ML20215N055
| ML20215N055 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 05/08/1975 |
| From: | Deyoung R Office of Nuclear Reactor Regulation |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20197J003 | List: |
| References | |
| FOIA-86-371 NUDOCS 8611040220 | |
| Download: ML20215N055 (5) | |
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Docket Fil DPAllison LWR 1-3 File TJHirons RSBoyd VHWilson RCDeYoung WRButler RWKlecker DBVacsallo MAY 081975 MWill imin ODParr
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50-275 and 50-323 A. Gimbusso, Directw, Division of Reactor Licensing, NRR STA'IUS OF THE SAFE 1Y EVAUJATION REPORT FDR DIAUA CREON, UNITS 1 NtD 2 (OL)
This mmorundum is to advise you of the status of the Safety Dealuation Report (SER) ard its supplenents for Diablo Canyon Units 1 and 2 and to surazarize the cutstarding itens. The outstarding items are categorized accordirg to the method proposed in your memomrdum of Decenber 5,1974 to Mr. h. K. Shapar.
'Ihc SER ms issued on October 16, 1974 and Supplement };o.1 was issued on January 31, 1975. The ACRS did not prucced with the review because we had rot resolved the geology /scismology issues. Following E. G. Case's request, ACR3 has agreed to consider the application in tw parts. The first part, which excludes geology, seisr. ology and seismic design is scheduled fx considemtion by the full ACRS in June 1975, with a subsequent neeting !.n September 1975. This split approach will entble us to minimize the len @
of our review ard its impact on fuel loadirs fx Diab 1n Canyon Unit 1.
We DL%g are now prepared to issue Supplement No. 2 to support the ACRS consideristion at its June meetirg.
In Supplcaent No. 2, we have identified certain issues categorizei as outstardirg issues in our review which require the applicant to petwide confirmatory informtion in onier that we may conplete our review, or which require our evaluation of infan:ation already provided by the applicant and which is currently urder review. These issues irwolve informtion that require our evaluation prix to issuarsee of an opemting license fx this application. The issues in this category are sunnsrized
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in Attactnent A and further discussed in the sections of the SER ard/or its supplanents, as irrifmted in the attachent. We anticipate that l
noot, if not all, of these issues (other than those related to geology, seisnology ard seismic design) can be satisfactorily completed prie to our scintuled date for issnence of the supplacent to the SER following the June ACRS meeting.
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j A. Giambusso I We Mve also identified certain issues categorized as resolved issues.
on which we lave carapleted our review and luve establiahed a position to which the applimnt Ms not yet agreed in the FSAR. The issues in this categwy are sumnarized in Attacluent B and are discussed in the sections of the SER and/or the supplerents as indicated in the attaclment. We anticipate that these issues will be satisfact wily addressed in the suppleasnt to the SER following the June ACRS meetirg.
On the basis of our assessrrent that the issues identified in Attaclvaents A and B, which are not related to geology, seisrclogy or seismic desimi, can be satisfactorily concluded prim to our scheduled date fw issuance of the supplanent to the SER following the June / CPS raeeting, we rh.un-rd that Supplanent No. 2 be issued and that we meet with the ACRS in June 4
j as scheduled.
omia w.!tvn.c.WYmme R. C. DcYoung, Assistant Director i
for Lirjit Water Reactors Group 1 Division of Reactor Licensing Attach:ents:
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5/6/75 5/F/75 5/f75 form AFCdle (Rev. 9.$3) AECM 0240 W u. e. oovannusm? PnaNTING 0,FICEB te74 488.644
'MAY. O 8 1975
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n ATTACE'ENT A OUTS?ANDDE ISSUES MD CONCERNS DIABLO CA! PION UlTITS.1 MD 2 OutstaMire issues which require the applicant to provide additional infoma-ion in oMer that we may complete our review, or which require our evaluation of infomation already provided by the applicant and
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which is currently under review.
(1)
We reqaire aWtional information regaMing geology and seismology (Sections 2.5.1 and 2.5.2 of Supplement Ib.1).
(2)
We are evaluating the applicant's subnittal on Tsunani's generated by nearshore faults. Possibly this iten can be seperated from the geology /seis:: ology issues (Sections 2.4.2, 2.4.3 and 2.4.5 of Supp1 ment Ib.1).
(3)
We are evaluating the applicant's subsittal regarding pipe breaks outside contaiment (Section 3.6 of the SER).
(4)
We require additional information regading seismic qualification of electrical instrunentation and equip:ent (Sections 3.7 and 3.10 of the SER).
(5)
We require additioral infonration regarding enviromental qualification of electrical equipnent and instrumentaticn (Section 7.8 of the SER).
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(6)
We require infamation to justify using the results of 7-grid fuel assembly tests to =uve the acceptability of 8-grid fuel assembly design (Section 4.2.1 of Supplement Ib. 2).
(7)
We require information to verify that the design nodel adequately predicts the effects of fuel rod bowing beycM the first fuel cycle (Section 4.4 of Supplenent No. 2).
(8)
We.@c test results which adequately deronstrate that the effect of non-unifcm heating on departure frun nucleate boiling is properly accounted for, or, altermtely, we will i:spose an additional 5 pezrent nargin on the departure from nucleate Iniling ratio in the technical specifications (Section 4.4 of Supplement No. 2).
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Attachment A A-2 (9)
We require test results which adequately verify certain aspects of the THDC code or, alternately, we will include appropriate restrictions in the technimi specifications to maintain required margins to fuel rod damge (Section 4.4 of Supplement 16. 2).
(10) We require subnittal of a revised ECCS analysis in accordance with the final acceptance criteria (Sections 6.3.3 and 6.3.5 of Supplccent 16. 2).
(11) We are evaluating the informtion regarding Anticipated Transients Without Scram (Section 7.2.5 of the SER).
(12) We require information substantiating the building heat loads which the applicant assumed in calculating the humidity of air entering the auxiliary building chnW filters in the event of an RHR leak following a IOCA (Section 15.1 of Supplement Ib. 2).
(13) We require that the applicant provide a armitment to certain additioml restrictions on fuel storage and cask hmiling if he is to store spent fuel in a location where it could be danaged by a dropped fuel cask (Sections 9.2.3 and 15.2.2 of Supplanent' lb. 2).
(14) We require information justifying the assumed limited break size used in the subcompartment pressure analysis for the reactor vessel cavity (Section 6.2.1 of Supplerent 16. 2).
+"m4:6 (15) We require re-analysis of the subconpartment pressure for a pipe break in the reactor coolant pipe penetration of the bio-logical shield, or, alternately, verification that the stress levels and usage factors are low so that the break need not be assumed (Section 6.2.1 of Supplement 16. 2).
(16) We are evaluating the applicant's subnittal regarding physical separation in the process analog systen (Section 7.2.3 of Supplanent 1b. 2).
(17) We are evaluating the applicant's subnittal regarding the recent guidance in certain WASH documents pertaining to the operational quality assurance program (Section 22.0 of Supplement Ib. 2).
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MAY 081975 ATTACRENT B ISSUES A?O CONCERFE RESOLVED BY STAFF POSITION TO BE IMPOSED ON THE APPLICA?If DIABID CANYON UNITS 1 AND 2 Issues and Concems that will be resolved by a staff position imposed on the applicant where we do not accept the applicant's design. 16 further information is required for these items.
(1)
We require the applicant to utilize the standani equations for detemining plume parameters and relative concentration values in his control rxxxa meteorological ronitoring program for post accident coniitions (Sections 2.3.3 and 2.3.6 of Supplenent Ib. 2).
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