ML20211G375

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Summary of 870122 Meeting W/Util Re Status & Schedule of Licensing Actions.List of Attendees Encl
ML20211G375
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/18/1987
From: Kintner L
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8702250359
Download: ML20211G375 (17)


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UNITED STATES 0

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%j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 18, 1987  !

Docket No. 50-416 LICENSEE: System Energy Resources, Inc.

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUBJECT:

SUM ARY OF JANUARY 22, 1987 MEETING REGARDING STATUS AND SCHEDULE OF LICENSING ACTIONS The purpose of the meeting was to discuss the status of licensing activities on Unit I and the plans and schedules for future activities. Enclosure 1 is a list of participants. Enclosure 2 is a copy of handouts prepared by the licensee for use in the meeting. This report was prepared by L. Kintner and J. Unda.

The licensee described the status of Unit 1. Unit I was placed on line on January 8,1987 and after about one week of power ascension tests, the plant has operated at about 100% power. The first refueling outage, which began September 6,1986, was extended 33 days primarily because of a damaged main stream turbine bearing, and also problems with the main generator excitation, a hydrogen seal ring and the main lube oil system. The licensee plans to operate Unit 1 at full power for several months. Cooling tower modifications were completed during the first refueling outage so that full power should be achievable under all seasonal weather conditions.

The licensee described present thinking about the second and third refueling outages (See Sheet 4 of Enclosure 2). The second fuel cycle is a 12-month cycle while the third fuel cycle will be 18 months. Because of the load demand on the Middle South Utilities system, Grand Gulf Unit 1 power may be reduced in the spring months. The earliest date for the start of the second refueling outage is October 1, 1988, but the reduced load demand may extend the starting date several months. The second outage is planned to last eight weeks and will include low pressure main steam turbine disc inspections, control room modifications in accord with NUREG 0737 Supplement 1, modifications of post accident monitoring instrumentation in accord with Regulatory Guide 1.97, modifications of ATWS components in accord with 10 CFR 50.62, and completion of the removal of core vibration monitoring instrument-ation. The third refueling outage is presently scheduled for February and March 1989.

The licensee described some changes in the SERI organization. Larry Dale, Director of Nuclear Licensina and Safety, who has been managing emergency preparedness activities, will remain with Mississippi Power & Light Company.

Bob Fron, assistant to the Manager of Plant Support, will manage emergency 4 planning activities. J. G. Cesare is the new Director of Licensing in the corporate office in Jackson. Sheet 5 of Enclosure 2 shows the organization and responsibilities of the Director of Licensing. Assistants will be 1

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e assigned to positions under Fred Titus, Director of Nuclear Plant Engineering (MPE) to assist in managing the engineering effort. The licensee has completed all programs for INPO accreditation ard will be evaluated by INPO -

this fall.

In response to licensee's question, staff said that reorganization plans at NRC although announced, are not yet implemented. The reorganization, when it occurs, is not expected to significantly impact planned licensing activities at Grand Gulf.

The following comments were made regarding specific items in Enclosure 2.

I.D. - Submittals regarding effect of ownership of mineral rights of land in the exclusion area will be made January 28, 1987 and will include the fact that mineral rights for 89% of land in exclusion area are now owned by the licensees due to a recent purchase and the report of a geologist regarding oil and gas exploration in the region of the plant. Efforts to purchase additional mineral rights are continuing.

A colored map showing ownership of mineral rights was provided to the NRC Project Manager. '

3 I.E. - The licensee has decided to use for internal planning an integrated living schedule which combines the use of an annual operating plan and a long-tem (5-year) plan. A submittal will be made February 13, 1987 regarding an integrated living schedule pursuant to Generic Letter 85-07. (SeealsoSheet6ofEnclosure2) 1 I.F. - Pending Technical Specification (TS) changes, together with staff 4

target dates for the Federal Register notice are shown in sheet 7 of Enclosure 2. (Target dates have been updated by the staff suusequent l' to the meeting). Regarding lessons learned in the first refueling the licensee said that amendments of Technical Specification pages J that include more than one design change are sometimes difficult to implement in the plant because the systems may be made operable at different times; therefore, the licensee will coordinate planned t changes with plant operations personnel. The licensee plans to I submit an application to amend the fire protection ifcense condition and Technical Specification in accord with Generic Letter 86-10 on March 20, 1987. Fuel reload for the second refueling outage will be Exxon fuel and no Technical Specification changes are planned.

