ML20202J431

Summary of 860321 Meeting W/Util in Bethesda,Md Re Status of Licensing Actions.List of Attendees & Licensee Prepared Handout Encl

ML20202J431
Person / Time
Site:	Grand Gulf
Issue date:	04/07/1986
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8604160039
Download: ML20202J431 (22)

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d ,','. . **,9 APR 7 1986 Docket No. 50-416 LICENSEE: Mississippi Power & Light Company (MP&L)

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUMMARY

OF MARCH 21, 1986 MEETING REGARDING LICENSING ACTIONS The purpose of the meeting was to discuss the status of licensing actions.

Enclosure 1 is a list of attendees. Mr. H. Dance, Chief, Projects Section, Region II, Mr. R. Butcher, Senior Resident Inspector, and Mr. J. Caldwell, Resident Inspector participated in a portiun of the meeting via telephone.

Enclosure 2 is a handout prepared by the licensee.

The licensee described the plant status. The plant was shut down to repair leaking relief valves in the ADS control air system. When the plant is restartec, the ADS control air system will be operated at a lower pressure to give a greater margin between the relief valve setpoint and operating pressure to reduce the potential for leakage.

The licensee is currently planning an 8 to 9 week refueling outage to begin September 1, 1986. A meeting is scheduled for April 23, 1986, with NRR in Bethesda, Maryland to describe the refueling outage and associated licensing activities.

The following comments were made regarding the items on the agenda, Page 2 of Enclosure 2.

Item I.C Of the 9 actions listed under the first refueling outage (RF01) deferrals, six have been submitted for review by the staff. Concerning the remaining 3 items: a deferral will not be requested for the upgrade of the heating ventilation and air conditioning system for the remote shutdown panel l run; a deferral may not be needed for the implementation of Regulatory Guide l 1.97; and, a tear down inspection for the TDI diesel generator for Division II is planned for RF01. The licensee has submitted its diesel generator inspection plan to the TDI Owners Group for review. After an acceptable plan is worked out with the Owners Group, the licensee will submit it to the NRC. The Owners Group has scheduled to complete its review by April 30, 1986 and the licensee plans to submit it to the NRC by May 30, 1986. Concerning the 6 items submitted for review, the request for deferral of the ADS accumulator pressure instrument installation was withdrawn March 17, 1986. The other 5 submittals are under review by the staff. The schedule dates for completion of staff's review of these items are indicated in parentheses on Page 2 of Enclosure 2. The licensee will provide additional information regarding isolation valves for the main steam isolation valve leakage control system and heat tracing of the HPCS pump suction pipe from the condensate storage tank. The schedule dates shown depend on receipt of this information prior to April 30, 1986.

8604160039 860407 PDR ADOCK 05000416 P PDR

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Item I.D There are three submittals requesting Technical Specification-t.nanges. The January 29, 1986 submittal has not been noticed because sub-stantial changes are needed to proposed technical specifications for the vacuum breaker position. indication instruments and for the scram discharge volume drain and vent valves. Provided acceptable information is received by April 7, 1986, the license amendment can be noticed and issued by May 30, 1986. The February 17, 1986 submittal regarding the standby gas treatment systeia heaters is scheduled to be completed April 7,1986. The February 28, 1986 submittal regarding a control switch on the remote shutdown panel and an additional sprinkler system is scheduled to be completed May 30, 1986.

Item I.E The staff said that the target date for issuance of the high density spent fuel racks license amendment is June 30, 1986. This uate depends on receipt of satisfactory responses to staff questions on the thermal and hydraulic aspects of the spent fuel cooling by April 30, 1986. Staff indicated that the occupational dose assessment provided by licensee's March 14, 1986 letter appeared to be satisfactory. In response to licensee's question, staff '

said it did not see any problem with placing spent fuel in the upper contain-ment pool while working on one of the standby service water loops. However,  !

a technical specification change is needed to pemit opening cf valves to j the spent fuel pool cooler. '

Item I.G The licensee described its review of change notices generated during l the preparation of the Updated Final Safety Analysis Report. Out of 350 change notices screened, 16 were identified as having potentially non-con-servative changes. Analyses of change notices will be made in accord with ,

10 CFR 50.59 by a team composed of licensee personnel from the plant, Nuclear Plant Engineering, and licensing. Completion of the review is scheduled for May 1, 1986.

The staff requested the licensee to consider whether the functional test of l Diesel Generator 13 (letter dated Feb. 18,1986) which was intentionally terminated without loading because of a generator problem should be counted as a valid test in the determination of test frequency per Technical Speci-fications. Licensee said it would consider staff's comments and advise us of its finding.

The scheduled dates for staff completion of items listed on Page 3 of are indicated in script in parentheses following the items. The scheduled dates for licensee submittals in the next 90 days are listed on Page 4. Pages 5-17 are the licensee's listing of MP&L sbbmittals made since the last meeting and forecasts of submittals within the near future.

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

Enclosures:

As stated DISTRIBUTION [bodit h M el cc: See pqxt page NRC PDR Local PDR ~ 'PD#4 Reading PD#4/PM g PD#4/D WButler EJordan LKintner M0'Brien Young,0 ELD BGrimes LKintner:lb WButler A ACRS (10) NRC Participants 04/o//86 04/ /86

Item I.D There are three submittals requesting Technical Specification changes. The January 29, 1986 submittal has not been noticed because sub-stantial changes are needed to proposed technical specifications for the vacuum breaker position indication instruments and for the scram discharge volume drain and vent valves. Provided acceptable information is received by April 7, 1986, the license amendment can be noticed and issued by May 30, 1986. The February 17, 1986 submittal regarding the standby gas treatment system heaters is scheduled to be completed April 7, 1986. The February 28, 1986 submittal regarding a control switch on the remote chutdown panel and an additional sprinkler system is scheduled to be completed May 30, 1986.

