ML20204E956
| ML20204E956 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/23/1986 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-86-10, NUDOCS 8608010377 | |
| Download: ML20204E956 (20) | |
Text
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JUL 2 31986 Docket No. 50-416 LICENSEE: Mississippi Power & Light Company (MP&L)
FACILITY: Grand Gulf Nuclear Station, Unit 1
SUBJECT:
SUMMARY
OF JUNE 13, 1986 MEETING REGARDING LICENSING ACTIONS The purpose of the meeting was to discuss the status and schedule of licensing actions on Grand Gulf Unit 1. Enclosure 1 is a list of attendees. Enclosure 2 is an agenda, status and forecast of licensing activities prepared by the licensee. Enclosure 3 is the status and schedule of licensing actions prepared by the staff. Enclosure 4 is the status of review of FSAR change notices.
The licensee s'ta1!ed that the plant is entering the summer peak load season.
The load is expected to be limited to 80% power by the capacity of the cooling tower. Cooling tower modifications during the first refueling outage (RF01) are planned to increase its capacity. The refueling outage is currently scheduled to start September 1, 1986 and to end in November 1986.
The licensee has created a new position of plant licensing superintendent to coordinate plant support for licensing activities in a nev Plant Licensing Group. The new group will also coordinate compliance activities at the plant.
The licensee stated that several submittals regarding Technical Specification changes are planned within the near term. Changes needed for RF01 include:
changes to the scram discharge volume vent and drain valve submittal and the drywell vacuum breaker submittal in accord with staff discussions; a new Technical Specification regarding air leakage from the automatic depressuriza-tion system; and, draw down time for secondary containment when the primary containment is open to secondary containment. Changes that will be needed after RF01 are: deletion of chlorine detectors; changes to the drywell air-lock specification to facilitate testing; and, changes to specifications for a stuck open relief valve action statement that presently requires plant shut-down if the valve is not closed within two minutes. A complete list of sub-mittals made since the last meeting and forecast for the next 3 months are given in Enclosure 2. Two potential submittals not listed in Enclosure 2 are: proposed RCIC test with loss of A. C. power; and, deferral of instal-lation of seismically qualified light bulbs for the control room panels (RG 1.97).
The staff provided a schedule for issuance of near term licensing actions in Enclosure 3. The licensee stated that additional information regarding single loop operation (SLO) and maximum extended operating domain (ME0D) would be submitted in June 1986. The licensee said that three other actions not listed in part 1 of Enclosure 3 will be needed prior to RF01. These actions are safety evaluations for: the TDI diesel generator Division II inspection submitted June 7,1986; relief from the ASME Code for certain inservice e60801o377 PDR e60723 P
ADOCK 05000416 -
inspections; and, approval of intraplant communication modifications. The licensee is presently planning for a 100% inspection of the Division II diesel generator versus the June 7 submittal which is for a partial inspection.
Approval of a partial inspection will shorten the refueling outage time.
Certain inservice inspections per the ASME Code Section XI will be performed during RF01, and evaluation of the inspection programs, particularly sampling of supports for inspection, is needed prior to inspection. Intraplant communi-cations tests are currently scheduled for mid-August and therefore the evaluation of modifications is needed the first part of August.
The licensee stated that HCOG is preparing the Mark III containment emergency procedure guidelines and that HC0G will integrate them with the BWR Owners Group BWR emergency procedure guidelines. The licensee commented regarding other items on the agenda (Enclosure 2) as follows.
I.E. A response to Generic Letter 86-10 is in preparation. Preparation of the response will include identification of the GGNS Fire Protection Program, includ,ing the instrumentation now located in the Technical Specifications and proposing a license amendment to revise the Fire Protection license condition and delete Technical Specifications regarding fire protection instruments. Licensee estimates the first quarter of 1987 for the submittal.
I.F. A change to Relief Request No. 8 is planned to change a periodic test each refueling firm a hydrostatic test to a leakage test. Review of the ISI 10 year program shows that more items should have been included in the first 40 month segment. Subsequent to the meeting, the NRC staff said that as long as all components required to be inspected in the 10 year interval were completed in that interval, the particular 40-month segment in which they are inspected is not significant.
I.G. After receipt of the NRC staff's generic safety evaluation report on TDI diesel generators, MP&L will submit a letter responding to the staff's SER and endorsing the TDI Owners Group DR/QR Report, as applicable.
This letter will identify the maintenance and surveillance procedures
. for the GGNS Unit 1 TDI diesel generators pursuant to license condition 2.C.(25)(b).
