inspection interval. T:: place visual dr. spec-tion w!!! be performed on all the bulting during the 10 year inspee-tion intervel with 1/3 being checkeJ about every 3-1/3 yearn.

2.6 0-2 Ivessure retalning bolt- Yleual Thie t.olting vill be visually in-ing less than 2 inches spe:ted at Icast once during the in diameter 10 year interval. The inspectione vill '.,e done in place unless break-the :onnection is required for cther r.asors. 1/3 of these in-spe:tions util be done about every 3-1/3 years.

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! e This persgraph of the #Svr Code for Inservice Inspetion gives rulee which sselude evall y else peaetartione, etc., frts. the fM11 requirements of the Code.

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4 7tBLE 4.2-1 (Contfaued) Swet 6 of 13 Item Examinatiot Enemination TS - M1 Category-IS _- 2$1 Arees to be Psamined Methods gepection Schedule and Extent Remarks 2.7 11 Integrally we'ted vessek Visual and Visual su veys of the supports The ultrasonic inspection euroorts volumetric will be performed at the first technique is developmental.

refueling and every third re- These inspections will be fueling thereafter. A thorough done on a "best effort" visual inspection will be per- basis.

formed on all the supports near the end of the 10 year inspection interval. An ultramonte inspec-tion will be performed of the weld on one of the supports about evrry 3-1/3 years.

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l Steen Generators (S.C.) and Let-down Coolers (L.C.?

H m tongitudinal or ctrewa- Visual and 8.0. - The sly welds in this The urper head to tubesheet 3.1 a rarential welds in pri- volumetrie category are the tube-sheet to welds are subjected to more mary side shell head welds. Five percent of severe stress conditions the upper head to tubesheet veld than the lower head to tube-on one steem generater will be sheet velds.

inspected near the end of the inspectica interval.

L.C. - A portion of the longitud- ne inlet manifold is sub-inal sess welds on each primary jected to much more severe b ) manifold is accessible at the reni- temperature transients than the outlet manifold.

fold te ylpe joint. The eccessible

{ g Portion will be inspected near the end of the inspection interval on 10] the inlet manifold of the cooler which is used the most.

D- 3) The pressurtser surge nozzle 3.2 t-Mib D */rtmary nor.sle to head Visual ~ S.C. - No volumetric inspections c~d velds and nozzle *.nsid, are planned. Visual inspection and reactor vessel outlet 99 radiused section of the inside radiused section nossle velds are subjected

-* .- CFJ vill be performed cmce during the to more severe stress con-

.b (AH) 20 year inspection interval if the ditions than the S.C. nozzle g C primary heada are opened for other' welds. Since the pres-

- y C-j - reasons, surizer surge and reactor

@ kbi vessel outlet nozzle welds will be inspected, inspec-CJ tion of the S.G. no: ale g b .

welds is not warranted.

6 CD t.C. - There sere no L.C. welds in this category

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d TAE12 4.2-1 (Contioned) Sheet 7 of 13 Enemination D'.sistnettos Item Fethods Inspeetten Schedule and Extent ytemarks

S - XI Category-IS - 2$1 [ ween to be Enam!ned_

Nimrry noule to safe- See remarks See :.emarks S.C. and 1..C. - There are 3.3 F no welds in this entegory.

end welds (dissimila-metal)

Pressure retaini.sg bolt- Vis.tal ar.d 0.0. - The boating for Ce pri- note 2 3.6 0-1 mary head manway vill be in ing 2 inches dad over voltssetric in diameter o surface spected during the 10 year interval. This inspection will be performed without disas-sembly of tbs connection unless disassembly is res. aired for other reasons. In place visual inspec-tion will be perfereed on e11 the bolting during the 10 year inspec-tion interval with 1/3 being 4:- checked about every 3-1/3 years.

I r0 o L.C. - There is no 1:olting in this category.

