ML20236F817
| ML20236F817 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/24/1998 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9807020357 | |
| Download: ML20236F817 (59) | |
Text
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20086 0001 I
***** ~ June 24, 1998 LICENSEE: Entergy Operations, Inc.
FACILITY: GRAND GULF NUCLEAR STATION, UNIT 1 (GGNS)
SUBJECT:
PRESENTATION BY THE LICENSEE ON RISK MANAGEMENT FOR REFUELING OUTAGE NO. 9 FOR GRAND GULF NUCLEAR STATION, UNIT 1
. A meeting was held on Tuesday, March 31,1998, between the Nuclear Regulatory Commission (NRC) staff and the licensee for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The meeting was held at the request of the licensee to brief NRC on the licensee's risk management of the upcoming ninth refueling outage (RFO 9). This outage began on April 11,1998, and ended 40 days later on May 21,1998. The notice for the meeting was issued on March 19,1998.
Attachment 1 is the list of attendees, and Attachment 2 is the handout provided by the licensee at the meeting. The RFO 9 summary schedule as of March 29,1998, by month and day of the outage, is shown on pages 18 to 24 of Attachment 2. The end of Attachment 2, pages 48 to 54, provides a summary of the work planned for the GGNS RFO 9. The staff did not provide any handout at the meeting. The agenda for the meeting is the second page of Attachment 2. The licensee's presentation included an overview of the outage, the RFO 9 scope and schedule, the RFO 9 risk assessment, and the shutdown operations protection plan (SOPP). The seven key elements of risk management at GGNS are given on page 3 of Attachment 3. These elements include the review of key safety functions (KSFs), the use of the computer
/
/
program Outage Risk Assessment Management (ORAM) that was developed by the licensee in I the early 1990's, the shutdown cooling assessment for the outage, and the SOPP. The KSFs i are reactivity control, reactor vessel water inventory control, electric power availability, decay l heat removal, and containment control. ORAM does not include the potential events of loss of 1 power (LOP), fire, and loss-of-coolant accidents beyond the actual work being performed in the l outage, and these potential events are addressed separately in the independent safety l engineering oversight. Contingency plans for the risks identified for the outage are contained in the SOPP and in off-normal event procedures (ONEPs). ; Graphs of the reactor cooling system (RCS) boiling risk and core damage risk presented for l
' RFO 9 are given on pages 30 and 31 of Attachment 2. The graphs for RFO 9 are estimates l made from the scheduled work as of March 10,1998. The schedule of work in the outage would 1 be adjusted as needed to reduce and level the risk through the outage. This risk would be !
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continually reviewed throughout the outage as adjustments are made to include emergent work. ; A comparison of the average core damage risk for RFO 4 through RFO 9 is given on page 29. j The average core damage risk shown for RFO 4 through RFO 8 are for the actual work ' performed in the outages; the average for RFO 9 is based on the estimates of March 10,1998. The licensee discussed three special considerations for RFO 9 that are shown on pages 35 to 37' of Attachment 2. l The licensee completed its presentation and the meeting was closed. Based on the presentation, the staff concludes that the licensee has a robust administrative system in place to ! control risk during a refueling outage which is more than is required. Jack N nohew, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation l l r i ! Docket No. 50-416 Attachments: 1. List of Meeting Attendees
- 2. Licensee's Handout '
cc w/atts: See next page l
e
. 5 continually reviewed throughout the outage as adjustments are made to include emergent work.
A comparison of the average core damage risk for RFO 4 through RFO 9 is given on page 29. The average core damage risk shown for RFO 4 through RFO 8 are for the actual work performed in the outages; the average for RFO 9 is based on the estimates of March 10,1998. The licensee discussed three special considerations for RFO 9 that are shown on pages 35 to 37 - of Attachment 2. The licensee completed its presentation and the meeting was closed. Based on the
, presentation, the staff concludes that the licensee has a robust administrative system in place to control risk during a refueling outage which is more than is required.
