ML20129E392
| ML20129E392 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/27/1985 |
| From: | Stern S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8507160804 | |
| Download: ML20129E392 (5) | |
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h, UNITED STATES y
g NUCLEAR REGULATORY COMMISSION
'- l WASHINGTON, D. C. 20555
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JUN 2 71985
. Docket to. EO aff AFFLICANT: Gulf Station Utilities FACILITY:
River Bend Station, Unit No. 1
SUBJECT:
CONVERSATION WITH DR. D. OKRENT ON DEFERRAL OF ACRS fEETING ON RIVER BEND STATI0fl SU W RY On June 9,1985, the staff discussed with Dr. Okrent and f1r. Savio of ACRS progress in preparation for the scheduled July ACRS meeting on hydrogen control at River Gend Statico (RBS). ACRS had earlier requested both applicant and stoff to present to their assessnent of the hydrogen control issue to support ACRS reccnendation for a full power license at RBS.
The pro. lect c6 nager, Mr. Stern, informed the ACRS that due to substantial slippages in the applicarts' submittals on hydrogen centrol, the staff could not support a July ACRS meeting. All parties agreed that once the dpplicant submittec the required inputs to the staff, the staff woulo review these inputs for adequacy and reschcdult the r.ieeting.
EACK6RCUhD On July 17, 1964, the ACRS issued a letter to Chairnian Falladino stating that RBS "...can be operated at power levels up to 5% of full power withcut undue risk to the health and safety of the public" (Enclosure 1).
However, ACRS stated that they would complete their review of full power operating license when both the ap)licant and staff had made sufficient additional progress in resolving tie matter of hycrogen control.
On February 1, 1985, GSU informed the staff in writing that GSU would submit the results of the CLASIX-3 Computer Coce by February 15, 1985 and the results of liroited equipment survivability analysis by March 15, 1985 (seeEnclosure2). Both items are necessary for the staff assessment of hydrogen control issues for River Bend.
8507160904 850627 PDR ADOCK 05000458 A
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The applicant had not yet submitted these inputs to hRC as of Jurie 6,1985.
In addition, the staff requested at least one nonth to assess hydrogen control at River Bend atid the ACRS requires written staff assessnent two weeks in advance of the subcomittee neeting to revius this issue. Therefore the staff will not be able to support a inid-July ACRS meeting. This meeting will be scheduled following the staff's assessitent of GSU's submittals regarding this issue and pending Dr. Okrent's availability.
%1oni sifmed by:
Stephen Stern, Project Manager Licensing Branch No. 2 Division of Licensing
Participants:
NPR ACRS U Stern D. Okrent C. Stable Savio R. Hernan cc:
H. Denton H. Thompson D. Okrent R. Savio C. Stable T. Novak W. Butler A. Notafranasco, CSB J. Kudrick, CSB
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DISTRIBUTION
- Docket File LB#2 Reading EHylton SSter Rfuoe IDL
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- Rilernan WButler 06/24/85 06/21/85 06gde'85
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r The applicant had not yet submitted these inputs to fiRC as of June 6,1985.
In addition, the staff requested at least one month to assess hydrogen control at River Bend and the ACRS requires written staff assessr.ient two weeks in advance of the subccmittee meeting to review this issue. Therefore the staff will not be able to support a mid-July ACRS neeting. This reetir.g will be scheduled following the staff's assesstent of GSU's submittals regarding this issue and pending Dr. Okrent's availability.
Stephen Stern, Project itanager Licensing Branch No. 2 Division of Licensing
Participants:
i.RR ACRS S. Stern D. Okrent C. Stable Savio R. liervan cc:
R. liernan D. Olkrent R. Savio C. Stahle H. Denton T. liovak W. Butler H. Thompson A. flotafracasco, CSB J. Kudrick, CSB DISTRIBUT10l4 Docket File LB//2 Reading EHylton SStern M(bV U@p}
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2-The applicant had not yet subniitted these inputs to NRC as of June 6,1985.
In 7.ddition, the staff requested at least one month to assess hydrogen control et River Bend and the ACh5 requires written staff assessment two wceks in advance of the subcomittee aceting to review this issue. Therefore the sta f d
will not be able to support a mid-July ACRS neeting. This meeting will be scheduled following the stuff's assessment of GSU's submittals reoarding this issue and pending Dr. Okrent's availability.