Item I.E The staff said that the target date for issuance of the high density spent fuel racks license amendment is June 30, 1986. This date depends on receipt of satisfactory responses to staff questions on the thenal and hydraulic aspects of the spent fuel cooling by April 30, 1986. Staff indicated that the occupational dose assessment provided by licensee's March 14, 1986 letter appeared to be satisfactory. In response to licensee's question, staff said it did not see any problem with placing spent fuel in the upper contain-ment pool while working on one of the standby service water loops. However, a technical specification change is needed to permit opening of valves to the spent fuel pool cooler.

Item I.G The licensee described its review of change notices generated during the preparation of the Updated Final Safety Analysis Report. Out of 350 change notices screened, 16 were identified as having potentially non-con-servative changes. Analyses of change notices.will be made in accord with 10 CFR 50.59 by a team composed of licensee personnel from the plant, Nuclear Plant Engineering, and licersing. Completion of the review is scheduled for May 1, 1986.

The staff requested the licensee to consider whether the functional test of Diesel Generator 13 (letter dated Feb. 18,1986) which was intentionally i terminated without loading because of a generator problem should be counted as a valid test in the determination of test frequency per Technical Speci-

, fications. Licensee said it would consider staff's comments and advise us of its finding.

The scheduled dates for staff completion of items listed on Page 3 of

. Enclosure 2 are indicated in script in parentheses following the items. The scheduled dates for licensee submittals in the next 90 days are listed on Page 4. Pages 5-17 are the licensee's listing of MP&L submittals made since the last meeting and forecasts of submittals within the near future.

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

Enclosures:

As stated cc: See next page

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Mr. Oliver D. Kingsley, Jr.

Mississippi Power & Light Company Grand Gulf Nuclear Staiton CC*

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 Baton Rouge, Louisiana 70804 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 Services, Inc.

P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. Larry F. Dale, Director Resources Nuclear Licensing and Safety Bureau of Pollution Control Mississippi Power & Light Company Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 Alton B. Cobb, M.D.

Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claibor.se County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150' Route 2, Box 399 i Port Gibson, Mississippi 39150 Mr. Ted H. Cloninger Vice President, Nuclear Engineering Regional Administrator, Region II and Support U.S. Nuclear Regulatory Commission, Mississippi Power & Light Company 101 Marietta Street, N.W., Suite 2900 Post Office Box 23054 Atlanta, Georgia 30323 Jack:on, Mississippi 39205 Mr. J. E. Cross Grand Gulf Nuclear Station Site Director Mississippi Power & Light Company P.O. Box 756 Port Gibson, Mississippi 39150 Mr. C. R. Hutchinson GGNS General Manager Mississippi Power & Light Company Post Office Box 756 Port Gibson, Mississippi 39150

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Enclosure 1

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Attendees MP&L - NRC Meeting 3/21/86 Name Affiliation )

L. L. Kintner BWD4/ DBL /NRR/NRC J. G. Cesare, Jr. MP&L, Manager of Nuclear Licensing S. H. Hobbs MP&L, Manager of Nuclear Safety &

Compliance W. K. Hughey MP&L Technical Specification Coordination M. L. Crawford MP&L Supr of Licensing W. Butler BWD4/NRC D. Katze US NRC, NRR, Plant System Branch, DLB A. Serkiz US NRC, NRR, DSR0 i J. N. Ridgely US NRC, NRR, PSB/ DBL Carl H. Berlinger US NRC, NRR, RSB, PWR-A l Warren H. Swenson US hRC, NRR/0 RAS /0RPW l 1

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Enclosure 2 4

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NRC NRR/RECION II - MISSISSIPPI POWER'& LIGHT' l i

i LICENSING ACTION STATUS MEETING l

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BETHESDA - MARCH 21, 1986 1

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NRC-MP&L LICENSING ACTION STATUS MEETING MARCH 21, 1986 AGENDA I. GENERAL & SPECIAL TOPICS OF INTEREST A. Plant Status / Outage Schedule J. G. Cesare B. RF01 Planning - Proposed Meeting J. G. Cesare of 4/23/86 C. RF01 Deferrals S Turbine Disc Inspections (43/31/1d . H. Hobbs/L. L. Kintner ADS Accumulators Peak Recording Accelerographs (OS/Jef f 6 )

HVAC/ Remote S/D Panel Reg. Guide 1.97 MSIV-Leak Control System C C.5 /3 ^/ I b)

Low Temp Protection, CST Cc5/Je/N)

Hydrogen Control (rS/J0/I') #

TDI D/G Div. II D. Technical Specifications S. H. Hobbs/L. L. Kintner

1. Status of Items Submitted L. L. Kintner

2. Planned Submittals (RF01 and others) S. H. Hobbs E. High Density Spent Fuel Racks J. G. Cesare/L. L. Kintner

1. Status of Review L. L. Kintner i

2. Remaining Licensing Actions J. C. Cesare F. Communications, Copy Distribution J. C. Cesare Requirements C. Updated FSAR, Change Notice Review J. G. Cesare Program Status H. TDI Diesel Generators, Planning / J. G. Cesare RF01 Scope /TDI OG

