ML19268B952

Provides Review of Pressure Temp Operating Limits in Response to Util 770233 Amend Application.Recommends Proposed Pressure Temp Operating Limit Curves Be Limited to Operation Through Five Effective Full Power Years,Not Six

ML19268B952
Person / Time
Site:	Crane
Issue date:	04/14/1977
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
References
NUDOCS 7910220662
Download: ML19268B952 (2)

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KDORMDUM FOR:

K. R. Golle'r. Assistant Director for Operating

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D. G. Eisenhut. Assistant Director ter Opeestional

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THREE MILE !$LMO. UNIT N0.1 - REVIEW OF PRESSURE-

'j[1 TEMPERATURE CPEMTING UNITS (TAC 6612)

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Plant Manc: Three Mile Islant 1

. ~4 Docket No: 50-283

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i Responsible Branch and Pioject l'eader: ' 0RS-4. C. Zwetzig

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. Re44ested Completion Data: April 11.1977

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• ' Description of Request: ' Review of Pressure-Tenperature Operating Limits Review Status: Complete,

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In letter' dated February 23. IM7. Metropolitan Edison Company requested 4

'. amendment to Techatul toecification 3.1.2. ' Pressurization Heatup and

c. Cooidown Limitations.' for Three Mlle Island. Unit 1.

They also enclosmi

.,.A y, in.this'1stter the results and analysis of Capsule TMI-IE removed from

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i' tihy: the Three Mile.! slam. Unit 1 reactor.vassel. The prorosed pressure-w.

'..W.4.X f temperature opeeating Ilmits were calculat*d for' operation through six ETPY.

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r dThe m.xlaus flgn/cag, ythe vessel wall 10 4urface at 6 EFPY is calculated 4.'.: ', Y, f *:,.

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to be 3.2 X 10 J

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. :gj.: 5L p.1,!n the... reactor vessel beltline restoo there are six different w

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'v "A - WW-8. W-25,,W-67. W-70. SA-1494 and $A-1526 From the chemical

. composition and location of these welds. the W-25. kT-70 and SA-1536

.r welds are the most critical..The hT-25 material is included in the

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.a Three Mlle Islam materall surveillance program.

It has 0.341 copper and 0.015; phosphtruss. and its initial RTunr is -14'F.

For the proposed operating itait curves, weld asterial SA-1526 was calculated to be the sost lir.iting material. It has 0.36%, copper and 0.0161 phosphorus ad an_inttial RTROT of 20*f.

Capsule TMI-IE was removed during the first refueling shutdown g{ Threq Mile Island Unit 1.

Specimens received a fluence of 1.07 I 10' n/cu'.

.The upper shelf energy of the weld material. kT-25. dropped from al to

• N 62 ft-lbs. The shif t in RTxny measured at 50 ft-lbs is 117'F. Both of the above expertrental valuel agree closely with values predicted from x

i, NResulatory Guide 1,.99 T

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2 APP,141977 (a.)

We have reviewed the proposed pressure-tesperature operating limits for

1. h Three Mile Island, Unit 1.

We agree that weld sterial in the vessel

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beltline reston will be the liatting material. Howevu. in view of the

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varinness we have found in the chemical composition (particularly copper 3

content) of the B&W welds we feel that untti ecre data are available the

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upper limit prediction itne of Regulatory Guide 1.99 should be used to predtet changes in RTwot due to irradiation. Using this criteria, weld N

NDT of 140*F. due to irradiation.T of 20'F an It has an initial RTND metal WF-70 will be IVaiting.

Thus, the value a

predicted shift in RT

'of RTNDT at 6 ETpf is predicted to be 160'F. RTgny for weld raterial p,.

'5A-1526. the assumed limiting unterial by MetropoTitan Edison Coroany

.d for, their proposed limit curves is 145'T at 6 ETPY, Because of the a'

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.above discrepancy. we recoseand that the proposed pressure-temperature Ty:

' : operating. limit curvas for Three Mile Island. Unit 1 be limited to p

operation through five EFPY. If the proposed operating limits are s

limited.to operation through five ETPY, the proposed Technical Specification i,'

'A 3.1.2 is acceptable and is in conforvance with Appendix G.10 CFR Part 50.

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• t.No changes were prope:ed for TecMiE.al '$pecification'3.1.3, 'Mininum u

,..l' ' o; Conditions for criticality". 'This spuification requires that the.

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.rea: tor' coolant terperature be above 525'F prior to criticality r,

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(#p,: ;. except for low power physics tests. This specific f

requirements' of

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te t Conformance 'with Appendix G.10 CTR Part 50 in establishing safe operating 9

. limitations will ensure adequare safety surgins during operatton, testing.

A reintanar,ce and postulated accident conditions and constitute an acceptable '

i basis for satisfying the requirements cf MRC Ceneral Design Criterion 31 t.

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Appendtx A.10 CFR Part 50.

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3 D. G. Eisenhut. Assistant Director for Operational Technology

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DISTRIBUTION:

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