Target dates for completion of pending licensing actions by the staff are shown under Item II.A of Enclosure 2. Additional submittal dates are shown under Item II. B in Enclosure 2.

I.G. - The licensee requested that consideration be given to deleting license conditions that were completed (See Sheets 8 and 9 of Enclosure 2). In particular, four license conditions appear to the licensee to be ambiguous if left standing: 2.C.(20),(21),(39)and (40). The NRC Project Manager said that he would consider their

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request after consultation with other staff. Subsequent to the meeting the, Project Manager advised the licensee that license conditions may not be deleted until the staff has verified that they are completed by means of an inspeciton report or letter from the Office of Nuclear Rector Regulation. After appropriate verification, a request to delete the license conditions may be made together with other administrative changes. License conditions, such as 2.C.(38) which specify operating conditions may be amended by proposing Technical Specifications to supersede them.

I.I. - Core hydraulic stability tests run on January 31, 1987, confirmed the stable operation of Unit 1 in the maximum extended operating domain at recirculation flows around 40%.

I.J. - Licensee advised that its mailing address should'be Post Office Box 23054, not the old P. O. Box 1640 that some NRC organizational units are still using.

I.K. - The licensee is planning to improve 50.59 evaluations and summaries provided to NRC by instituting a training program for evaluators.

I.L. - Licensee is planning licensing program improvements in submitting LERs on time, by allowing more time for internal review and approval.

The staff is considering the generic question of which systems and components should be reported when they are inadvertently activated -

i.e., what is the definition of an "ESF actuation" that is required to be reported by 10 CFR 50.72 and 50.73. The licensee is developing a list of ESF components for reporting purposes.

I.M. - Near-term meetings are listed on Sheet 11 of Enclosure 2, with

changes as noted in the present meeting. Regarding Item 4, it was noted that Grand Gulf is the lead plant for the IDCORE program.

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Lester L. Kintner, Project Manager

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BWR Project Directorate No. 4 Division of BWR Licensing i

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l request after consultation with other staff. Subsequent to the meeting the, Project Manager advised the licensee that license conditions may not be deleted until the staff has verified that they l are completed by means of an inspeciton report or letter from the l Office of Nuclear Rector Regulation. After appropriate verification, a request to delete the license conditions may be made together with other administrative changes. License conditions, such as 2.C.(38) which specify operating conditions may be amended by proposing Technical Specifications to supersede them. '

I.I. - Core hydraulic stability tests run on January 31, 1987, confirmed the stable operation of Unit 1 in the maximum extended operating i domain at recirculation flows around 40%. l I.J. - Licensee advised that its mailing address should be Post Office Box .

23054, not the old P. O. Box 1640 that some NRC organizational units l are still using.

I.K. - The licensee is planning to improve 50.59 evaluations and summaries provided to NRC by instituting a training program for evaluators.

I.L. - Licensee is planning licensing program improvements in submitting LERs on time, by allowing more time for internal review and approval. l The staff is considering the generic question of which systems and i components should be reported when they are inadvertently activated -

i.e., what is the definition of an "ESF actuation" that is required to be reported by 10 CFR 50.72 and 50.73. The licensee is developing a list of ESF components for reporting purposes.

I.M. - Near-term meetinas are listed on Sheet 11 of Enclosure 2, with changes as noted in the present meeting. Regarding Item 4, it was noted that Grand Gulf is the lead plant for the IDCORE program.

l OrisaalSm a in Lester L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing DISTRIBUTION

Docket File Jilnda NRC PDR M0'Brien LPDR Young, OGC PD#4 Rdg. EJordan WButler BGrimes LKintner/BSiegel ACRS(10)

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Mr. Oliver D. Kingsley, Jr.

System Energy Resources, Inc. Grand Gulf Nuclear Station (GGNS) cc:

Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support System Energy Resources. Inc.

System Energy Resources. Inc. Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Nicholas S. Reynolds, Esquire Bishop. Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 Washington, D. C. 20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services Inc.