1. Division I D/G Overspeed Event, J. G. Cesare IEN-86/07 J16 MISC 86031801 - 2 g

l II. KEY LICENSING ACTIONS (NEAR TFRM)

A. ITEMS REQt' IRING NRC ACTION

1. Pump & Valve IST Program and Relief Requests oh[30/Ib)

(6/28/85)

2. RF01 Deferrals (covered above)

3. Technical Specification Changes (covered above)

4. Interplant Communications (1/10/86) [A ok/M

5. Recirculation Pipe (Cross) Cracking (3/10/86) ( CI/3 ///5)

6. RAI-Position Report on Reg. Guide 1.97 (2/14/86) ( 07/JF//l)

7. CST Vortex / Suction Design (2/15/86) (oy/30//?)

8. Reactor Internals Vibration Monitoring (2/22/86) (o f, /t f // 0 )

9. HDSFR (covered above) 1 1

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B. ITEMS REQUIRING MP&L ACTION (NEXT 90 DAYS)

1. OL Condition 2.C(10)c - Dynamic 3/26 Qualification of fuel handling .

and other equipment

< 2. Reactor Performance Improvements (a) Core Stability / Single Loop 3/28 Operations (b) Max Extended Operating Domain 4/8

3. OL Condition 2.C(33)(b), Station 3/31 Blackout

4. Financial Protection / Nuclear 4/1 Property Insurance

- New insurance industry policy

5. (a) Violation Response - UFSAR, 4/4 Failure to Perform 50.59 (b) Violation Response - UFSAR, 4/1 Failure to Reflect RPT Coastdown Analyses

6. (a) STA Team Concept Evaluating (b) Generic Letter 86-04 5/5

7. Fire Hazards Analysis, Annual 5/7 Revision

8. Technical Specifications (covered above) l t

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i III. ACTION ITEM LISTINGS Attachment 1 - MP&L Submittals Since Last Meeting l Attachment 2 - Forecast of MP&L Submittals over Next Ninety Days Attachment 3 - Forecast of Technical Specification Submittals

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MP&L SUBMITTALS SINCE LAST MEETING l

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MPLL NUCLEAR LICENSING & SAFETY DATE: 03/20/86 ACTION TRACKING MNA6EMENT SYSTEM RECENT MPLL LICENSIN6 ACTIVITIES PAGE: 1 l S ES R 333 33 33 33333 33333333 3333333333333333 333333333333333333 33333 E E333 33 3R RS S S SES S ES E333333332353333333313 333& g333333333 SU MITTAL DATE NRC REQUEST DATE MP6L CORRES. NUM RESPONSE MPLL CORRES. NUM TOPIC 0F SUBMlilAL KSCRIPi!ON MP&L ID NUM NEEDED TAC NUMBER 33333EER3333SRRE 3333 ESSE 3333313333333333 833333333333333333 333333333333333333333333333333338832333333333333333333333333 01/29/84 08/15/B5 TECH SPEC CH6 $UBMIT TS CH M6E 10 M LETE REPERENCE 10 6.9.1.13.f IN AECM-86/0023 PMI-B5/6900 TS 3.12.1.

10 51275 01/29/96 YES 04/02/B4 TECH SPEC CH6 PROCESS A 15 CHANGE ROSI THRU PSRC & SRC ADLIN6 REDUIREMENTS AECM-86/0023 TSPS 210 FOR ADDITIONAL SCRM DISCHAR6E VOLUME LEVEL INSTRUMENTATION ID 51529 MD VALVES M0 SUBM11 TO NRC.

01/29/86 YES 08/01/93 TECH SPEC CH6 PROCESS A TS CHANGE THRU PSRC & SRC TO RE'llSE FOOTNOTE TO l AECM-Bo/0023 AECM-83/0422 TABLE 4.3.3-1 (HPCS LEVEL B INTLCD MD SUBM11 TO MC.

10 51531 01/29186 YES // TECH SPEC CH6 PROCESS A TS CHM 6E RGST THRU PSRC & SF.C ON EICLUDING ITEMS AECh-56/0023 NRt RQ3T IN 6.10.1 FROM LIFETIME RETENT10N IN 6.10.2.1 AND SUBMIT TO ID 51557 MC.

01/29/86 06/03/B5 IECH SPEC CH6 PROCESS A 15 CHANGE RBST THRU PSRC & SRC RENAMING CERTAIN AECM-B6/0023 PMI-65/5380 PLM T SERVICE NATER VALVES IN TABLES 3.6.4-1, 3.B.4.1-1. MI ID 51566 3.B.4.2-1 AS DRYNELL CHILLED NATER VALVES MD SUMli TO NRC.

01/29/86 YES 01/15/85 TECH SPEC CH6 PROCESS A 15 CHNEE RBST THRU PSRC & SRC CORRECTIN6 FIRE PECM-86/0023 PMI-85/0583 PROTECT!UN INSTRUMENTATION lABLE 3.3.7.9-l.6 TYPD 'lH' TO 10 51569 'SH' MD SUBMli TO NRC.

01/30/B6 12/31/B5 LER B5-050-0 SUBMil LER CONCERNIN6 LON LEVEL REACTOR SCRAM CAUSED BY LDS!

AECM-86/0029 IR B5-12-14 0F CONDENSATE PUMPS.

ID 60095 01/30/86 12/31/B5 LER B5-050-0 SUMIT LER CONCERNING FAILURE OF HPCS INJECTION.

