ML19221A001
| ML19221A001 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/16/1969 |
| From: | Tedesco R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7905160477 | |
| Download: ML19221A001 (3) | |
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CfVs M*d W Peter A. Morris, Director, Division of Reactor Licensing F a" L : -
TERU: R.ager S. Boyd, Assistant Director for Reactor Projects, ORL REPORT TO ACES ON TEREZ MILE ISL.L';D UNIT 2 in our report to the ACRS regarding our review of the Three Mile Island Huclear Power Station Unit No. 2 (TMI #2), we have iden-tified several matters which still re=ain to be resolved. *hese matters can be resolved following issuance of a ecustruction permit because they are either (1) items of a general nature gener1c to this class of reactor plant or (2) additional infor=a-tion not yet available is necessary to resolve these natters on a quantitative basis. The applicants are aware of our views on these satters. We expect to resolve these matters within a year following issuance of the construction permit.
Those matters of a general concern to this class of light water reactor plants are:
(1) design loadine conditions, testing asnects on the vent valves and confirnatorv vibrational test erogram This is a standard 3&W research and develop =ent ite:s.
(2) pressure vessel surveillance orocra:s The applicants have indicated that they are participating in an integrated Babcock & Wilcox pressure vessel surveil-lance program. The extent and adequacy of participation vill be determined during our post-ccustruction permit review.
(3) ECCS initiation signal diversity The aplicants have indicated that ECCS diversity may not exist for primary piping breaks of 0.4 ft2 and that none is needed. The applicants have not provided sufficient
.mmlysis of braah less than 0.4 f t2 to support their conclusion. We vill review this =atter with thes during the post-construction permit review period.
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(4) iodine removal effectiveness Iodine removal effectiveness following an LOCA has been based uoon the use of albline sodium thiosulfate. Since i
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-2 the sodium thiosulf ato spray additive is an R&D ites which is being rev1_
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The appiteants have =ade co=it=ents to provide alternatives such as reducing contaic=ent leah rate or installing an internal recirculation filter systas to get the necessary iodine reduction factors to =eet 10 CFR Part 100 guideline values.
(5) affects of radiolvsis The applicants have proposed to control the radiolytic hydrogen concentration in the containment building fol-Icving the LOCA by purging to the atmosphere in order to =aintain the hydrogen concentration below the flam-
= ability limit. In addition, the applicants have made a ecx= tit =ent to provide other naans of control such as reccabiners or catalyst if purging is not acceptable.
This is a generic review and resolution =atter.
(6) steam generator tube failure ceincident with au LOCA We have infor= ally asked the applicants to analyze this accident considering the effects of steam back-flov to the pri=ary system and its ef f ects on ECCS. This problem (steam binding) was not considered in our IMI #2 review.
The =atters of particular concern for TMI #2 that vill require resolution as the necessary infor=ation becomes available are:
(1) flood protection requirements 3e U. S. Corps of Engineers have just coc:pleted the analysis of the probable maximum flood (?MF) for the Susquehanna River at the TMI site. This FMF vill not become officially accepted by the Corps of Engineers until June 1970. The applicants are aware of the increased PMF and have indicated they will nake co=mit=ents to protect the TMI site for the official Corps of Engineers FMF.
(2) environmental =onitoring erogram The Fish & Wildlife letter has not been received, hov-ever, we have discussed the reca=sendations of the Fish & Wildlife with the applicants infor= ally and CFT!CZ > ;l i
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they have indicated they would have no problem in ecoplying with these recensendations. This natter should be resolved prior to the public hearing.
(3) tendon anchorare desien and surveillance crocran We have indicated to the applicants that instrunentation embedded in the concrete to nonitor the reactor buildint; vould be required to provide early indication of any detarieration of the 3 routed tendens.
n e applicants are proposing to use one offour types of grouted tendon anchorages. Only the 33R7 anchorage syste:n has been reviewed and accepted by OPl.
We inforned the applicants that the anchorage systen
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they selected and the final details of the surveillance program would need to be reviewed and approved by us prior to construction.
(4) analysis and inscection of fivvhe(1s We have informed the applicants that we vill require 100% volumetric inspection of the flywheels during fabrication, their analysis of the effects of earth-quake loading, and inclusion of the flywheels in the plant's inser71ce inspection program. The applicants had originally planned only to perforn a surface inspection of the flywheels.
(5) inservice inspection provisions We have inferned the applicants ti.at they will be required to review with us the st.atus of plans and provisions for inservice inspection progran within about six months of issuance of the construction permit.
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(6) leakage detection Docket Fila DRL Reading We have requested the applicants to review their leak RF3-2 Reading detection systems regarding design criteria for sensi-
- 3. Grines tivity in relation to leak sizes and response ti:ne.
3 ranch Chiefs, RF his vould be reviewed during the post-CP period.
Originu ;;g.cJ, j Robert L. Tedmen R. L. Tedesco, Chief, RP3-2 ca._
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