I 67/WW ack N. Donohew, Senior Project Manager
, Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
. Docket No. 50-416 Attachments: 1. List of Meeting Attendees
- 2. Licensee's Handout cc w/atts: See next page DISTRIBUTION l Docket File PUBLIC PD4-1 r/f J.Donohew E. Adensam J.Hannon C.Hawes P. Gwynn (RIV)
OGC (15B18) ACRS . M. Rubin S. Burgess P. Wilson M. Shuaibi M. Wohl M. Pohida Document Name: GG033198.MTS OFC PM/Pld4M LA/PD4-1 DkM1b NAME JDordhb CHawe bnn DATE la /24198 h /.k198 hdI//98 l COPY YES/NO YES/NO YES/$Q OFFICIAL RECORD COPY 1
Ent:rgy Optretions, Inc. Grand Gulf Nuclear Station I cc: Executive Vice President General Manager, GGNS
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 756 P. O. Box 31995 Port Gibson, MS 39150 Jackson, MS 39286-1995 Attomey General Wise, Carter, Child & Caraway Department of Justice P. O. Box 651 State of Louisiana Jackson, MS 39205 P. O. Box 94005
, Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer Washington, DC 20005-3502 State Board of Health P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural Office of the Govemor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 '
Jackson, MS 39209 Attomey General President, Asst. Attomey General Claibome County Board of Supervisors State of Mississippi P. O. Box 339 P. O. Box 22947 Port Gibson, MS 39150 Jackson, MS 39225 Regional Administrator, Region IV Vice President, Operations Support U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 1000 P.O. Box 31995 Arlington, TX 76011 Jackson, MS 39286-1995 Senior Resident inspector Director, Nuclear Safety U. S. Nuclear Regulatory Commission and Regulatory Affairs P. O. Box 399 Entergy Operations, Inc. Port Gibson, MS 39150 P.O. Box 756 Port Gibson, MS 39150 Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc. P. O. Box 756 Port Gibson, MS 39150
4 .g i LIST OF ATTENDEES AT MEETING OF MARCH 31.1998 GRAND GULF NINTH REFUELING OUTAGE SCOPE N_A._ME AFFILIATION J.Donohew NRC/NRR/PDIV-1 J.Hannon NRC/NRR/PDIV-1 S. Burgess NRC/NRR/SPSB P. Wilson NRC/NRR/SPSB M. Pohida NRC/NRR/SPSB M. Shuaibi NRC/NRR/SRXB M. Wohl NRC/NRR/SPSB W. Hughey EOl - Grand Gulf J. Booth EOl - Grand Gulf R. Ingram EOl- Grand Gulf l 1 i where: EOl = Entergy Operations, Inc. NRC = Nuclear Regulatory Commission NRR = Office of Nuclear Reactor Regulation SPSB = Probablistic Safety Assessment Branch SRXB = Reactor Systems Branch PDIV-1 = Project Directorate IV-1 I l ATTACHMENT 1 l l l l l 1
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l \ SHUTDOWN CONDITION 1 - MODE: 4 STATE: Cold S/D FUEL STATUS: Fueled l RPVLEVEL: Any POOL GATES: N/A i I DECAY HEAT REMOVAL (SDC) Circle nooropriate color [ ] 1. Of the following three available for decay heat removal. ( ) RHR A ( ) RHR B areen - Three available ( ) ADHR Yellow- Two available j
-OR- or*"S*- "* *v*il*bl*
Red - Zero available [ ] 2. RWCU ifin Ops Hydro R;sgg ymsag yja gga!g[ag g g g yefg!g]g l Comment / Contingency: I l l l pP FUEL POOL COOLING (FPC) Green - Available FPC [ ] 1. Sufficient Fuel Pool Cooling Trains available for Trains are sufficient current heat load. Yellow- RHR in FPC assist l Red - nothing avail WM58thRegaisiesTWM,monax hteagis e<,wma~ ,- w m e;<eu a +mmw,m m e fps 44 Comment / Contingency: 37
SHUTDOWN CONDITION 1 (cont.) cir'eie soorooriate coior l l AC POWER CONTROL (AC) 1 [ ] 1. Of the following three offsite power sources: For offaite power sources I ( ) a. BaxterWilson and Esr xfarst ( ) b. Franklin ( ) c. Port Gibson Green - >= Two available i gg Yellow - one available [ ] 2. Of the f*;frg three ESF transformers: Red - Zero available ( ) a. ESF11/ST11 ( ) b. 'ESF21/ST21 ( ) c. 'ESF12 ror Div 1 a 2 D/G's:
-AND.
[ ]3. EmergencyDieselGenerators Green - Two available ( ) a. Div i Yellow - one available~ Red - Zero available ( ) b. Div ll ( i m.m m ww wsw m+ T s?tWressiistfsiitWifeedai$erwennammanswumm1sfidiDiv219eciDiv129E Comment / Contingency:
- lNVENTORY CONTROL (IC)
[ ] 1. Adequate ECCS inventory exists and of the following five systems: ( ) a. RHR LPCI A ( ) d. LPCS ( ) b. RHR LPCI B ( ) e. HPCS ( ) c. RHR LPCI C Green - >=Three available Yellow- Two available Orange- One available OR ; l' T15r? BeguisesF2 ssystensioperable7AND;f SP.Blevels less than adequate
; >12jt*f0RAfor$NPCS[onlybya,pmegy&j$, ECCS' inventory exists.
e9 cmmsm, syn ;e CSTyleve1%>19$, $$,sj i Red - Zero available Comment / Contingency: I 18 i i
SHUTDOWN CONDIT!ON 1 (cont.) Circie u s te e r CONTAINMENT CONTROL (CON) j [ ] 1. Of the following if.Det handling irradiated fuel, Not handling irr. fuel, i core alts orperforming OPDRVs: core alts or not performing OPDRVS: ( ) Secondary Containment operable and and SBGT A and SBGT B operable. Green - All three operable. [ ] 2. Of the following if handling irradiated fuel, core alts Yellow- < All operable. or performing OPDRVs: -------------------------- Handling irr. fuel, core ( ) a. Secondary CTMT Operable alts or performing OPDRVS: ( ) b. SBGT A operable ( ) c. SBGT B operable Yellow- See CTMT operable and two SBGT trains operable. Orange- Sec CTMT operable and one SBGT train T.sh mequiresfsecic1MTiand A&R ssGT-if ? i operabic. h=d14 ==*)irradiathd[fuAl forf performing F Red - See CTMT not OPDRV's. ' operable or two SBGT S trains not operable. Comment / Contingency: - REACTMTY CONTROL (RC) Green - All Inserted [ ] 1. All control rods fully inserted or one rod outinterlockis operable. Yellow- Not all inserted AND one rod out interlock operable AND TS 3.10 for single rod removal met. T . sg shu tdown Marginj anis tialways ; be : me t) : control:modsifullylinserted/during: fuel' Red - SDM not met or not loadin6 scod10.s* rolirodslaafibhisithdrawn? all inserted AND one rod under'T.sij3 W ^ " out interlock not operable OR TS 3.10 for single rod removal not met. Comment / Contingency: Performed By-Date/ Time- ! t i i l 1 19 l
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