P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensing and Safety Bureau of Pollution Control System Energy Pesources, Inc. Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 l Mr. R. W. Jackson, Project Engineer ta e ea dficer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205

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Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Comission Port Gibson, Mississippi 39150 Route 2 Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W., Suite 2900

. Atlanta, Georgia 30323 Mr. James E. Cross GGNS Site Director System Energy Resources, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150

Enclosure 1 NRC - SERI Licensing Actions Meeting January 22, 1987 Name Affiliation

0. D. Kingsley, Jr. SERI - Vice President, Nuclear Operations L. L. Kintner NRC/NRR/BWD-4 Juan Unda NRC/NRR/BWD-4 W. F. Smith NRC Resident Inspector T. H. Cloninger SERI - Vice President, Engineering & Support F. W. Titus SERI - Director NPE J. G. Cesare SERI - Director, NL&S M. L. Crawford SERI - Supervisor, NL R. L. Besser SERI - Technical Specification Coordinator S. H. Hobbs SERI - Manager Nuclear Safety & Compliance J. L. Robertson SERI - Plant Licensing Support J. P. Czaika SMEPA - Resident Manager R. C. Butcher NRC/ SRI H. C. Dance NRC Region II, Chief, Project Section IB l

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Enclosure 2 NRC-SERI LICENSING ACTION STATUS MEETING JANUARY 22, 1987 AGENDA I. GENERAL & SPECIAL TOPICS OF INTEREST A. Plant Status / Schedule (RF02 forecast) ODK/JGC B. NRC Reorganization - Potential Impact on GGNS LLK Licensing C. NL&S Department Realignment JGC D. Mineral Rights SHH E. Integrated Living Schedule JGC F. Technical Specifications

1. Status of Items Submitted LLK
2. Planned Submittals JGC o RF01 Lessons Learned o GL-86/10 (Fire Protection) o RF02(DCPs)

G. Deletion of Completed Operating License Conditions LLK/JGC H. UCNR 50.59 Summary Report: Status JGC I. Core Stability Test JGC J. Mail Handling (SERI Mailing Address) JGC K. SERI 50.S9 Program Review & Upgrade JGC L. SALP - Licensing Functional Area Improvement Areas JGC/NRC M. Unit 1/ Unit 2PlantTour(1/23/87,0830-1130) MLC N. NRC-SERI Meeting Forecast . JGC J16M15C87012002 - 1

II. UPCOMING KEY LICENSING ACTIONS A. NRC Action

1. SRV Fatigue Evaluation dy/J. 4/I7 I
2. Fire Brigade Drill Schedule 'C f [17/[7
3. Loose Parts Monitoring System #3//f/'[7
4. ISI/IST Program pg/3 c /T7 T
5. Various HCOG submittals -

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6. Control Blade Surveillance, IEB 79-26 p 3 /3 4/f 7 T-B. MP&L Action
1. Mineral Rights (Covered Above) 1/g 2_T 2.

.LER 86-045-01 ( T'r e e F411 onLaThasy M. @)k 1/26

3. EQ - A0V, MOV Deficiencies 1/28
4. Confirmation Measurements Program -(Tr*.bQ 1/28 Corrective Action Report
5. Region II PRA Inspection - 1/29 NRC/SERI Pre-meeting
6. SSW System Deficiencies (Meeting with NRC) 2/4
7. LER 87-001 Invalid offgas pretreatment samples taken 2/9
8. Containment Purge Monitoring Program 2/11 (Meeting with NRC)
9. Revised Requalification 2/13 Operator C D u. f+Training

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10. Integrated Living Schedule, ToIlowup Response 2/13 to Generic Letter 85-07 l 11. EQ - Raychem Splices 2/15
12. SERI comments on SALP 2/16
13. UCNR 50.59 Summary Report 2/16
14. PCOL on Neutron Monitoring -Deferral 2/27 from RF02 to RF03
15. Hydrogen Control Program - Quarterly Report 2/28 (4th Quarter)

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14. Generic Letter 86-10, Proposed License 3/20 Amendment to Delete Fire Protection Features From Technical Specifications i
15. RF01 S/U Sumary Test Report 4/6
16. OLC Deletion (covered above) To Be Determined
17. SSW System Design Review - Scope, Schedule h Da ntwh e L M uf% Fe44, s 9 P7