AECP-86/0029 1R B5-12-15 ID 60096 01/30/86 12/31/65 LER 85-050-0 SULMIT LER CONCERNING 19C5 DIESEL START DURING AECM-B&/0029 IR 85-12-16 TROU)LESHGOTING.

ID 60097 01/30/06 01/01/86 LER 86-001-0 SUBMli LER CONCERNIN6 REACTOR SCRM DURING STARTUP CAUSED B)

AECM-B6/0028 IR B6-1-1 LON VESSEL LEVEL.

ID 60096 01/31/86 12/06/95 SR B5-016/0 SUMIT FINAL SPECIAL REPORT CONCERNING D/611 DVERSPEED AECM-86/0034 AECM-85/0394 EYENT.

10 51483 01/31/06 01/15/86 HYDROGEN CONTROL PREPME SUBMITTAL TO ABBRESS LES K!NTNER REQUESTS FOR AECM-86/0009 MAEC ADDli!0NAL INFORMATION ON HYDRO 6EN PCOL B5/24.

ID 60193 3.

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MP&L NUCLEAR LICENSIN6 L SAFETV DATE: 03/20/B6 ACTION TRACKlh6 MANAGEMENT SYSTER RECENT MPLL LICENSING ACTIVITIES PAGE: 2 RSSSSESSSESSEESS S3333338 S333883333333333 33883333E333333333 333333333333333333523333333338ES881J888883355353332832385338 SUBMITTAL DATE MC REQUEST DATE MPLL CORRES. NUM ESPONSE MPLL CORRES. NUM 10 Pit 0F SUBMITTAL KSCRIPi!0N MP&L 10 NUM NEEDED TAC NUMBER E321133333332233 3333 SEES 333333318E3838E8 33388333333333E838 E333333333E288331888883E88833383E888833SES333333333333333333 02/07/86 01/22/86 TEES PAY FEES FOR REPLACEMENT AND REGUALIFICA110N EIAMS.(PART 55)

AECM-86/0032 MMC-B6/0021 ID 60224 02/10/B6 01/10/B6 LER SUBMli LER CONCERNIN6 CONTAINMENT PEETRATION ISOLAilDN MCM-86/0038 IR 86-1-4 VALVES LOCAL LEAK TEST RATE TESTING EICEEDING TECH SPEC ID 60200 TIME LIMli.

02/14/86 05/02/95 PART 21 REPORT SUBMli REPORT ON INADEDUATE COOLIN6 IN TDI DIESEL ENERATOR MC&66/0050 AECF85/0139 CONTRDL PANELS (LIEAR REACTOR FAILURES).

ID 50018 02/17/66 08/31/85 PAMI QLR RESPOND TO E C COMMENTS ON THE R.S. 1.97 POSITION E PORT IAN AECM-86/0030 ERC PROJ PLAN ERC PROJECT PLAN SECil0N 5.43.

ID 51208 l

02/17/B6 01/24/86 FEES PAY FEE FOR INSPECT 10N FOR PERIOD 03/31/B6 THR006H 06/22/96 AECFS6/0036 MAEC-86/0019 ID 60225 02/18/96 12/30/65 HYDRDSEN CONTROL SUBMIT 4TH GUARTER REPORT FOR 1986 RE6ARDING HYDROGEN AECFB6/0043 NFF-29 CONTROL ACTIVITIES.

10 60316 02/20/E6 YES 11/01/64 TECH SPEC CH6 TRANSMii A 15 CHANGE RQSi TO NLS ADDING A STRON6 MOT 10N AECM MAE; 64/0387 ACCELEROMETER 10 THE DRfNELL.

ID 50363 02/21/96 01/22/96 LER 66-003-0 SUBMIT LER CONCERNING REACTOR SCRAM DUE 10 A LDAD REJECT AECFB6/0053 IR 66-1-6 CAUSED BY 6 RID SNITCHING PROBLEMS.

ID 60276 l 02/22/B6  !!/01/94 BYhAMICTESilN6 SUBMli 10 NRC FINAL REPORT ON REACTOR VESSEL INTERNALS AECF86/0054 OLC 2.C.(9) VibEAi!0N PRO 6 RAM.

10 60288 02/26/86 01/02/06 MATERIAL LICENSE SUBMli E DUEST 10 RETIRE MATERIAL L1 TENSE 23-19573-01.

AECM-86/0044 MAEC-66/0007 l

ID 60229 02/26/f6 / / ANNUAL DPER. RPT. EVIEN AND SUBMIT TO NRC THE 1995 ANNUAL OPERAi!N6 REPORT.

MCFB6/0062 TECH SPEC IB 60349 02/20/B6 YES 07/16/92 TECH SPEC CHE PROCESS A 15 CHANGE ROST T au PSRC n SRC ADDING AUTO AECF06/0067 AECM-82/0324 SPRINKLER SYSTEM TO AREA 10, EL. 164; AUI BLD6 AND SUBMIT TC ID 51536 NRC.

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MPbl NUCLEAR LICENSING & SAFETY RECENT MP&L LICENSING ACTIVITIES PAGE: 3 DATE: 03/20/B6 ACTION TRACKING MANAGEMENT SYSTEM 83323R2E33332123 33321332 3333323332833333 333333333331333333 333333ms3333333333333333333333333S&3333333333333333333333333 SU6MITTAL DATE NRC REQUEST DATE MP&L CORRES. NUM RESPONSE MFnt CORRES. NUM TDPlc 0F SUBMITTAL DESCRIPT10N MPLL ID NUM DEEDED TAC NUM6ER ESE S S ESES S EES SES ESSES 373 3238333333333335 333283333333333333 3883333333333333335533333833383F3 SS3 33 3333 r3333333 3333333333 02/28/06 12/27/85 ILRT SUBMIT FINAL ILRT REPORT TO mR.