I.K. The status of the program to review the changes made to the original FSAR in the updated FSAR was outlined (Enclosure 4). The screening phase of 1 change notices (CNS) has been completed by the reviewers and 70% of the review items have gone to the Plant Safety Review Committee. Of 358 change notices reviewed, 188 required 50.59 evaluations and 25 required commitment deletion resolution. Three changes in which commitments were deleted will be submitted to the NRC for review. There were no unidentified safety questions found in the 50.59 evaluations.
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II.B.5 The licensee advised that relief may be needed regarding operator license exam applications because of revised Form 398 which became effective April 1, 1986. This form does not allow training to be counted in meeting the experience requirement. The licensee is in touch with Region II staff regarding this matter.
The NRC staff questioned the referencing of the updated FSAR in licensing documents by the acronym FSAR because that is the acronym used for the original FSAR. The updated FSAR is substantially different in organization from the original FSAR because of the incorporation of answers to questions and letters of commitments into the updated version and because in some cases description of equipment is updated. The reason the licensee prefers use of the same acronym is so that a multitude of plant procedures and evaluations that reference the FSAR will not have to be reviewed and modified to use a new designation such as UFSAR. Subsequent to the meeting, the NRC staff discussed the matter internally and concluded that the updated FSAR should continue to be referenced by the acronym FSAR. Absent a more specific reference or date, such a reference will be taken to mean the latest version of the updated FSAR.
Ldc %
L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated cc w/ enclosures:
See next page l
l l
l 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 1038S 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 Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2, Box 399 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 Jackson, 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 ,
4 Enclosure 1 June 13, 1986 Meeting Re Licensing Actions NRC - MP&L Name Affiliation Ward F. Smith USNRC Resident Inspector L. L. Kintner USNRC Project Manager H. C. Dance USNRC Project Section Chief, RII M. L. Crawford MP&L Supervisor, Nuclear Licensing J. G. Cesare MP&L Manager Nuclear Licensing J. L. Robertson MP&L Plant Licensing Superintendent G. H. Davant MP&L Regulatory Compliance Supervisor L. F. Daughtery MP&L Compliance Group S. H. Hobbs MP&L Manager, Compliance g.__. .p _, __ _ - ., _ _ _ _ _ _ . _ _ _ _ .
Enclosure 2 NRC-MP&L LICENSING ACTION STATUS MEETING JUNE 13, 1986 AGENDA I. GENERAL & SPECIAL TOPICS OF INTEREST A. Plant Status / Outage Schedule J . 's . Cesare B. Establishment of Plant Staff Licensing Section J. G. Cesare C. Technical Specifications
- 1. Status of Items Submitted L. L. Kintner
- 2. Planned Submittals (RF01 & Others) S. H. Hobbs D. High Density Spent Fuel Racks L. L. Kintner/
J. G. Cesare E. Fire Protection
- 1. GL-86/10 Guidance J. G. Cesare
- a. UFSAR Changes
- b. TS Deletions / Procedure Generation
- c. OL Condition Revision
- 2. Appendix R - Site Visit (6/17-18/86) J. G. Cesare F. ISI Ten-Year Program
- 1. Status of Review L. L. Kintner
- 2. New Licensing Actions J. G. Cesare G. TDI Diesel Generators
- 1. Partial Teardown L. L. Kintner
- 2. NRC Generic SER J. G. Cesare
- 3. OLC 2.C(25).b Response J. G. Cesare J10 MISC 86061201 - 1
. I H. Reactor Performance Improvements ,
- 1. Status of Review
- a. Core Stability / Single Loop Operations L. L. Kintner
- b. Maximum Extended Opertting Domain L. L. Kintner
- 2. Remaining Licensing Actions L. L. Kintner/
J. G. Cesare I. SB0 Test Report S. H. Hobbs
- Status of NRC Review J. Regulatory Guide 1.97 S. H. Hobbs
- Seismic Light Bulbs K. UFSAR CN Review - Status J. G. Cesare L. NRC Project Manager's Agenda at GGNS J. G. Cesare II. KEY LICENSING ACTIONS (NEAR TERM)
A. NRC Action
- 1. Hf h Density Spent Fuel Racks Covered Above)
- 2. ISI Ten-Year Program (Covered Above)
- 3. ISI Pump and Valve Program & Relief Requests
- 4. Core Stability / Single Loop Ope' rations (CoveredAbove)
- 5. Maximum Extended Operating Domain (Covered Above)
- 6. Intraplant Communications
- 7. STA Team Concept
- 8. Reactor Internal Vibration Monitoring
- 9. TDI D/G Partial Teardown (Covered Above)
J10 MISC 86061201 - 2
B. MP&L Actipn
- 1. CS/5LO, Supplemental Tech. Spec. Revision 6/13
- 3. ISI - Revised Relief Request 6/20
- 4. Fire Protection
- a. RAI - Raceway Supports 6/20
- b. Additional Exceptions / Clarifications 6/20
- 5. Operator License Exam Applications 7/10
- 6. Cycle 2 Reload Licensing Amendment Request 7/14
- 7. TDI D/G OLC 2.C(25).b/ Generic SER Response ?
