ML20141N661
| ML20141N661 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/10/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141N660 | List: |
| References | |
| NUDOCS 8603170466 | |
| Download: ML20141N661 (4) | |
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Introduction In a letter from E. A. Liden to S. A. varga dated Octcber 15, 1954, the P:.blic Service Electric & Gas Company (the licensee) pecposed an amer.d.r?r.t ta their Facility Operating Licer.se DPR-75 fcr Salen Generating Statica, Unit.
No.2(Salen-2).
The asend. Tant propose; to revise heatup and ccoldown I'mit curves in Figures 3.4-2 and 3.4-3, and bases Figure B 3/4.4-1 in Appendix A of the Sale:-2 Technical Specification.
The re/ised curves are to be ap;)1icable through seven (7) effective full po ee years (EFPY).
The bases for these i
changes are the test results fro 1 tr.e Salen-2 surveillance program, which u2 -
contained in Report ',l CAP 10492, " Analysis of Capsule T, Salea Unit 2 Reacter Vessel", dated March 1924.
Report WCAP 10432 was submitted for staff reviea in a. letter frc. E. A. Liden to S. A. Varga dated July 3, 1924.
Evaluation and Sumary,-
Pressure-te:rperature limits ruust be calculated in accordance with the require:ents of Apper. dix G,10 CFR 50, which became effective on July 25, 1983. Pressure-te:perature limits that are calculated in accordarce with ti.e requiree.ents of Appendix G,10 CFR 50 are dependent upon the initial RT,T for g
the limiting caterials in the beltline, and closure flange regions.of tne reactor vessel and the increase in RTI3T resulting feca neutron irr'adiatica damage to the limiting beltline caterial.
The Sales-2 reactor vessgl was procured to A5I:E Ccde rectiravants, which did not specify fracture tcugh sis testing to deter:1'e tha ir.iti:1 P.T,;,37 for a:.5 vessel r.tcriti.
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- ' a Fractere Teaghnags.Rar,uintents." This athod results -in aa int th! ?,T,.,i for th'a li iting baltlina's eld catel cf PF and ca. initial.T n fer the-I..
,iritic]ciesurep, lata..at:rialcfWF. 'The increase :n RTET resulting frca neutron irradiation dtnage s.as estirtt2d -by t'he licensee using tha enpirical relationship docuranted la Rig 21st:rf Guide 1.93, Rev.1, April:'.377, 'iffects of Residual Els;ents ca' ?redicted
- Radistica Da sge to Reactor Vessel l'sterials." This ceth:d :f precicting
'neutraa irraciation daTage is de;endent upon the predicted azaunt f ciute:a c fluecce' and the atounts of resid:.11 elements (cep;er tad phaiphnrus) f a the beltline caterial. The cette:n fluence predicticas were verified tj measuren nts frca passive neutron flux conitars and by analysis, which w:s nde with the DOT two-dicer.sicaal discrete ordinnes code. Inputs into the analysis. included 47 neutrca energy groups, P3 expansion of the scattarh3 cross sectica,'and power distributicns reprasantathe of tice-avers;ed conditions derived frca ststistical studies of Icng-term cperatica of 1 Westinghouse 4-lcop plants. The crcss secti:ns ussd in the analysis were
- cbtained from the SAILO3 cross section library.
Using this method cf analysis, the ceasured saturated activity and neutron fluences (E>1Mev) for ~ five foi1 reactions, which were calculated froa neutroa d:si:etry in Ca;s21e T, were less. than that predicted fres the design basis calculated neutron 'fluences. The autbcrs of WCAP 10492 raccceended that projections cf vessel toughness into the future be based ca the design calculated fluence levels, ~ ~ since the calculated fluence levels era based ca cons'ervative representaticas cf core power distributions derived for long-tern operation while the C1;sule i data are repre:entative 'only cf cycle 1 operatien. The staff agrees with this recommendation. e ine predicted ar. aunts of 'nectron irradiation damage are based cn dasiga t, asis calculated neutrea ficences and the Re;ulatory Guide 1.93, Rev.1 u per licit curves for increase in RT The ressured increase in RT from the weld OT. ET ~. -.
,3, samples in Capsule T is 155 F. The increase in RTO T predicted using Regulatory Guide 1.99, Rev. 1 upper limit curves is 165'F. Sir.ce the increue in RTIOT predicted using the' upper limit curves exceeds that ceasured fron the sa:ple naterial, t,he Lppcr linit curves sh:uld c:nservatively predict the a.To.nts of neutron irradiation da a;e. s L: The staff has used the teth:J of.calculatir.; pressure-terpatcra li-its in UPiRC Standard Revie.rPlan 5.3.2, !!'JREG-0300, f.ev.1, July 1731 to ev31 Late the proposed pressure-terparature limits. The' amounts of nautron irradistica damage was calculated using design basis calculated neutron fluences'and the Regulatory Guide 1.99, Rev.1 upper ifnit prediction curve. Our cor.clusion is that the proposed pressure-temperature limits meet the safety margins of . Appendix G,10 CFR 50 for 7 EFPY and may be incorpcrated into the plant's technical specifications. Environmental Consideration This ' mendment. involves a change in the installation or use of a facility a .corponent located within the restricted area as defined in 10 CFR Part 20. ~ The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in idual$r' cumulative occupational radiation exposure. The Commission has 'in previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coment on s 'h finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9). Pursuant to I 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this, amendment.
.E.. 4 gi 4.. + v Conclusion We have' concluded, based on the consideratiens discusserl above," t't=t: (1) there is reasonable assurance that the healch a1d safety of the .public will_not be endangered by. operation in the proposed manrcr. and (2),such activities will be conducted in comp'11ance with the Comission's regulations and the issuance of this errendrnent will hot be inimical <to the common defense an'd security or to the health and -safety.of the public, Dated: March 10' 1986 Principal Contributor: B. Elliot t r A D e l l -}}