ML17037C349

Letter Regarding the Application Proposing a Power Increase and Requesting Additional Information Necessary for the Commission to Complete the Evaluation

ML17037C349
Person / Time
Site:	Nine Mile Point
Issue date:	09/25/1970
From:	Morris P US Atomic Energy Commission (AEC)
To:	Pratt M Niagara Mohawk Power Corp
References
Download: ML17037C349 (10)

Text

DISTRIBUTION W. Dooly, DR R. Engelken,,CO (2)

H. Shapar, OGC J. R. Buchanan, ORNL 8~I'5 1970 PDR,

~ocket File DR Reading DRL Reading Docket No. 50-j220 Branch Reading ACRS (3)

F. Schroeder, DRL Niagara HohaT>k Power Corporation D. J. Skoyholt, DRL ATTN: >h. Knot H. Pratt D. L. Ziemann, DRL Vice President and C. J. DeBevec, DRL Executive Engineer R. M. Diggs,'RL D. Thompson, DRL 300 Erie Boulevard West R. H. Vollmer, DRL Syracuse, Ncv York 13202 E. G. Case, DRS Gentlemen In revieving your application dated April 20, 19/0, which proposes a pover increase for the Nine Nile Point Nuclear Station (N:P), TFo find that additional information is necessary to complete our evaluation.

The specific information requested is described in the enclosure.

Xn addition, ve note that Provisional Operating License {POL) No. DPR-17 for MP Trf.ll expire on February 22, 1971, or upon the earlier issuance of a full-term license. Please indicate your plans regarding the application for a full-term license, including your schedule for submission.

.Please contact Messrs, C. DeBevec or D. L. Ziczmnn of if you desire addi-information tional discussion or clarification of any the requested.

Sincerely, prig~no( signed i',

Pefer A. Morris Peter A. Yurris, Director Division of Reactor Licensing I

Enclosure:

Request for Additional

, Information cc: Arvin E. Upton, Esquire LcBoeuf, Lamb, Leiby 6 MacRae OFFJCE> ......-.JUL...................D . RL......... ....................DRL.......

SURNAME > .Cgegeeec~jg/. 1.... eggs.... ...DLZiemann.... .DJSka halt......E c aedsr...

DATE > .9/25/70.............9/X./20 .. .9/.25.../70.. 9/....../7Q....986 ./70 ....

Porrgr hEC-318 (Rsv. 9-53) IAS,GOYERNNCNTPRINNNG OrjjCGslgg&0-ggs+Gg

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RE UBST FOR ADDITIONAL INFOIQQTIOH PERTAINING TO APPLICATION FOR POWER INCREASE OF NINE tO;LE'POINT NUCLEAR STATION 1, Our review of the proposed instrumentation modifications indicates that the turbine control valve fast closure scram can be defeated by failure of a single acceleration relay and that physical inde-pendence Xs not apparent fox the four redundant pressure mritchos which respond to tuxbine first-st'age pressure and effect the auto-matic removal of tho bypass at pover levels above 45% of design rating. Provide additional information Justifying, or modifying, the proposed turbine contxol valve fast closure scram circuitry and describing tho physical independence of the turbine first-stago pressure sensors.

2. The information Trhich you submitted by letter dated July 2, 1970, is insufficient to por'mit evaluation of the effects of failure of a pressure oossol nozzle safe end on the biological shield or shield plugs. In this regard:

a. Provide details of construction and appropriate detailed sketches of the biological shield aud its load-bearing steel membered'ndicate the assumptions mado and the calculational methods used to determine the capability of the shield to withstand an internal pressure og 96 ps%.

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b. Describe the cal'culational methods, including the venting assumptions, and the transient pressure distributions, which vore used to deteWine that the maximum pressure rise in the biological shield in the event 'of a postulated double-ended bre'ak of a rod.rculation line at the safe end is approximately 40 psi.

c. Provide an analysic of 'thb effects"6f a brcak of the pressure vessel recirculation'ozzle safe end on the shield wall and on the shield gates at the penetrating pipes. Consider the potential for generating missiles or )ot forces which .could Jeopardize tho integrity of tho containment shell, or engineered s'afety system-components, OFFICE+

SURNAME y DATE ~

FOrm AEC-31S (Rev. 9-SS) US.COYERNNENTPRLNIlNGOFHCCU9I% O-30t<98

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0 Docket Mo. 50-220 Niagara Vohavk Pover Corporation ATTN: lfr. Mnot H. PraCC Vice President and Executive Engineer 300 Eric Boulevard Pest Syracuse, Hev Yorle 13202 Gentlemen>

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In revieving your application dated April 20, 1970, vhich proposes a pover increase for the Nine Bile Point Nuclear SCation (%P), ve find Chat additional information is necessary to completo our evaluation.

