ML20154S287

Summary of 860207 Meeting W/Util Re Status & Scheduling of Licensing Actions.Attendee List & Proposed Agenda Prepared by Licensee Encl

ML20154S287
Person / Time
Site:	Grand Gulf
Issue date:	03/19/1986
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8604010026
Download: ML20154S287 (8)

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.), *# WR 191986 Docket No. 50-416 LICENSEE: Mississippi Power & Light Company (MP&L)

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUMMARY

OF FEBRUARY 7, 1986 MEETING REGARDING LICENSING ACTIONS The purpose of the meeting was to discuss the status and scheduling of licensing actions. Enclosure 1 is a list of attendees. Enclosure 2 is a proposed agenda prepared by the licensee.

The licensee described a review program initiated to find unreviewed changes in the Updated Final Safety Analysis Report (UFSAR) compared to the Final Safety Analysis Report (FSAP) as supplemented by operating license review responses to questions and letters of committment. The review was initiated in response to inquiries by the NRC staff regarding three differences between the UFSAR and the FSAR:

(1) the UFSAR does not retain the statement that the shift superintendent will be responsible for protective tagging.

(2) the UFSAR changed the minimum sub ergence of the HPCA suction pipe entrance from 2.5 feet to 0.75 feet.

(3) the USFAR included additional ex.eptions to AWS D1.1-72, a code for welding in building construction.

The licensee stated that these differences were due to differences between the FSAR and the plant and procedures which existed prior to licensing and not due to changes made in equipment or procedures after licensing. Therefore they considered it appropriate to make changes for the USFAR without making a 10 CFR 50.59 analysis. The staff commented that all changes to the facility and procedures as described in the FSAR at the time of licensing should be reviewed in accordance with 10 CFR 50.59 and the analyses documented. The staff also comented that Generic Letter 81-06, (which includes 10 CFR 50.71e and associated supplemental information) should be used as guidance for making UFSAR changes. Generic Letter 81-06 states that the level of detail to be maintained in the UFSAR should be at least the same as originally provided in the FSAR. The 'iicensee said its review program would include screening of changes made in preparing the UFSAR to see that 10 CFR 50.59 analyses had been made. The review program will also determine if the level of detail in responses to staff questions is retained in the UFSAR. The licensee plans to complete the review program, including any necessary 10 CFR 50.59 evaluations by May 15, 198C and will make appropriate changes in the UFSAR in December 1986.

The licensee stated that the first refueling outage had been rescheduled from June to September 1, 1986 in order to have the plant available throughout the hottest part of sumer. Currently, an outage of 9-10 weeks is planned. Licensee will prepare a presentation for NRR staff in Bethesda within a few months to describe the refueling outage.

8604010026 860319 PDR ADOCK 05000416 P PDR

l Regarding the schedule for licensing actions, the licensee said it would submit the response to staff questions on the high density spent fuel rasks in March.

The licensee stated that it is considering moving spent fuel into the upper containment pool at the same time a larger standby service water pump is installed in the cooling tower basin, and if so a license amendment for that work may be required.

The staff provided estimated dates for the items listed under Item F. of Enclosure 2 as indicated in script. As of the date of this meeting sumary preparation, favorable safety evaluations have been completed on all items, except the IST program, peak recording accelersmeters, ADS License Amendment, MSIV leakage control system and main feedwater flued head limiting permissible metal temp-erature. The ADS License Amendment request is expected to be withdrawn. The other refueling outage (RF01) deferral items safety evaluations are currently scheduled for completion by March 31, 1986. Letters transmitting the safety evaluations will follow shortly.

The licensee's submittals planned through May 5, 1986, are indicated on Sheet 2 of Enclosure 2. As of the date of preparation of this summary, responses to questions on the high density spent fuel racks, the Startup Final Test Report and Vibration Monitoring Report have been submitted. Items 4 and 5 are submit-tals to Region II for review. The remainder of the items are expected to be submitted in March 1986. Regarding other projections of submittals, the licensee said it is now planning to install the following equipment during the first re-fueling shutdown, rather than request a deferral; strong motion accelerometer, radiation monitors required by Regulatory Guide 1.7, and the remote shutdown panel HVAC upgrade. Also technical specification changes will not be required for the SPDS nor for the upgrade of spent fuel pool pump room coolars. The licensee plans to submit a request to extend the operating domain for Cycle I in March and for Cycle II in July, 1986. Because of the later fuel load date, the Exxon reload will be submitted July 14, 1986. Core stability analyses and justification of single recirculation loop operation will be submitted in March 1986.

km L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing

Enclosures:

As stated cc: See next page l

l l

r Regarding the schedule for licensing actions, the licensee said it would submit the response to staff questions on the high density spent fuel racks in March.

