ML19308D833
| ML19308D833 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/01/1978 |
| From: | Noonan V Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19308D832 | List: |
| References | |
| TAC-08884, TAC-8884, NUDOCS 8003191022 | |
| Download: ML19308D833 (2) | |
Text
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~ i'a MEMORANDUM FOR:
R.' Reid,' Chief, Operating. Reactors Branch No. 4 l Division of Operating Reactors FROM:
V. S. Noonan, Chief, Engineering Branch Division of Operating Reactors
SUBJECT:
-. CRYSTAL RIVER UNIT 3 - PRESSURE-TEMPERATURE OPERATING LIMITS r
Plant:Name: " Crystal;RiveEUnit 3 NSSS Vendor:' Babcox and Wilcox
~ Docket Numberi 50-302' Operating Reactors Branch and~ Project Manager:
ORB-4, C. Nelson Engineering and Projects' Branch Involved:
Engineering Branch Due Date:
August 31. 1978 Review Status: Complete In letter dated August 18, 1978 Florida Power Corcoration submitted a set of revised pressure-tenperature ocemir.g curver a ': auplied to Crystal River Unit 3 administratively until 1) it H determ. 2d that the atypical weld wire was not used in enufacNre o#this reacter vessel or 2) until a license amendment is issued th: t inserts the revised curves into the TechnicM Specifications.
'he proposed c;:erating curves were calculated for operat og through 5 EFPY There are seven weld raterials in the reactor vessel Mitline reg'c.
3ared en chemical composition and weld location, sF-70 is ex:ected to be the most limiting vessel naterie' The licensee's s.tittal of August 18, 1978, included revisions to reflect the possible ute of atyoical weld wire in welo WF-70. This atypical wire had a lower nickel centent
'(0.1% vs typically 0.6%) and a higner silicon content (15 vs typically 0.5%) than the wire normally used.
The effect of this variation is to cause a higher initial reference tr.coerature for the nil ductility transition (RTNOT), This higher value of RTET was used by' the licensee in his analysis, J
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Weld material'WF-70 contains 'approximately 0,' 2% cspper and 0 017%
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phasphorust and its initial reference temperature 120kF,. Five capsules containing thi.s. material,are being irradiatediat iarious facilities; two capsules;each at Davis-Besse Unit No, l~and Ciystal River Unit No, 3, and one capsule at a test reactor,. The capsule being irradiated at tne test reactor is scheduled for removal during 1973, and the other capsules are scheduled for removal in 1981, 1932 and 1989, Should the-results of tnese capsule irradiations so indicate we will requi,re appropriate modification. of the pressure-tempera}ure limits, '
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i We'have revieweel the ifcensee's ' submittal., Based on our review we.
agree that weld WF-70 is the limiting material. We estimate that the'
- naximum value of fluence p this weld at the 1/4 T location at end
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of life will be 1.55 x 10' n/cn2 Using this fluence value and Reguistory Guide 1.99, Revision 1 to predict radiation damage, we calculate the propo:cd operatta;; curves are a::cpptable for.
operation through 3 EFPY. For operation through 3 EFPY the proposed pressure-tepperature operating limits'are in conformance with Appendix G,10 CFR Part 50..
Conformance wf th Appendix G,10 CFR Part 50 in establishing safe o'perating limitations will ensure adequate safety margins during operation, testing mainterance and postulated accident conditions and constitutes an acceptabio basis for satisfying the recuirements to NRC General Desien Critarion 31, ApNndix A, 10 CFR Part 50.
Vincent S. henan, Chief Engineering Branch Division of Operating Reactors Centact:
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Date:
X/.19/7f
- William 0. Miller, Chief License Fee Management Branch, ADM Attended For g y Nh pg; R
FACILITYAMEtIDME!!TCLASSIFICATI0tl-DOCKETfiO(S){.,
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LFMB eac e-Licensee:
Fr-a'/an R e?P G!.'^M re 0 LFNB Exe mtien Filo RDiggs 9/M/
Plant flame ard Unit (s):
,._'.s < A c 'P, w := Uv. r.3 License !!o(s):
D /k' - N Mail Control *lo: W.c 2/c M Request Dated:
f/ 4/-7c Fee Remitted: Yes /
tio Assigned TAC flo:
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Licensee's Fee Classification:
Class I II
, III I, IV
,V
, VI flone f
/b E' Amendment flo.,6 A n s b, Date of Issuance
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1.
This request has been reviewed by DOR /DPM in accordance with Section 170.22 of Part 170 and is properly categorized.
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This request is incorrectly classified and should be oropedly-categorized
.a s -Gl ass-Justification for classification or reclassification:
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3.
Additional information is required to properly catagorize the rwast:
[il 4.
This request is a Class gtype of action and is exempt rom fees because
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it:
(a) was filed by.a nonprofit educational institution, (b) was filed by a Government agency 'and is not for a power reactor, (c) is for a Class (can only be a I, II, or III) amendment which results from a written Commission request dated for the application and the amendment is to simplify or clarify license or technical specifications, has only minor safety significance, and is being issued for the convenience of the 3
Commission, or
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(d)
I other (state reason therefor):m'd.k Een.. d 4.<.a t',,,-/
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The.above reques t has been revie. led and is exempt frem ices sd e' e-w_.ff,,, / 2.
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