?renru-o retaining wit- Visue.1 S.C. - Thic bolting will be vise-3.5 0-2 ally inspected at 1 cast once ing less than 2 ine'.es in durir.c the 10 year inspection ,

diameter in '.e rv al . The inspections vill be done i'i place unless breaking the connection is r quired for other reasone. 1/3 of these checke will be done about overy 3-1/3 years.

L.C. - There is no bohlrg in this catesory.

Inte8va33y we3ded m . Vism1 anQ S.C. - Ten perceat of the 3ength Ti se are some of the more 3.6 N eel supporte volumetric of this veld on each steam highly st.essed velds in

-* generator will be inepected during the plant.

the 10 year inspection interval f .f.:=. with 3-1/35 of each veld being

3 q inspected about every 3-1/3 ywars. ,

H 1.C. - There are :w supports in thle category.

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TABLE 4.2-1 (Contlaued) Sheet 6 of 13 ften Isaminatios Examinatics Areas to be haalped Methods Inspeettom Schedule and hteet Remarks IS - 261_ Category-IS - 2 Q O

Psptog 2005 of the binatallic wetos or pote: The stress evaluations F Safe-end welde Visual,sur-4.1 face and tuo safe-ends in the main reac- are tentative and selected (dissimilar metal) tor coolant piping will be in- welds may be revised.

volumetric f

su spected during the 10 year in.

H spection interval. One safe-end will be at a pump outlet and the other at a pump inlet.

For smaller site safe-ends, the nossie safe-end welds in each site rangs esposed to the most severe stress condittor.s will be inspected during the 10 yeas in-spection interval. This means t.%t one or more weld of each of y the following groups of safe-G end velds will be inspected as kJ in 31cate d :

a. Ik" pipe - 2 reactor vessel core flooding nottle dissi-d milar metal welds (see Item

- $' 1.T).

~ q;1 1 O h; rzh b. 12" and 10" pipe - One decay heat 09tlet and one surge line N D $1ssim11ar metal weld to the Q ,

3 reactor coolant (DC) piping, g 7M and one surge line dissimilar metal weld to the pressuriter.

~ The s rge linc connections to the reactor coolant pipe and Q - to the pressuriser both see relatively severe stresses and will be inspected.

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Sheet 9 of 13 TAht.E 4.2-1 (Continued)

Essainatloc Exasiinattoa Remarks Item Methods insoeetion Schedule and Extent IS - 261 Cateporv-!S - Q Areme to be Enestned

c. b" cr.d under pipe - Four high b.1 (Continued) pressure injection. wee letdown, three 4 ain an1 one spray line disristlar metal velds to the RC piping, and three a elief and one spray tiissimilar metal velds to the pressurizer. Of these the spray line cozzles t.o the reactor coolar.t pipe and to the prea-suriser see relatively higher stresses and are selected for inspection.

One third of these taspections vill be perforsed about every 3-1/3 years.

Circumferential and Y1sual and Circumferential and tonnitudinal velas

%.2 J-1 volumetric The most severely stressed welds Note: The stress evalusta.

y longitudinal pipe eelde tions are tentativ: and g

and branch pipe ccn- (exclusive of dissisilar metal selected velds muy be re-N nection velds grer.ter velits which are covered in Item k.1) in each site range in each wised than b inchen in diameter syste ,will be inspected. The -

follovirs velds vill be inspected during the 10 year inspection interval:

' Resctor enolant System Itote 1 applies to the

n. In the 36 I.D. reactor ecolant pipe, one of the volds between reactor vessel nozzle to the 1000 elbow at the top of the pipe veld.

stenn generator and the vertical l

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vill be inspected t'6 ether with $

one foot of each !atersectins L LJ D b' uk 3 lonsitudinni veld. In addition, ,

one reactor vessel outlet nozzle to pipe veld will be in-spected. -

b. In the 28* 2,D. reactor cool-ant pipe, one of the velas at 4~ the dovnetream ends of the elbows

" m at the uischarges o* reacto:-

e coolant purope 1A1 and 1B2 vill D be inepected together with one f

P N foot of each intersectin6 1M81-C tudinni veld.

7.) c. The met sever:1y ' stressed veld O in the surgr lina. .

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