ML20245A276
| ML20245A276 | |
| Person / Time | |
|---|---|
| Issue date: | 03/04/1987 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Sniezek J Committee To Review Generic Requirements |
| Shared Package | |
| ML20235F344 | List: |
| References | |
| NUDOCS 8703090333 | |
| Download: ML20245A276 (2) | |
Text
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p' r . MAR 0 ( 1987 MEMORANDUM FOR: James H. Sniezek, Chairman Comittee tc Review Generic Requirements.
,. FROM: Harold R,' Denton, Director Office of Nuclear Reactor Regulation i
SUBJECT:
PROPOSED NEW STAND /RD REVIEW PLAN 6.5.5, " PRESSURE SUPPRESSION POOLS AS FISSION PRODUCT CLEANUP SYSTEMS"-
The Committee considered the subject SRP at its 109th meeting on February 9, and its minutes of thiL meeting were received by the cognizant branch on February. 19, 1987 Five-recommendations were made by the Comittee as indicated below, each one.followed.by NRR'r, response:
(1) If increased fission product concentrations in the suppression pool are-acknowledged, then the effect on the environmental qualification of equip-ment and access to equipment durino an accident should be addressed.
We agree, and expect that future revisions to SRP 15.6.5, Appendix B, and Regulatory Guide concentrations in BWR1.89 willwater.
cooling address A thegst-accigt N' *r^- fissionprpdg g' "'7 '~'y 4 '
i d u,m E (2) SRP 6.5.5 and R.G.1.3 are inconsistent. They should both be revised in !
final form at the same time and, by so doinn, ba made consistent. This {'
correlation should be indicated when the SRP is issued for comment.
A revision'to Reuulatory Guides 1.3 and 1.4 is in progress, and this fact will be stated when the SRP is issued for comment. /N< f dav ( !
1 (3) AI ARA considerations vs. system safety requirements should be balanced.
As a minimum, there should he a recognition of AlARA concerns.
Although offsite doses calculated as a result of postulated accidents are not required to be as low as reasonably achievable (ALARA), a balancing of such considerations can enter into the evaluation of ESF filtration systems,- ,
espef ally in reoard to the savings in occupational dose as a result of reduc sd filter testing and change-out vs. the system safety requirements in thn f t m of slightly lower but stil' highly effective removal efficiencies.
The SR. has been m a C 4 '*^7
,,a.4 to afscm.s Ag odi %fied lum m, reccanition of ALARA concerns.W s H s k M w A tmto i nclur.'i M 77 c i (4) It should he made clear that the burden of proof ;hould be on the anpli-cent if DFs above the co .servative allowables are used.
We agree, and the proposed section has been rewnrded te so indicate j c4 /M Pevisiore to allowahle containment leakace rates should be handled I)
Separately as part of the siting, source term or containmer t performar're r ri + 'a efforts. .-
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JamesH.[Sniezek 2 g ;; g 1937 i Atlthe CRGR meeting, the Committee agreed that the staff's position that it would not favorably entertain reouests by. existing plants to increase l! containment leakage could be stated in the cover letter distributing the
, section for comment. This will be done. tur, i. 6 A - ,rA .ys t1/tf f
a % Mi O SJ % be bn 6 s,.9 sy.ca,-.,s A 77 OnLFebruary .l?th, we were informed by RES that an experiment by its contractors, intended to validate the sourct term code: package treatment of. suppression pool scrubbing, had unexpected results. It may be.that Mark !!! horizontal vents ~
would be less effective than had been supposed during some phases of the most severe accidents. These preliminary indications may or may not provc valid, and may or may not bear upon accidents for which the proposed SRP section may reasonably be applied. We will pursue and resolve this issue prior to returning ,
tn CRGR and ACRS following public comment. c m 2 4 e .j. m.s4 D d&<.
. .r Harold R. Denton, Director Office of Nuclear Reactor Regulation DISTRICT l TION Central File DSRO'r/f RlB r/f VStello EBeckjord
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