ML20128C833

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Summary of 710915 Meeting W/Util to Discuss Change 2 to TS of Plant Re Waste Gas Sys.List of Attendees Encl
ML20128C833
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 09/21/1971
From: Benaroya V
US ATOMIC ENERGY COMMISSION (AEC)
To: Boyd R
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212040541
Download: ML20128C833 (2)


Text

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$[P 21 1971 Roger S. Boyd, Assistant Director, BWR, Division of Reactor Licensing TRRU: Donald F. Knuth, Chief, BWR-1, Division of Reactor Licensing 1TETING WITil NORTIIERN STATES POWER COMPANY (HSP) - l'ONTICE110 GENERA 11NG F1 ANT (E-5979), CONCERNING TECil SPEC CllANGE NO. 2 - WASTE GAS SYSTE!l, DOCKET No. 50-263 Sunnn ry A meeting was held on September 15, 1971, with NSP to discuss Change tio. 2 to the Technical Specifications of the lionticello plant. An attendance list is attached. ,

Change No. 2 consists of proposed modifications to the gaseous radwaste system. The proposed system consista of redundant hydrogen recombiners and compressors, and 5 gas storage tanks which will hold gases at 300 psig.

We proposed modification will increase the holdup time of the condenser air ejector non-condensable gases from 30 minutes to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.

The meeting was held at the request of the licensee to clarify the questions raised on this subject.

Discussion in our previous ineeting with the applicant on the same subject, we had informed them that we would need additional information to complete our review. W e first set of questions was sent on June 3, 1971. The appli-cant asked for this meeting to clarify some of our concerns. The follow-ing items were discussed.

1. We need an evaluation which shows that a hydrogen-oxygen explosion will not affect the integrity of the compressors or equipment down-stream of the compressors. The applicant is designing the equipment to survive such an explosion up to the compressors.
2. Actual data taken at the site should be used in calculating doses from postulated accidents and for normal releases. This will require a considerable amount of effort, since the PSAR considered elevated wind speeds only, i

t 3. C: led.:tien :' d:::.: :b::!d be 5::co en 10 C" Pest 20 "~8e (8-SA&9: Lating doses,7, > eta and ,gansas activities areadditives{.

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Ont> . . . .

Fbrm A EC.818 (Rev. 948)

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U,s. 6cvtanutut emat u.6 ormt .nse- oas4 See 9212040541 710921 PDR P ADOCK 05000263 PDR

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j Roger S. Boyd 2 $(P 21 197f 1

$ 4. The probable halogen concentrations should be calculated and the con-

! sequences evaluated. i I

! 5. Even though Appendix I does not consider radiation from the turbine j building, a survey should be conducted at the site, and the actual dose measured. At this time, this dose need not be included in  !

j calculating the dose at the site boundary.  !

6. An equipment failure analysis should be performed and the conse-

] quences evaluated.

t

) 7. The proposed changes to the Technical Specifications will be dis-

cussed at a later date, in conjunction with other changes being

! considered now.

j .erisinal signed by j vieler senereye j Victor Benaroya, Project leader l Boiling Water Reactors Br. No.1

{ Division'of Reactor Licensing i

Enclosure:

i Attendance List

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i

_ Distribution
Docket i DRL Reading  ;

i BWR-1 File ,

l PAMorris, DRL

FSchroeder, DRL Asst. Diuretors, DRL j EGCase, DRS--

1 RRMaccary, DRS l HDenton, SERSG l Br. Chiefs, DRL/DRS Compliance (2)

SMKari, DRL VBenaroya, DRL Attendees, AEC 7

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VBenaroy is

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om > ...9/20 ni, lbrm A EC.318 (bv. 9-63) 41AlHL u.t Govtputwf Pamtma ostet ant-o ,s.4ss i

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