AECM-86/0039 MAEC-85/0419 10 60100 02/28/B6 02/1B/06 TECH SPEC CAHN6E PROCESS A TS CHANGE THRU PSRC AND SRC ON CLOSURE TIME FOR AECM-6e/0067 PMI-86/0966 RNR REACTOR HEAD SPRAY VALVE E12-F394 AS NOTED IN TABLE IC 60332 3.6.4-1.

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03/07/B6 12/06/85 6LB3.28 SALER/ATNS Snt TO SubMli A RESPONSE TO NRC REQUEST FOR ADDITIONAL AECM-86/0059 MAEC-E5/0413 INFORMATION DN 6L B3-2B POSITIONS 3.1 AND 3.2.

I 10 60286 1

03/10/56 // RECIRC CROSS S3MIT FINAL REFDRT DN RECIRC CROSS CRACKING.

AECM-86/0019 AECM-66/0019 ID 60389 03/14196 02/05/86 H16H DENSITY RACKS SUBMIT SPENT FUEL POOL LDADING PATTERNS DES 16MED TO AECP-86/077 NRC SITE VISIT MINIMIZE OCCUPATIONAL DOSE RATES. f ID 60564 03/15/66 09/20/95 HIGH DENSITY RACKS SubMli RESP 0 HSE TO RAI RESARDING THERMAL HYDRAULIC AECM-86/00ll MAEC-65/0275 CHARACTERISTICS OF THE HDSFR.

ID 60299 Y

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ATTACHMENT 2 FORECAST OF MP&L SUBMITTALS OVER NEXT NINEY DAYS

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MF&L NUCLEAR LICENSIN6 & SAFETY DATE: 03/20/B6 ACTI0h TRACKING MANAGEMENT SYSTEM FORECAST W EL LICENSING Ati!VITIES PAGE: 1 3333333333333333 33333333 3333833333333333 333333333333333333 33 3333 3 3 33 3385 83334a33333333 33 33 33 3 333 33 84 8883 33333333 332838 SCHEDULED DATE NRC REQUEST DATE MF6L ID NUM RESPONSE MP&L CORRES. Nun TOPIC OF SUBMITTAL MSCRIPi!DN NEEDED TAC NUMBER 3333883333333338 33333333 3833283333333333 833333333388833333 883333333333333333883333388333333333333833333333338388833333 03/22/96 02/20/Bo LER SUMIT LER CONCERNING RHR B M10 START CAUSED BY PERSOMEL ID 60454 IR 86-2-13 ERROR 03/26/B6 02/24/06 LER SubMli LER CONCERNING POS$1BLE DEFECTS ON FIRE RATED ID 60530 1R 86-2-15 PENEIRAT10N SEALS.

03/28/86 / / TECH SFEC CH6 PROCESS A 15 CHAN6E THRU PSRC MD SRC CONCERNING CORE ID 60153 TSPS 382 STABILliY MD SINGLE RECIRC LOOP OFERA110N AND SUHli TO WC.

03/28/06 02/26/06 LER SUMii LER CONCERNIES PROCEDURES NOT MEETING THE INTENT OF ID 60381 1R Bo-2-16 THE TECH SPECS. l I

03/28/66 VES / / RELOAD LIC. SUBM!i TS CHANGE ADDRESSING OLC 2.C.13(a) CORE STABILlif TO ID 51411 OLC 2.C.13(al EC.

03/29/06 02/27/86 APPLICAi!ON FEES PAY PART 50 APPLICAT10N FEE OF $4,596.00.

10 60565 MAEC-66/0045 03/31/86 09/20/B2 FART 21 REPORT SUMIT FINAL UN11110CFR21 REFORT CONCERNING STMDBY ID 50565 AECM-62/40B SERVICE NATER 'A' LOOP SYSTEM FLON.

03/31/66 04/01/95 6.. n. xN CON!ROL ESTABLISH FINAL LIST OF EQUIPMENT TO BE MALYIED. THl$ LIS' ID 50987 AECM-85/0069 NILL BE REQUIRED TO SURVIVE A HYDAD6EN BURN DURING A DEGRADED CORE ACCIDENT.

03/31/86 05/23/B5 HYDR 06EN IGNITORS SER SUPPL. 3, liEM 22.2 CONTAINS COMITMENTS FOR HYDRO 6EN ID51291 PMI-85/5tB3 16N!iDR TESTIN6 IN ADD 1110N TO TECH SPEC REQUIREIENT.

NRifE LETTEP TO MC 10 CLARIFY.

03/31/86 / / ROUTINE REPORT SUBMIT AWUAL PERSONNEL EIPOSURE MD MONiiORING REPORT 10 ID 60460 NLSAP 2.4 NRC.

04/01/96 / / PROCEDURE SUMIT ANNUAL REPORT OF DNSITE PROPERTY DAMAGE INSURMCE 10 10 60526 NLSAP 2.4 NRC.

04/05/86 03/06/B6 UFSAR M C ACTION RESPOND TO NRC VIOLAi!ON B6-01-01 REGARDING FAILUPE TO 10 60574 MCC-B6/0056 UPDATE THE FSAR 1RPT C0ASTD0m).

