ML20154J406

Summary of 880414 Meeting W/Representatives & Contractors of Licensee in Rockville,Md Re 870605 Amend Application for Util.Highlights of Discussion Listed.Nrc Indicated That Request for Addl Info Would Be Prepared If Needed

ML20154J406
Person / Time
Site:	River Bend
Issue date:	05/17/1988
From:	Paulson W Office of Nuclear Reactor Regulation
To:	NRC
References
NUDOCS 8805260337
Download: ML20154J406 (20)

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,b, UNITED STATES NUCLEAR REGULATORY COMMISSION js e WASHINGTON, D. C. 20555 o May 17,1988 Docket No. 50-458 LICENSEE: Gulf States Utilities Company FROM: River Bend Station, Unit No.1

SUMMARY

OF APRIL 14, 1988 MEETING On Ari i 14, 1988, members of the NRC staff and representatives of Gulf States Utilities Company (GSU) and their coi.'.ractors met in Rockville, Maryland. The purpose of the meeting was to discuss GSU's .une 5, 1987 license amendment applict. tion for River Bend Station, Unit 1, that requests modification of the allowable average drywell area temperature, main steam tunnel area tem;,erature monitoring, and main steam tunnel temperature isolation actuation instrumentation setpoints. Enclosure 1 is a list of meeting attendees.

Enclosure 2 is c handout provided by GSU.

-The licensee stated that it is their intention to withdraw that portion of Attachment 3 to the June 5, 1987 amendmert reouest that deals with the terperature setpoints in the main steam tunnel (MST) south. The licensee indicated that the proposed technical specification values for the MST south did not consider use of the temporary unit coolers. GSU representatives stated that with this temporary unit cooler now being made permanent, there is no need to increase the setpoints.

The licensee sumrarized the ventilation in the MST north. Cooler trending shows a heat load of about 350,000 Btu /hr. in the MST north (analyses performed by the staff and confirmed by the licensee subsequent to this meeting show that this cooler heat load is about 600,000 Btu /hr). The licensee indicated that they had added insulation and revised the ducting to make the air flow better to reduce the maximum MST north in temperature. In addition, l the unit cooler was cleaned during the last refueling outage. The licensee l based the proposed setpoint on a 154'F calculated temperature assuming a 25 gpm leak in one hour, 148.5*F allowable temperature which icludes an error allowance, and a setpoint of 141*F which includes an allowance for setpoint drift.

i l The licensee also discussed the meeting agenda questions forwarded by the NRC's letter dated March 24, 1988. The highlights of this discussion are I sumarized below:

8805260337 880517 l hDR ADUCK 05000458 PDR l

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The model used for transient analysis of the PST was implemented in ,

the Stone & Webster Engineering Corporation proprietary computer program, THREED, described in Appendix 6B of the Updated Safety Analysis Report.

The design conditions for setting the leak detection process safety limit are based upon actual plant conditions for summer, with an assuned 25 gpm steam leakage over a one hour period.

The circulation rate of unit cooler HVR*UC8 is 18,000 cfm. The cooling capacity of this cooler is controlled by the temperature of the service water; the service water flow to the cooler is not regulated.

The HVR*UC8 cooler design includes a condensate drain which collects condensed moisture from the MST north in one of the common auxiliary building sumps.

• The volume of the MST north is about 26, 775 cubic feet as used in the subcompartment analysis.

The circulation rate of unit cooler HVT*UC11 is approximately 24,000 cfm for one fan operation and 34,000 cfm for two fan operation. The coeling capacity for this cooler is approximately 1,425,500 Btu /hr.

The cooling medium is chilled water. The cooling capacity is controlled by regulating chilled water to the cooler.

The recirculation cooler MR 86-000 3 consists of three closed loop freon cycle units with a total heat removal capacity of 50 tons.

Monitoring of any radiation leakage into the MST is provided by the turbine building radiation monitor (RMS-RE118). Turbine building exhaust ventilation is directed to the main plant exhaust duct which is monitored by RMS-RE125 and RE126.

The equipment located in the MST was environmentally qualified in accordance with NUREG-0588, Category I res uirenents.

During refueling outage 1, 86 weld examinations were performed in the MST of the total of 287 exams planned during the first ten year inspection interval. One indication was found in the ICS system. A base metal repair was performed and additional weld sampling was selected and examined. No additional indications were found in the added weld sample. The indication is believed to be a talent construction scratch or gouge.

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At the conclusion of the meeting, the staff indicated that a request for .

additional information would be prepared if there was a need for any further clarification of the information discussed during the meeting or if additional information needs are identified based on this meeting.