The licensee stated that it is considering moving spent fuel into the upper containment pool at the same time a larger standby service water pump is installed in the cooling tower basin, and if so a license amendment for that work may be required.

The staff provided estimated dates for the items listed under Item F. of Enclosure 2 as indicated in script. As of the date of this meeting summary preparation, favorable safety evaluations have been completed on all items, except the IST program, peak recording accelerometers, ADS License Amendment, MSIV leakage control system and main feedwater flued head limiting permissible metal temp-erature. The ADS License Amendment request is expected to be withdrawn. The other refueling outage (RF01) deferral items safety evaluations are currently scheduled for completion by March 31, 1986. Letters transmitting the safety evaluations will follow shortly.

The licensee's submittals planned through May 5, 1986, are indicated on Sheet 2 of Enclosure 2. As of the date of preparation of this sumary, responses to quastions on the high density spend fuel racks, the Startup Final Test Report and Vibration Mcnitoring Report have been submitted. Items 4 and 5 are submit-tals to Region II for review. The remainder of the items are expected to be submitted in March 1986. Regarding other projections of submittals, the licensee said it is now planning to install the following equipment during the first re-fueling shutdown, rather than request a deferral; strong motion accelerometer, radiation monitors required by Regulatory Guide 1.7, and the remote shutdown panel HVAC upgrade. Also technical specification changes will not be required for the SPDS nor for the upgrade of spent fuel pool pump room coolers. The licensee plans to submit a request to extend the operating domain for Cycle I in March and for Cycle II in July, 1986. Because of the later fuel load date, the Exxon reload will be submitted July 14, 1986. Core stability analyses and justification of single recirculation loop operation will be submitted in March 1986.

L. L. Kintner, Project Manager 3WR Project Directorate No. 4 Division of BWR Licensing

Enclosures:

As stated DISTRIBUTION cc: See next page Docket File Young, OELD NRC PDR EJordan Local PDR BGrimes PD#4 Reading ACRS (10)

WButler NRC Participants

/s LKintner

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PD#4 PH PD#4/D kv MDuncan  :

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03 /86 03/@/86

Regarding the schedule for licensing actions, the licensee said it would submit the response to staff questions on the high density spent fuel racks in March.

The licensee stated that it is considering moving spent fuel into the upper containment pool at the same time a larger standby service water pump is installed in the cooling tower basin, and if so a license amendment for that work may be required.

The staff provided estimated dates for the items listed under Item F. of Enclosure 2 as indicated in script. As of the dite of this meeting sumary preparation, favorable safety evaluations have been completed on all items, except the IST program, peak recording accelerometers, ADS License Amendment, MSIV leakage control system and main feedwater flued head limiting permissible metal temp-erature. The ADS License Amendment request is expected to be withdrawn. The other refteling outage (RF01) deferral items safety evaluations are currently scheduled for completion by March 31, 1986. Letters transmitting the safety evaluations will follow shortly.

Tne licensee's submittals planned through May 5, 1986, are indicated on Sheet 2 of Enclosure 2. As of the date of preparation of this sumary, responses to questions on the high density spend fuel racks, the Startup Final Test Report and Vibratica Monitoring Report have been su hitted. Items 4 and 5 are submit-tals to Region II for review. The remainder of the items are expected to be submitted in March 1986. Regarding other projections of submittals, the licensee said it is now planning to install the following equipment during the first re-fueling shutdown, rather than request a deferral; strong motion accelerometer, radiation monitors required by Regulatory Guide 1.7, and the remote shutdown panel HVAC upgrade. Also technical specification changes will not be required for the SPDS nor for the upgrade of spent fuel pool pump room coolers. The licensee plans to submit a request to extend the operating domain for Cycle I in March and for Cycle II in July, 1986. Because of the later fuel load date, the Exxon reload will be submitted July 14, 1986. Core stability analyses and justification of single recirculation loop operation will be submitted in March 1986.