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CYCLE 2&RF02SCHEDULElCURRENTPLANS) o Cycle and Outage Planning Considerations Cycle energy design Expected plant performance Reload licensing analysis " window" Typically restrict outage from holidays and high system demand period Outage length controlled by refueling floor activities o Schedule (Current estimates)

- Nominal cycle length: 12 months i - Cycle 2 Shutdown: 10/12/87 RF02 length: 8 weeks 4

- Cycle 3 Startup: 12/7/87 (Cycle 3 length, nominal 18 months)

J19 MISC 87012103 - 1

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DIRECTOR

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i NANAGER NANAGER LICENSING SUPPORT LICENSING J

i SUPEWISOR LEAD ENGINEER OFFICE SERVICES SUPERVISOR SUPERVISOR RESULAT SUPPORT ASSISTANT LICENSING LICENSING PROJECTS g l

1. LER 1. Cole 8IT TRACKING: 1. ALL STO OFFICE
1. DVERALL LIC STRATEGY. 1. PROJECT NGNT
2. NOV/N00 LCTS. ATS. SATS. SERVICES 00R, C00RI, SCED. 2. UFSAR/SO.59
3. EQUIP OUAL 3. PART 21 IETRACK. OVERALL CONTROL (INCL. EP)
2. NRR RAI 2. PROCEDURES. CONTROL 2. SRC/ SUPPORT
3. TS C00RO/ PROS NSNT 4. NURES 0737 SUPP 1 4. IES (TRACK)
5. IE ADMIN TRACKING 3. BIEEET/ ACCOUNTING
4. ONNERS GIF TRACKINS 4. TRNG RECORDS

. 5. GENERIC LTRS 6. SPECIFIED ROUTIE REPORTS 5. SPEC TRNS PROJECTS

6. TRANS/ACC SAFETY ANALYSES
6. 60AL/08J NGNT

. 7. ROUTINE EPORTS 7. C00@ UTER SUPPORT

! 8. INTERPRET. WIC E SS. 8. DEPT EFFECTIVENESS.

GGNS LIC BASIS COMPLIANCE APPRAISAL

9. MONITOR ItOUSTRY ISSUES
9. DEPT LD61STIC SUPPORT
10. OP LIC/TRNG PROG NATTERS
11. SRC SECRETARY
12. GENERIC ISSUES i 13. RELOAD LICENSINS l

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- Generic Letter 85-07.7requested response to NRC proposal to implement i ILS concept t

- MP&Lrespondedvia7etterdated7/1/85(AECM85/0203) ,

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Position at that time was as follows: . \

o ILS considerations being used to develop RF01 schedule -

o ILS evaluation for usage in future outages to be submitted ,

post-RF01 i s o MP&L's' impression was ILS concept not proven as effective ~ " ,

method to prioritize/ defer commitments , y

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o MP&L developing Annual Operating Plan (A0P') and Long Term Plan (LTP) to address planning, both short and 1.ong range

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o Status: j f Evaluation of use of ILS for future outages completed ILS which combines elements of AOP and LTP to be used as .an internal ~

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- InternalproceduredraftedaddressingILSutilization(procedere C currently under review)

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- Currently evaluating use of ILS as basis for schedule discussions <

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- Letter drafted to NRC as follow-up tri commitment made in AECM45/.0203 i\

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' sff TECH SPEC CHANGES SUBMITTED TO NRC Awaiting Approval in 1987

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[p M TSC ID Submittal Fed. Reg.

c - (PCOL #) Subject (Re-submitted) Notice r

PS 86/08 RPCS Bypass Switch 10-07-86 12-30-86 (PCOL86/23) (12-05-86)

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PS 86/06 Iodine Sampling 10-07-86 12-30-86 (PCOL86/23) Analysis '

PS 85/07 'DW Airlock Sea 1 Test 05-28-86 2 F- l' 7 T g (PCOL86/11)

PS 85/09 '

DW Airlock Leak Test 11-11-86 2-Ai-T7 F

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NLS 86/09 Delete 2 Min SRV 10-17-87 2-19-P7 T fe? 4]

(PCOL8C/24)