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Walter A. Paulson, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Encicsures:

As stated cc w/ enclosures:

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At the conclusion of the meeting, the staff indicated that a request for additional information would be prepared if there was a need for any further clarification of the information discussed during the meeting or if additional information needs are. identified based on this meeting.

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Walter A. Paulson, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION Docket or Central File NRC PDR Local PDR PD4 Reading J. Calvo W. Paulson 0GC-Rockville E. Jordan i

J. Partlow NRC Participants ACRS (10) l PD4 Plant File h-PDd fM WPa)ulson:sr 05//7/88

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• Mr. James C. Deddens Gulf States Utilities Company River Bend Nuclear Plant cc: .

Troy B. Conner, Jr. , Esq. Mr. J. E. Booker Conner and Wetterhahn Manager-River Bend Oversight 1747 Fennsylvania Avenue, NW P. O. Box 2951 Washington, D.C. 20006 Beaumont, TX 77704 Mr. Les England Mr. William H. Spell, Administrator Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Ccrpany Office of Environrental Affairs P. O. Box 220 P. O. Box 14690 St. Francisville, LA 70775 Baton Rouge, Louisiana 70P98 Richard M. Troy, Jr. , Esq.

Assistant Attorney General in Charge M; J. David McNeill, III State of Louisiana Department of Justice William G. Davis, Esq.

224 Loyola Avenue Department of Justice New Orleans, Louisiana 70112 Attorney General's Office 7434 Perkins Road Pesident Inspector Baton Rouge, Louisiana 70808 P. O. Box 1051 St. Frar.cisville, Louisiana 70775 H. Anne Plettinger 3456 Villa Rose Drive Gretchen R. Rothschild-Reinike Baton Rouge, Lcuisiana 70606 Louisianians for Safe Energy, Inc.

2108 Broadway Street New Orleans, Louisiana 70118-E462 President of West Feliciana Police Jury Regiont i Administrator, Region IV P. O. Box 1921 U.S. Nuclear Regulatory Commissien St. Francisville, Louisiana 70775 Office of Executive Director for Operat ions Mr. Frank J. Uddo 611 Ryan Plaza Drive, Suite 1000 Uddo & Porter Arlington, Texas 76011 6305 Elysian Fields Averue Suite 400 Philip G. Harris New Orleans, Louisiana 70122 Cajun Electric Power Coop. Inc.

10719 Airline Highway P. O. Box 15540 l

Baton Rcuge, LA 70895 l

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4-Enclosure 1 Attendance List April 14, 1988 Meeting .

Gulf States Utilities /NRC NAME ORGANIZATION W. Paulson NRC/NRR John Craig NRR/SPLB E. Earl Nichols, Jr. GE Licensing Ed Goodwin Stone & Webster Eng.

Vincent P. Bacanskas GSU DE/EQ Barry M. Burmeister GSU Licensing Donald R. Hoffman GSU Licensing Joseph Schippert GSU Operations Erwin J. Zoch GSU Engineering John R. Hamilton GSU Engineering Rick King GSU Licensing Jack Kudrick NRC/NRR/SPLB Robert Licciardo NRR/ DEST /SPLB Kris Parczewski NRR/ DEST /ECEB Frank C. Skopec NRR/DREB/PRPB Hulbert C. Li NRR/ DEST /SICB Don Katze NRR/ DEST /RSB Arnold Lee NRR/ DEST /EMEB Mark Hartzman NRR/ DEST /EMEB Harold Walker NRR/ DEST /SPLB

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GSU/NRC APRIL 14 1988 MEETING AGENDA 4

INTRODUCTION R. King PRESENTATION ON - PHYSICAL DESCRIPTION / LAYOUT of the MAIN STEAM TUNNEL J. Hamilton REASON AND DESCRIPTION of the PROPOSED CHANGES DESCRIPTION of MODEL CONCLUSIONS PRESENTATION ON THE RBS DESIGN BASIS OF 25 gpm E. Nichols ,

DISCUSSIONS OF NRC QUESTIONS IN ENCLOSURE 1 TO MARCH 24, 1988 LETTER Open G

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t-PURPOSE

• TO PRESENT AND DISCUSS GSU'S JUNE 5 1987 PROPOSED TECHNICAL SPECIFICATION REQUEST ON MAIN STEAM TUNNEL TDiPERATURE ISOLATION ACTUATION INSTRUMENTATION SETPOINTS.