- 8. Resolution of IEB 79-08/II.K.1.10 Issue ?
J10 MISC 86061201 - 3 J5
e 6 KEY SUBMITTALS - SINCE LAST MEETING J10 MISC 86061201 - 5 p
HP&L NUCLEAR LTCENSidS & SAFEVY DATE: 06/12/86 ACTION TRACXING MANAGEMENT SYSTEM RECENT MF&L LICENSING ACTIVITIES PAGE: 1 SUBMITTAL DATE NRC REQUEST DATE MP&L CORRES. NUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUBMITTAL DESCRIPTION MF&L ID NUM NEEDED TAC NUMBER 05/13/86 12/30/85 HYDR 0 GEN CONTROL SUBMIT IST GUARTER REPORT FOR 1936 REGARDING HYDR 0 GEN AECM-86/0107 NFF-29 CONTROL ACTIVITIES.
ID 60315 05/13/86 // ASME CODE CS N-411 SUBMIT TO NRC REQUEST TO USE ASME CODE CASE N-411 AS AECM-86/0127 X ALTERNATIVE TO DAMPING VALUES SPECIFIED IN R.G. 1.61 ID 60966 CURRENTLY IN USE.
05/14/86 11/15/85 IE BULLETIN RESP. SUBMIT IEB 65-03 RESPONSE CONCERNING M0V COMMON MODE AECM-86/0135 MAEC-85/0379 FAILURES DURING PLANT TRANSIENTS DUE TO IMPROPER SWITCH ID51460 SETTINGS.
05/16/86 // FERIODIC REPORT SUBMIT MONTHLY OPERATING REPORT TO NRC FOR AFRll 1986.
AECM-86/0139 x ID 60967 05/16/86 01/28/86 HUMPHREY SUBMIT TO NRC CLARIFICATION OF PLANNED ACTIONS TO RESOLVE AECM-86/0143 AECM-86/0012 CONCERN OF CHUGGING FROM YENTING GASES AND STEAM SUFFRESS ID 60968 FOOL THRU RHR RELIEF VALVE DISCHARGE.
05/19/86 YES 03/21/86 TECH SFEC CHANGE PROCESS A TS CHANGE REQUEST THROUGH PSRC AND SRC ON E0C-RFi AECM-86/0150 PMI-86/1385 BREAKER ARC SUFFRESSION AND SUBMIT TO NRC.
ID 60689 05/19/86 YES 11/01/84 TECH SPEC CHG PROCESS A TS CHANGE RGST THRU PSRC & SRC ON COMPLETION OF AECM-86/0150 MAEC-84/0387.20 STANDBY SERVICE WATER BASIN A MODIFICATION AND SUBMIT TO NRC ID 51535 05/19/86 YES 11/01/84 TECH SPEC CHG PROCESS A TS CHANGE RQST THRU PSRC & SRC ON 2ND LEVEL OF AECM-86/0150 MAEC-84/0387 UNDERVOLTAGE PROTECTION FOR THE DIVISION III POWER SUPPL 1 ID 51537 AND SUBMIT TO NRC.
05/19/36 YES 11/01/84 TECH SPEC CHG PROCESS A TS CHANGE RQST THRU FSRC & SRC ON DIVISION III AECM-86/015.' MAEC-84/0387 DIESEL GENERATOR RETURNING TO STANDBY FROM TEST MODE WHEN ID 51538 IT RECEIVES AN ACCIDENT SIGNAL AND SUBMIT TO NRC.
05/19/86 // EP EXERCISE SUBMIT TO NRC SCENARI'0 FOR LIMITED RADIOLOGICAL ASSESSM AECM-86/0155 X EXERCISEON5/22/86.
ID 60969 05/23/86 // TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC AND SRC ON DIESEL GENERATOR AECM-86/0157 G.L. 84-15 SURVEILLANCE RELAXATION AMD SUBMIT TO NRC.