L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing

Enclosures:

As stated DISTRIBUTION cc: See next page . Docket F1le- Young, OELD NRC PDR EJordan Local PDR BGrimes PD#4 Reading ACRS (10)

WButler NRC Participants LKintner

/j q MDuncan PD# P PD#4/D LKintner:lb WButler W 03 /86 03/@/86

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.j Hr. Oliver D. Kingsley, Jr. ,

Mississippi Power & Light Company Grand Gulf huclear Staiton cc

The Honorable William J. Guste, Jr.

Robert B. McGehee, Esquire hise, CLrter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge,iauisiana 70804 hicholcs S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street,ii.W.

Washington, D. C. 20036 Mr. Ralph T. Lally Manager of Quality Assurunce Office of the Governor Middle Scuth Services, Inc. State of Mississippi P.O. Box 61000 Jackson, liississippi 39201 hew Oricans, Louisiana 70161 Attorney General lir. Larry F. Dale, Director Gartin Building i;uclear Licensing and Safety Jackson Mississippi 39205 Mississippi Fcwer & Light Company Mr. .'ack McMillan, Director P.O. Box 23054 ~

Jackson,!!ississippi 39205 Solid Waste flississippi State Board of Health Mr. R. W. Jackson, Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Marylund 28077-1454 Alton B. Cobb, i;.D. >

State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Ccmission Jackson, Mississippi 39205

Route 2, Box 399 Fort Gibson, Mississippi 39150 President Claiborne County Board cf Supervisors Regional Administrator, Region 11 .

Port Gibson, Mississippi 39150 a

U.S. Nuclear Regulatory Comission, D 101 Marietta Street, N.W., Suite 2900 Mr. Ted H. Cloninger Atlanta, Georgia 30323 Vice President, Nuclear Engineering and Support Mr. J. E. Cross  !!ississippi Power & Light Corrpary L Grand Gulf Nuclear Station Site Director Post Office Box 23054 j Mississippi Power & Light Company Jackson, Mississippi 39205 i P.O. Box 756 l

Port Gibson, Mississippi 39150 Mr. C. R. Hutchinsco GGNS Cer,eral hanager ,

Mississippi Pcwer & Litjht Company i

Post Office Box 756 Port Gibson, Mississippi 39150

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^* Enclosure 1 Attendees Meeting with MP&L Feb. 7, 1986 NRC MP&L i L. L. Kintner G. W. Smith H. Dance W. K. Hughey

J. Caldwell S. H. Hobbs R. Butcher M. L. Crawford V. W. Panciera J. G. Cesare L. F. Dave F. W. Titus f b a.

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. Encisoure 2 NRC - MP&L PROJECT STATUS MEETING February 7, 1986 Grand Gulf A. Updated Final Safety Analysis Report (UFSAR) J. G. Cesare B. GGNS Plant Status L. F. Dale C. Refueling Outages / Planning & Schedule L. F. Dale Proposed Meeting W/NRC Staff D. Significant Hazards Evaluations S. H. Hobbs i

E. Upcoming Heeting W/ Region II (2/20/86) J. G. Cesare Licensing / Quality Assurance F. NRC Action NRC

1. IST Program & Relief Requests g

2. FSAR 13.2 y /g L,d .'/" b

3. Onsite Communications S/U Test Results dle[O G/h

4. RPM / CRC Supt TS Change g & / L./ / M  ;

5. RF01 Deferral Items

• Peak Recording Accelerometers (PRA) p 2 N [b l

• ADS License Amendment p yj (([f

• Turbine Discs Ot/u/M6

• MSIV Leakage Control System Commitment y }/ g y /[f l

• Hydrogen Control System g j3/gj

• MS/FW Flued Head LSMT 3 g LJ~/ M I

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MP&L ACTION 2/5 - 5/5 J. G. Cesare

1. High Density Spent Fuel Racks 2/14/86 e Thermal-Hydraulics Questions (ASB)

2. S/U Testing

• Final Test Report 3/15/86

• Vibration Monitoring 2/23/86

3. Reload Licensing

• Core Stability / SLO 2/21/86

• MEOD Cycle 1 3/14/86

4. Independent Verifier Qualifications 2/14/86 1 5. Shift Technical Advisor - Team Concept 2/21/86 G. DISCUSSION OF NRC LICENSING ACTION PROJECTION LIST i

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