6 MP&L NUCLEAR LICENSING L SAFETY

• FORECAST MP&L LICENSIN6 ACTIVITIES PAGE: 2 DATE: 03/20/06 ACT10N TRACKING MANA6EMENT SYSTEM 3333388228388223 33333388 3333383833333333 338333333333338333 333383333883333333338333333338383333333333333333333833333333 SCHEDULED DATE NRC REQUEST DATE MP&L ID MUM RESPONSE MPLL C0k2ES. NUM TOPit 0F SUBMITTAL DESCRIPi!0N NEEEED TAC NLMEER 8333333333333333 38338333 33333F3228333333 333333338833333333 3388333383333388388388333338833SSSSSSESSSSSSR 833333333333333 04/07/86 / / TECH SPEC CH6 PROCESS A TS CHANGE R0ST iMU-PSRC & SRC ON SURVEILLANCE OF ID 50777 TSPS 150 'JTOMATIC DEPRESSURIZAi!ON SYSTEM (ADS) 11MER MD ShllCH AND

.dlMIT TO NRC.

04/07/B6 YES  !!/01/84 TECH SPEC CH6 PROCESS A TS CHAN6E ROST TMU PSRC & SRC ON ELECi3 CAL ID51530 MAEC-84/0381 ISOLATION MTNEEN CONTROL ROOM MD REMOTE SHU1DONN PWEL MD SUMli TO NRC.

04/07/06 YES 11/01/84 TECH SFEC CH6 PROCESS A TS CHANGE ROST THRU PSPC & SRC ON 2ND LEVEL OF ID 51537 MAEC-B4/0387 UNDERVOLTAGE PROTEti!DN FOR THE DIVISION !!! PONER SUPPLY AND SUBMli 10 NRC.

04/07/96 YES 11/01/84 TECH SPEC CH6 PROCESS A TS CHANGE ROST THRU PSRC L SRC ON DIVISION !!!

10 51538 MAEC-84/03E7 DIESEL BENERATDR RETURNING 10 STMDBf FROM TEST MODE NHEN li RECElvES M ACCIDENT SIGNAL M0 SUBMIT TO NRC.

1 04/07/86 1ES 05/17/85 TECH SPEC CH6 PROCESS A TS CHANGE ROST THRU PSRC & SRC CORRECTING THE 10 51596 PMI-85/5117 EICLUSION MEA FIS. 5.1.1-1 MD CHAN6ING THE REF TO FSM 4.3 TO 9.1 FOR SPENT FUEL KEFF IN TS 5.6.1.a MD SUBMIT TO NRC.

I 04/07/E6 YES 03/12/B5 TECH SPEC CH6 PROCESS A TS CHANGE RGST THRU PSRC & SRC RE90ESilN6 APPROVAL ID 51635 MP6E-55/0053 0F OPERATION IN THE MAllMLM EITENDED OPERATING DOMAIN MD SUMli 10 NRC.

04/07/86 03/07/06 UFSAR NRC ACTION RESPOND TO NRC VIOLATION 86-01-01 REGARDING FAILURE TO ID 60575 MAEC 86/0057 PERFORM SAFETV EVALUAT!DNS PER 10CFR50.59.

04/15/86 01/31/86 HYDR 06EN CONTROL PREPARE AND SUBM11 A REVISE 1 SCHEDULE FOR MEETING THE ID 60231 AECM-66/0009 HYDRO 6EN RULE REQUIREMENTS.

04/15186 / / ROUTINE REPORT SubM!i MONTHLY OPERATING REPORT 10 NRC FOR TE MONTH OF ID 60527 NLSAP 2.4 MARCH.

l l

l 04/23166 05/07/85 FlkE HAIARDS ANALY SUMIT REVISION TO THE FIRE HAIARDS MALYSIS TO NRC. l ID 60434 AECM-85/0129 04/23/66 YES // UFSAR NEN ACT10N ADMESS SHIFT SUPERV153R MD SHIFT SUPERINTENDENT ID 604B0 VIOL. B4-16-01 RESPONSil!LITIES FOR FSAR SECTION 13.1. REVISE MD SUMli TO NRC.

04/25/86 YES // TECH SPEC CHM 6E PROCESS A TS CHM 6E THRU PSRC MD SRC 10 MME TECH SPEC ID60340 RF01 SCHEDULE A6REE NITH MPLL*S RES GulK 1.97 POSli!0N AND SUMIT TO NRC l t.

MP&L NUCLEAR LICENSING & SAFETY DATE: 03/20/B6 ACTICN TRACKIN6 MANAGEMENT SYSTEM FORECAST MPLL LICEkSING ACTIVITIES PAGE: 3~

3333333333333333 83333333 3883333338888333 33ES83333333333383 E SS S S E SS SS E S S S S S SS SS S SSS E S SE S S S S 38 33 3 3 8888 8333 3333 8383 3 33383 SCHEDULED DATE MC REDUEST DATE MP&L ID NUM RESPONSE MP&L CORRES. NUM TOPIC ti SUBMITTAL KSCRIPTION NEEDED TAC NUMBER -

3333333833333333 33333333 3333333333333333 333333333333333333 333333333333333333333333333333322333383833333333333333333333 <

04/28/86 YES // TECH SPEC CH6 PAOCESS A TS CHANGE THRU PSRC-MD SRC ON DIESEL GEERATOR 10 60113 6.L. 64-15 $URVEILLMtE RELAIATION MD SUBMli TO MC.