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tdph t i, Project Manager Licensing Branch No. 2 Division of Licensing Participarts:
- b. Stern D. Ukrent C. Stable Savic F. Ecrrian cc:
H. Denton H. Thompson D. Okrent R. Hernan R. Savio C. Stable T. f.ovak W. Butler A. Notafranasco, CSB J. Kuorick, CSE L
Mr. Willian J. Cahill, Jr.
River Bend huclear Plant Gulf States Utilities Ccrpr,y cc: Troy B. Conner, Jr., Esq.
Ms. Linda B. Watkins/lir. Steven Irving Conner and Wetterhahn Atterrcy at Law 1747 Pennsylver.ia Avenue, N. W.
355 Napoleon Street Washington, D.C.
20006 Baton Rouge, Louisiana 70602 Mr. Williara J. Reeo, Jr.
Director - Nuclear Licensing Gulf States Utilities Cornpany Post Office Box 2951 Beaumont, Tenas 77704 Fr. David 7aloudek Nuclear Energy Division H. Anne Plettinger Louisiana Department. of 3456 Ville I;ese Dr.
.Lnvironmental Quality Baton Roust., Lcuisiana 70806 Post Office Ecx 14690 Baton Rouge, Louisiana 70658 Richard M. Troy, Jr., Esc.
Assister,t Attcrney General in Charge Stctc cf Louisiana Department of. Justice E34 Loyola Avenue New Orlears, Lcuisiana, 70112 Mr. J. David McNeill,111 Dwight D. Cher:berl&in William G. Davis, Esq.
Resident Inspector Lepartu.ent of Justice Pest Office Box 1051 Attorrey Ger.eral's Office St. Francisville, Louisiana 70775 7434 Perkins Road Baton Rouge, Louisiana 70808 Gretchen R. Rothschild Louisianians for Safe Energy, Inc.
1659 Glenmore Aser.ce Baton Rouge, Louisiana 70775 Jarnes U. Pierce, Jr., Esq.
P. G. Box 23571 Baton Rcuse, Lcuisiana 70893 Mr. Robert D. Martin U.S. hRC, Region IV Parkway Central Pitze Building 611 Ryan Plaza Drive, Sutie 1000 Arlington, Texas 76011
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UNITED STATES
- 8 NUCLEAR REGULATORY COMMISSION o
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.I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20555
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July 17, 1984 Honorable Nunzio J. Palladino s
Chaiman U.S. huclear Regulatory Comission Washington, D.C.
20555
Dear Dr. Palladino:
SUBJECT:
ACRS INTERIM REPORT ON RIVER BEND STATION During its 291st meeting, July 12-14, 1984, the Advisory Comittee on Reactor Safeguards reviewed the application of Gulf States Utilities Company (Applicant), acting on behalf of itself and as agent for the Cajun Electric Power Cooperative, for a license to operate the River Bend Station.
A tour of the facilities was made by members of the Subcomittee on the morning of June 7,1984, and a Subcomittee meeting was. held in Baton Rouge, Louisiana on June 7 and 8, 1984 to consider the application.
During our review, we had the benefit of discussions with representatives of the Applicant, the NRC Staff, and members of the public.
We also had the benefit of the documents referenced.
The Comittee. comented on -the construction permit a'pplication for this
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Station in its report dated _ January 14, 1975.
The River Bend Station is located in West Feliciana Parish, Louisiana on the east side of the Mississippi River approximately 24 miles north-northwest of Baton Rouge.
Originally the River Bend Station was to consist of two units.
Unit 2 was cancelleo on January 5,1984.
Unit 1 is approximately 90% complete, with an estimated fuel load date of April 1985.
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The River Bend Station uses a General Electric BWR-6 nuclear steam supply system (NSSS) with a rated core thermal power of 2894 MWt and a Mark III pressure suppression containment system with a design pressure of 15 psig.
l The Applicant has structured its organization, and has provided for
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continuity from project initiation up to and including operation, in a notable manner.
This structuring is along project team lines and appears to have provided good control and interfacing among the utility, the general contractor-architect engineer, and the NSSS designer.
Further, it appears this structuring has provided this first time t
nuclear utility with good personnel development for the utility's overall nuclear plant responsibilities.