The specific information requested is described in the enclosure.

In addition, ve note that Provisiona1 Operating License QPOL) No. DPR-17 for RP vill expire on r 1971 or u on Che earlier issuance f a full-tern license. guidance

+Z application for a fu -cern license sAyW/iy,~ h fI';(/~~ ig~~,

J p Ay pad host oh A f ttQ+

1. The application should provide a ctailed reviev of the

~4~ bases and ob)ectives, and the si nificance af lant Get problems that, have occurred and the remodial actions taken. It should discuss significant changes that have

'been made Co the facility or ta operating procedures since the Pinal Safety Analysis -'Report vas prepared; hovever, it is nat necessary Co include extensive details of design and analysis of changes that previously have bann subtdttad to thn Conntsofon for approval.

2. Tho opp]fcation should distuaoptho adaquaoy of your organization during the POL period, including onsite staff, technical support groups and advisory committees,

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Niagara MohaTrlc Pox'er Corporation - 2-PO~V- dd(On~ i~ WF+

3, The status ef<previous comments and recommendations by the AEC and the Advisory'ommittee on Reactor Safeguards

.,concerning RlP should also be discussed in your appli-I cation.

i.l +4 IS informatio by specific reference to infornation already submitted or

'4 b ng su tted in sup ort of the currently proposed pouor increase.

Wlc-as o~rovi~~Ioly~ic4440n~ f your plans regarding the application for a full-term license,

~nay including schedule e@suhudssdcnk blesse ccncscc Unseen.

C, DeBevec oz D. L Ziemann if ou desire additional discussion or clarification.oP~- tt ~;~drKtinnnl-epbmkel- requestedFiTT=

M~nehmm~

Sincerely, Pus Peter A. Morris, Director Division of Reactor Licensing

Enclosure:

Request for Additional DISTRIBUTION Information W. Dooly, DR R. Enge1ken; CO (2) cc" Arvin E. Upton, Esquire H. Shapar, OGG Lohoeuf, Lamb, Leiby 6 MacRae J. R. Buchanan, ORNL 1821 Jefferson Place, N, U. PDR Baohington, D. C. 20036 Docket File DR Reading DRL Reading Branch Reading

'F. Schroeder, DRL AGRS (3)

D. J. Skovholt, DRL D. L. Ziemann, DRL C. J. DeBevec, DRL R. M. Diggs, DRL D. Thompson, DRL R. H. VO11mer, DRL E,g Q DRL DRL D DRL DRL DRL OFFICE Is W ~~

SURIIAME Is eBevec:s g. ~ggs........ DLZiemann J ov FSchroeder PAMorris DATE Is 9/23/70 9/A/70 9723/70,. 9/>. 70 9/ /70 9/ /70 porm h Hc-318 (Rev. 9-53) UA.COVERNMQITPRlglNG OFFIC41069 0-364<OS

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RE(GUEST FOR ADDITIONAL INFOEfATXON PERTAINING TO APPLICATION FOR POWER INCREASE OF NINE l'GLE POINT NUCLEAR STATION

l. Our review of the proposed instrumentation modificattions indicates that the turbine control valve fast closure scram can be defeated by failuge of a single acceleration relay and that Physical inde-.,

pendence is not apparent for the four redundant pressure s~ritches which respond to turbine first-stage pressure and effect, the auto-matic removal of the bypass at power levels above 45Ã of design rating. Provide additional information Justifying, or modifying, the proposed turbines control valve fast c1osure scram circuitry and describing the physical independence of the turbine first-stage pressuxe sensors.

2. Tho information which you submitted by lotter dated July 2, 1970, is insufficient to permit evaluation of the effects of failure of a prcssure vessel nozzle safe end on the biological shield or shield plugs. In this regard:

Provldo datadls ox constructdon and appropr1ata ~dotailcd sketche~fstjje biological shield and its loaearing steel members , ha assumpt1ons made andgcalculatdona1 motbods use to a~~t-internal pressure of qapability of the shield to withstand an, 96 psi.

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transient press xo distribu iona uhich vore a to

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Describe the+erne, including the venting assumptions,>the nrN" e c cu o ..ethods pressure rise in the biological shield in the event of a postu; lated double-ended recirculation line appuomduatalx dD ps

~- at the safe end is X'xovide an ana1ysis of the effects of a broalc. of the pxesoure vessel recirculation. nozzle safe end on the shield vali',and, on the shiold gates at the penetrating pipes. Consider the.

potential for generating missiles or )et forces which..co~ld jeopardize the integrity of the containment shell, or engineered system components.

ma OFFICE >

SURNAME p DATE >

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