04/30/86 YES 11/01/64 TEtd SPEC CH6 PROCESS A TS CHANGE R9ST THRU PSRC L SRC ON COMPLETION OF ID 51535 MAEC-54/0387.20 STANDBY SERVICE NATER BA!!N A MODIFICATION AND SUN IT TO M C 04/30/86 1ES 02/17/86 O!V.11 TEARD0M SUBMIT A REQUEST FOR PMTIAL TEARDOM OF TE DIVISION 11 ED6 ID 60442 CDK INST. AT RF01. THIS SUBMITTAL SHOULD INCLUDE A CONCURRENCE FROM THE TDI 0.6.  !

l 04/30/66 / / R0dTINE REPORT SunMIT AMUAL ENVIROMENTAL REPORT TO NRC.

ID 60529 NLSAP 2.4 ,

04/30/86 // ROUTINE REFORT SUHli ANNUAL RADIOLOGICAL ENVIR0 MENTAL REPORT TO NRC.

10 60541 NLiAF 2.4 05/09/86 01/02/E6 TECH SPEC CH6 PROCESS A TS CHANGE THRU PSRC & SAC TO PLACE THE DRYNELL 10 60170 PMI-96/0201 BYPASS LEAKAGE TEST ON ThE 3AME FREQUENCY AS THE CONTA! MENT ILRT AND SUBMIT TO NRC.

05/09/96 / / TECH SPEC CAHNSE PROCESS A TS CHANGE THRU PSRC M3 SRC ON ADCRESSING SECONDAF ID 60334 ROUilNE TS CH6 Y CONTAIMENT INTEGRITY MILE MOVIN6 FUEL.

05/09/86 // TECH SPEC CHANGE PROCESS A TS CHANSE THRU PSRC AND SRC ON CORRECTING REACTOR ID 60337 ROUTINE TS CH6 CORE ISOLATION COOLING SYSTEM STEAM LINE FLON-H16H SETPOINT IN TABLE 3.3.2-2.

05/14/B6  !!/15/95 IE BULLETIN RESP. SulMIT IEB 85-03 RESPONSE CONCERNING MOV COMON RODE 10 51460 MAEC 85/0379 FAILURES DURING PLMT TRMSIENTS DUE TO IMPROFER SWITCH SETTIN6S.

05/15/86 / / ROUTINE REPORT SUBMli MONTHLY OPERATING REPORT TO NRC FOR MONTH OF APRIL.

ID 60518 NLSAP2.4 05/23/86 02/26/86 UFSAR NRC ACTION PREPME MD SUBMli UFSM ' FACILITY CHANGE' LISTING TO MC.

10 60482 NLSAP 2.16 -

05/23/B6 02/26/96 UFSAR M C ACTION PREPME AND SUBMli UFSM ' FACILITY CHAWE' LISi!NG TO MC.

1060482 NLSAP 2.16

/3

MPLL WCLEAR LICENSING b SAFETY DATE: 03/20/h ACT10h TRACKING MANAGEMENT SYSTEM FORECAST MP6L LICENSING ACTIVITIES PAGE: .4 3333133333333338 18333353 5333333333838333 533834831335333338 583333343838S81883833333183333818333E31883333838333333333333 SCHEDilLED NTE NRC REQUEST DATE MPhL ID mn RESP 0h51 MPLL CORRES. NUM TOPlc 0F SUBnlii n MSCRIPTION EEDED TAC NUAER S333883381333383 33333333 323333385E388333 SSESISSERESf3SFSSS S3883333358388E583383838888839883333383338333333333333333383 05/30/06 12/30/85 HYDRO 6EN CON! DOL SUDRil IST GUARTER EPORT FDR-8986 K6ARDING HYOR00EN ID 60315 NPF-29 CMTROL ACTIVITIES.

05/30/B6 TES  !!/22/95 DR/BR R/S SUBnli A POSli!0N ON TIE M/S THAT THE TDI 0.6. PROVIMS.

ID 60444 MAEC-BS/0395 THIS SUMITTAL MILL KPLKE IFLL's POSITION SUM 11TED DN 10/01/95 DN DR/64. THIS N!LL M W SED ON INFO FROM NPE.

06/02/B6 11/22/B5 TECH SPEC chi PROCESS A TS CHANGE ROST THRU PSRC AND SRC ON INSTALLING A ID 60071 MAEC-85/0389 MACTOR PRES $URE INTERLOCK DN THE INJECT 10N VALVES ON LPCS

& LPCI AND SUORif TO NRC.

06/07/96 04/30/85 HYDR 06EN CONTROL ENDORSE APPLICABLE PORI!DNS OF THE HC06 1/4 SCALE TEST -

ID 50467 PMI-65/4313 FACILITY FINAL MSI6N EPORT.

, 06/07/86 04/30/85 HYDRD6EN CONTROL ENDORSE HC06 EVALUATION REPORT ON NEVADA TESTS IF APPLICA6LE l ID 50533 PMI-85/4313 i

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4 ATTACMENT 3 FORE N T OF TECHNICAL SPECIFICATION SUBMITTALS

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DATE : 03/20/86 NUCLEAR LICENSING AND SAFETY PROJECT STATUS REPORT LSI NunM k $86TER TECH SPEC CMN6ES DUE TO NRC PA&E: 1 RSPNS6L W 6 18inm. ETIVITV NUMER MSCRIPflou IgASSIGNED BUE DATE 51542 BC05-1.02 PROCESS A TS CMN6E ROST THRU PSRC & SRC ADOING A STRONS ES 03/20/06 M0110N ACCELER0nETER TO THE DRvutLL 20 SUMIT 10 MC. GILDREATH 601 3 868.02 PRDCESS A 15 CH M 6E IMfrJ PSRC AND SRC CONCERNING CORE ES 03/28/06 STA41LITY AND $1NELE RECIRC LOOP OfthAi!DN MD SU6M11 TO DUEFORD NRC.