\IPF'86/14 CRD Room Smoke. 10-17-86 y (PCOL86/24) Detector Addition

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NPE 85/17 RCIC Thermal Overload 10-17-86 'A-24-P7 F (PCO'. 86/24) Protection Ild r NPE 86/12 RHR Flashline to LRW Table Clarification 10-17-86 2. - 2.- 6-f 7 T (PCOL86/24)

NLS 85/17 D-G Tech Spec Changes 05-22-86 g- tr p 7 r (PCOL86/10) 12-09-86 01-30-87 NLS 86/16 RPV Press-Tergp Curve 11-11-86 q,gy,pp 7-(PCOL86/26) Correction (01-20-87)

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J16 MISC 87012103 - I hj

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Completed GGNS Operating License Conditions OL Section Subject 2.C.(4) Independent Verification of Staff Performance and Other Plant Activities (a) o SRC review of operational readiness (b) o PSRC review of preoperational 3 testing 2.C.(5) Deferred Preoperational Deficiencies 2.C.(6) Soil Structure Interaction 2.C.(7) Seismic Monitoring Instrumentation 2.C.(8) Masonry Walls (IEB 80-11) 2.C.(9) Dynamic Testing -- Vibration Assessment Program 2.C.(10)' Dynamic Qualifications (b) o In situ test of HFCS servic water pump s

(c) o Qualify fuel handling and auxiliary platform, in-vessel ,

' rack, and storage container for defective fuel 2.C.(11) Environmental Qualification of Electrical Equipment 2.C.(13)(a) Core Stability Analysis -- Submit new core stability analysis prior to RF01 restart t .

Scram Discharge Volume 2.C.(15) 2.C.(17)

Containment Pressure Boundary -- ./

Feedwater Check Valve Disc 2.C.(18) Pressure Interlocks on Valves Interfacing at Low and High Pressure i

J19 MISC 87012101 - 1 fy

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2.C.(19) IE Information Notice 79-22, Qualification of Control System i

2.C.(20) Standby Service Water System 2.C.(21) Spent Fuel Pool Ventilation System 2.C.(22) Remote Shutdown Panel 2.C.(24) Interplant Communication Systems 2.C.(25)(a) Reliability of Diesel Generators

-- EMD turbocharger gear drive assembly 2.C.(28)~ Advisor to the Vice President 2.C.(29) Operating Shift Advisor 2.C.(31)(a)through(d) Initial Test Program 2.C.(33) NUREG-0737 Conditions

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, (b) Training During Low-Power Testing (I.G.1)

(c) Post Accident Sampling (e) Instrumentation for Detection of Inadequate Core Cooling .

(f) Modification of ADS Logic (g) Qualification of ADS Accumulators 2.C.(34) SRV Test Program 2.C.(35) Post-LOCA Vacuum Breaker Position Indicators 2.C.(37)(a) through (c) Evaluation of Licensee's Technical

. Specification Problem Sheets (Section 16.3, SSERf6) 2.C.(39) Temporary Secondary Containment Boundary Change 2.C.(40)(a) and (b) Temporary Ultimate Heat Sink Change J19 MISC 87012101 - 2

SALP Identified Problems or Areas Requiring Improvement (Licensing Functional Area)

1. LERs reported late -
2. Inadequate preparation of emergenc discretionary enforcement request)y ; inadequate technical specification involvement change of plant staff (or
3. Licensing submittals not timely, thorough, or technically sound (HDSFR, SDV vent & drain valves)
4. Approach selected on occasion was to meet minimum requirements
5. Lack of management attention, FSAR update program
6. Followup action not timely (containment and drywell penetration listing)

J19 MISC 87012104 - 1 /$

NRC-SERI MEETING FORECAST DATE LOCATION SUBJECT

1. 1/22 GGNS SALP
2. 1/22 GGNS Licensing Action Status Meeting
3. 1/23 GGNS Unit 1/ Unit 2 Plant Tour
4. 1/29 GGNS PRA Inspection - Premeeting
5. 2/4 Atlanta SSW System Concerns
6. 2/11 Bethesda Containment Purge
7. 2/18 Atlanta NRC Region II Workshop, Incident Investigation & Performance Monitoring

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