ADDRESS NRC STAFF QUESTIONS AND AGENDA ISSUES IDENTIFIED IN A LETTER DATED MARCH 24, 1988.

OBTAIN A GENERAL AGREDfENT BETWEEN GSU AND THE NRC STAFF ON THE PROPOSED CHANGE.

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MAIN STEAM TUNNEL ISOLATION SETPOINTS

1. REASON FOR REQUEST II. SYSTEM DESCRIPTION III. DESCRIPTION OF MODEL IV. CONCLUSIONS i

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i REASONS FOR CHANGE Steam Tunnel temperatures are about 10'f higher than the values predicted in 1982.

Risk of unnecessary isolations and scrams increased probability of challenging safety systems Nuisance alarms ,

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SETPOINT AND TEMPERATURES MST - NORTH '

RECORDED OPERATING TEMP.

AREA DELTA TYPICAL WINTER 105 39 EXTREME (1988),F TYPICAL SUMMER 132 22 EXTREME (1987),F TECH _ SPEC VALUES CURRENT PROPOSED AREA DELTA AREA DELTA INITIAL TEMP. 105 ---

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FOR CALCULATION,F CALCULATED PROCESS 148 59 154 65 SAFETY LIMIT,F TECH. SPEC. 142.5 55 148.5 61 ALLOWABLE VALUE,F l TECH SPEC. 135 51 141 57 SETPOINT,F l

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W PURPOSE OF TEMPERATURE MONITORS 2

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! To provide Control Room Alarm of a 1) steam leak.

2) To automatically isolate a leak of 25 gal / min or larger.

CONTAIN MEUT

. h s HAtW STEAM (3 L , TUN'l M06TH ()

sc E L ll'f '- O' HVR AUC8 s EL 42&-O' C>d EL 124'4" X EL 126'0

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NOTE: INSTR IN TuM'L NORTW' PREFIXED SY "lE31" INSTR IN TdW'l SOUTH PREFlxEP BY *1LDS" MST TEM PERA TORE DETEC TOR t. 0 C A T/C N S

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AS TOM Cnt TOTAL M ht h4 ST EA P1 S4 0,000 STU/ MR TuNkCL SO U T H /

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MAIN STEAM TUNNEL VENTILL ATION

DESCRIPTION OF MODEL .

(THREED.VER 12. LEV 06)

1) Calculates room temperaturas vs. time for given leak rate.

2) Input initial room temperatures.

3) Input HVAC flow rate.

4) Input HVAC supply temperatures.

5) Input heat sinks.

6) Analytical limit chosen as temperature l

obtained in one hour for a 25 GPM leak rate.

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SENSITIVITY TO SEASONAL VARIATIONS 1547 = PSL PSL = 657 STPT = 57F 1417 = STPT 1327 -

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CONCLUSIONS THE PROPOSED CHANGE:

1) Does not adversely affect safety-a) conservative leak detection design basis is maintained b) initial temperatures based on actual recorded temperatures providing for a modest setpoint increase ,

c) HVAC still modeled conservatively d) setpoints maintain margin to account for inst. accur, and drift e) redundant instrumentation exists for MST pipe breaks / leaks

2) Increases olant reliability by reducing the risk of unnecessary isolations and consecuent scrams.

3) Reduces the risk of unnecessary challenges to safety systems.

4) Eliminates nuisance alarms.

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GENERAL ELECTRIC COMPANY l1 e

LEAK DETECTION OUTSIDE REACTOR COOLANT PRESSURE BOUNDARY DESIGN BASIS

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GENERAL ELECTRIC COMPANY LEAK DETECTION DESIGN BASIS BASIS PHILOSOPHY LEAK BEFORE BREAK PROTECT ENVIRONMENTAL LIMITS LIMIT RADIOLOGICAL CONSEQUENCES REQUIREMENTS REACTOR COOLANT PRESSURE BOUNDARY (RCPB)

REGULATORY GUIDE 1.45 STANDARD REVIEW PLAN 5.2.5 0UTSIDE RCPB NO SPECIFIED REQUIREMENTS 2

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GENERAL ELECTRIC COMPANY LEAK DETECTION DESIGN BASIS BASIS RCPB 25 GPM - IDENTIFIED ,

5 GPM - UNIDENTIFIED OUTSIDE RCPB 25 GPM - RECOMMENDED ISOLATION TRIP 5 GPM - RECOMMENDED ALARM CONSISTENT WITN RCPB LEAK BEFORE BREAK CONFIRMATION RADIOLOGICAL CONCERNS BOUNDED BY MAIN STEAM LINE BREAK <

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