50777 6821 5.02 PROCESS A 15 Ch4N6E R951 THRU PSkt & SRC ON SURVEILLANCE OF ES 04/07/66 Auf0M11C MFRESSUR!!ATION SYSTEM (ACS) TIMER MD SuliCH AND SCOTT SUH11 10 NRC.

51530 BCe!-1.02 PROCESS A 15 CMNEE RGST THRU PSRC & SRC ON ELECTRICAL ES 04/07/06 ISOLAi!0N ETNEEN CONTROL ROOM AND REMOTE SNUTDONN PANELSCOTi MD SUHli TO MC.

51537 BPB1 1.02 PROCESS A 15 CHAN6E RGST TMU PSRC n SRC ON 2ND LEVEL OF ES 04/07/66 UNDERVOLTAGE PROTECT 10N FOR THE DIVISION !!! PONER SLfFLY $!L6REATH M D SubM!1 10 M C.

51538 bP91-2.02 PROCESS A TS CMNGE RGST THRU PSRC & SRC ON 91 VISION !!!ES 04/07/86 DIESEL GENERATOR RETURNING TO STANDIV FROM TEST N00E 6!LDREATH WHEN 11 RECEIVES M ACCIDENT Sl6NAL AND SutMIT TO EC. 51596 E23.02 PROCESS A IS CHANGE ROST THRU PSRC & SRC CORRICTING THEES 04/07/86 EICLUSION MEA FIS. 5.1.1 1 MD chm 61NE THE KF 10 FSAR 4.3 CLE66 10 9.1 FOR SPENT FUEL KEFF IN TS 5.6.l.a AND SulMil TO NF.C.

51635 142.02 PRDCESS A 15 CHANGE RGST TMU PSRC & SRC RE00ES11NSES AFPR0 VAL 04/07/06 0F OPERAi!DN IN INE Ml! MUM EITENDED OPERAi!N6 DOMAIN MD BURFORD SU Hli 10 M C.

51575 6833-1.02 PROCESS A TS CHAN6E ROST T M U PSRC n SRC DELE 11N6 DR ES 04/21/96 ALTERIN6 NOTE TO 15 4.3.4.2.3 20 MVISING EDC RPi DREArER SCOTT MC SUPPMS$10N 11E AND SusM!i TO NRC.

60113 EP75-1.02 PROCESS A 15 CMNGE TMU PSRC AND SRC ON IIESEL KNERATOR ES 64/28/86

$URVEILLANCE ELAIA110N M0 SUDMIT 10 NRC. MENDRV 64340 B00.02 PROCESS A IS CMNGE IMU PSRC AND SRC 10 RME TECH SPEC ES $4/20/06 AGRIE NiiH IF6L*S M6. IUlK l.97 POSiff th. Stoli 51535 BP41-3.02 PROCESS A 15 CMNGE RIST iMU PSRC n $RC ON COMPLEll0N OF ES 64/30/06 SIMDBY SERVICE NATER BASIN A ROBIFICAll0N AND SUtnli 10IRf8HET NRC IL Y

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I MTE : 03/20/06 NUCLEM LICENSINE Aug SEETY PROJECT STATUS MPMT

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LSI NURIER 586TSCR TECH SPEC'CMNES SWE 10 iRC $

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g e-Ml?0 377.02 PROCESS A 15 CHANGE INRU PSRC & WC TO PLEE TE BRYMELL ES  ; 05/M/86 BYPASS LEMAGE TEST h THE SAnt FROUEKf AS TE Comitl8 BENT Koil I ILRT ANC SUBRIT 10 MC.

H334 ET48.02 PRKESS A 15 CMM6E IMRU PSRC AND SRC ON ADDRESSill6 ECONMR MLS 05/09/66 i

V CONTAllNIENT INTE6411Y NHILE WWINE FEL. NUGNEf . ,

t 60337 E71.02 PRKESS A 15 CMNEE THRU PSRC MD SRC ON CORRECT!II6 MAtiOR El 05/09/06 CORE ISOLA 110N Coot!NG SYSTER STEM Lilf FLON-HIEN CETPolNT E!LMEATH IN TA6LE 3.3.2-2. g i

51546 ED23-1.02 PROCESS A 15 CHAh6E ROST ThRU PSRC L SRC DELE 11N MYNELL EC 05/28/B6 PARilCULATE M0mlT06 FROM 15 3.4.3.14 M0 SubMli 10, MC. SILHEATH 51593 E22.02 PROCESS A 15 CHANGE kGST THRU PSRC & SRC ON REACiJR CORE ES 05/30/16 ISOLATION COOLING SYSTEM Tint MLAYS FOR illlER RELAYS MD EILHEAih SUDMIT 10 MC.

51599 E24.02 PROCESS A IS CHANGE R95T iMRU PSRC L SRC ON THE RMUAL ES 05/30/96 juillATION/ TRIP CAFAllLili N001FICAT10N OF THE ATUS RPT SILMEATH SYSTER MD SutM!i 10 MC.

60129 E51.02 PADCESS A 15 CHA45E THRU PSRC MD SRC CORRECTING hlS 05/10/B6 itP06RAPHICL ERROR IN 15 3.4.5 ACT10N 10 CHANGE '0FERABLE' E!LMEATH 10 ' OPERATIONAL' MD SUBM!i 10 PRC.

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