In addition to this, the
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Honorable Nu'nzio J. Palladino July 17,1984
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Applicant has practiced aggressive recruiting and careful selection of qualified people ano has phased them into the project in a timely manner.
The dedicated diesel generator that drives the high pressure core spray pump currently depends on cooling water supplied by pumps powered by the other two diesel generators during loss of offsite power conditions. We recomend that the merit of removing this dependency be examined.
The Applicant stated that they plan to conduct a limited probabilistic risk assessment (PRA) for the River Bend Station.
We support the proposal to perform a plant-specific PRA and recomend that it include seismic-and fire-induced accident scenarios.
Although River Bend is in a relatively quiet seismic portion of the country, NRC contractor estimates of the recurrence interval for the safe shutdown earthquake are similar to those for most eastern sites.
We recomend that the Appi! cant review, in detail, the seismic capability of the emergency AC power supplies, the DC power supplies, ana small components such as actuators, relays, and instrument lines that are part of the decay heat removal system.
The Applicant has proposed to include in the River. Bend Emergency Procedures a procedure for venting the containment under certain accident conditions.
The bases for the decision to take this action are not yet clear.
The NRC Staff has not completed its review of this proposal.
We wish to be advised 'when the NRC Staff has reached a position on this matter ano to have an opportunity to coment generically or specifically.
The NRC Staff has identified a number of license conditions and con-firmatory matters, and several outstanding issues which remain to be resolved.
Except for the matter of hydrogen control, we are satisfied with progress on the other topics and believe that they should be resolved in a manner satisfactory to the NRC Staff.
We have not completed our review Jf hydro 5en control for the River Bena Station, particularly as it may be impacted by differences in containment design features between River Bend and Mark III BWRs previously reviewed.
The Comittee will complete its review of the full power operating license when the NRC Staff and the Applicant have mace sufficient additional progress in resolving the matter of hydrogen control.
In the interim, we believe that if due consideration is given to the recom-mendations above, and subject to satisfactory completion of construc-tion, staffing, and preoperational testing, the River Bend Station can
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Honorable Nunzio J. Palladino July 17, 1984
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be operated at power levels up to 5% of full power without undue risk to the health and safety of the public.
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Jesse C. Ebersole Chainnan
References:
1.
Gulf States Utilities Company, " Final Safety Analysis Report, River Bend Station," Volumes 1-18 and Amendments 1-11 2.
U. S. Nuclear Regulatory Commission, " Safety Evaluation Report Related to the Operation of River Bend Station," NUREG-0989, dated May 1984 m=
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f nelosure 2 O
e6b GULF STATES UTILITIES COMPANY
-POST OFFICE BOr 295;.OEAUMONT TEXAS 77704 AR f A COUE 409 838 6631 February 1, 1985 RBG-20062 File No. G9.5, G9.8.6.2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, P. C.
20555
Dear Mr. Denton:
River Bend Station-Unit 1 Docket No. 50-458 Enclosed is the Gulf States Utilities Company (GSU) response to Safety Evaluation Report (SER) Confirmatory Item #19 - Hydrogen Control (SER Section 6.2.5, Page 6 -32/33.).contains.the GSU endorsements for various Hydrogen Control Owners Group (HCOG) submittals.
These letters should be utilized to provide background and reference material for SER Confirmatory Item #19. Attachment 2 contains a revision to the Request for Additional Information (RAI), on the Hydrogen Ignition System (HIS) transmitted to W. J. Cahill (CSU)/ by A.
Schwencer (Nuclear Regulatory Commission - NRC) on DecGaher 2I 1983 and y
supercedes the original GSU response from J. E. Booker (GSU) to H.
R.
Denton (NRC) dated December 30,1983 (GSU Letter No. RBG-16679).
Enclosure I contains a revised response to FSAR Question 480.40 (Section 6.2) providing additional information on a RBS-specific Hydrogen Control Program. An FSAR description of the Hydrogen Ignition System based on the information noted above' will be provided to the Staff by March 29, 1985.
In addition, GSU will submit the results of the CLASIX-3 Computer Code (used to predict containment temperature and pressure) by February 15, 1985.
Also the results of a limited equipment survivability analysis and a specific program plan addressing the generic HCOG efforts will be provided by March 15, 1985.
Si erely.
-pk J. E. Bo r
Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group JEB/WJR/JWL/kt Attachments (2) l Enclosure (1)