ID 60113 05/22/86 // TECH SPEC CHANGES SUBMIT TO NRC (ROPOSED CHANGES TO TECHNICAL SPECIFICATIONS AECM-86/0157 X CONCERNING AC ELECTRICAL POWER SOURCES.
ID 60977
MP&L NUCLEAR LICENSINi & SAFETY DATE: 06/12/86 ACTION T!!ACXING MANAGEMENT SYSTEM RECENT MP&L LICENSING ACTIVITIES PAGE: 2 SU6MITTAL DATE NRC REQUEST DATE MPIL CORRES. NUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUBMITTAL DESCRIPTION MF&L ID NUM NEELED TAC NUMBER 05/28/86 07/23/85 TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC AND SRC TO DELETE AECM-86/0164 PMI-85/7346 SURVEILLANCE REQUIREMENT ON DRYWELL AIRLOCK INFLATABLE SEAL, ID 60125 AND SUBMIT TO NRC.
05/28/86 YES 04/02/86 INTRAPLANT C0MMUN. SUBMIT TO NRC ADDITIONAL INFORMATION REQUESTED ON AECM-86/0100 MAEC-86/0097 INTRAPLANT COMMUNICATIONS SYSTEMS TEST.
ID60970 05/28/86 05/02/86 RESOLVED GEN ISSUE SUBMIT TO NRC SCHEDULE FOR IMPLEMENTATION OF RES01VED AECM-86/0158 MAEC-86/0132 GENERIC ISSUES.
ID 60971 05/28/06 YES // TECH SPEC CHANGE SUBMIT TO NRC TS CHANGE REQUEST DELETING DRfWELL AIRLOCK AECM-86/0162 X SEAL PP.ESS. INSTRUMENTATION 31 DAY CHANNEL FUNCTIONAL TEST ID 60972 FROM SURVEIL. REG. 4.6.2.3.d.1.
05/30/86 11/22/85 ECCS INTERLOCIS RESPONDTONRCsREJEC.ON(1)0MISSIONOFIEYLOCIEDCONTROL AECM-86/0ll! MAEC-85/0389 SWITCHESORCONTINUEDIMPLEMENTATIONOFT.S.4.4.3.2.B,(2)
ID 60275 OMISSION /INTERLOCISTORSP(3)LPCI/LPCSSETPOINTOF519psig.
05/30/86 03/31/86 MSIV VALVES PREPARE LETTER TO NRC ON ELIMINATION OF FF01 DEFERRAL ITEM AECM-86/0128 SHH REQUEST E32-2 BASED ON NPE SAFETY EVALUATION.
ID 60761 05/30/86 03/27/86 MSIV-LCS NLS TO PROVIDE NRC WITH A SCHEDULE FOR RELNALY2ING MSIV LCS AECM-86/0128 TELECON ISOLATION COMMITMENT FOR DELETION INSTEA: 0F WITHDRAWAL.
ID60805 05/30/86 11/22/85 TECH SPEC CHG PROCESS A TS CHANGE ROST THRU PSRC AND SRC ON INSTALLING A AECM-86/0!!! MAEC-85/0389 REACTOR PRESSURE INTERLOCr 0N THE INJECTION VALVES ON LPCS ID60071 & LPCI AND SUBMIT TO NRC.
05/30/86 YES // ADS BYPASS TIMER SUEMIT TO NRC DESIGN CHANGE MADE TO BfPASS TIMER OF ADS A C AECH-86/0163 X THE EFFECT ON PROPOSED CHANGES TO TS SUBMITTED IN ID60973 AECM-66/0032.
06/02/86 02/13/86 GL 86-04 SUBMIT RESPONSE TO GL 86-04 TO NRC.
AECM-86/0142 MAEC-86/0051 ID60622 06/02/86 04/25/86 EFFLUENTS SUBMIT EFFLUENT DATA TO BROOXHAVEN NATIONAL LAE0RATORY.
AP0-86/0124 MAEC-86/0017 ID 60860 06/02/86 05/23/86 STA TEAM CONCEPT SUBMIT RESPONSE TO RAI REGARDING STA TEAM CONCEPT.
AECM-86/0169 MAEC-86/0163 ID60927
~ '
MP&L NUCLEAR LICENSING L SAFE 1Y DATE: 06/12/86 ACTIONTRACITNGMANAGEMENTSYSTEM RECENTGF1LLfCENSINGACTIVITIES PAGE: 3 SUBMITTAL DATE NRC REQUEST DATE MFIL CORRES. NUM RESF0NSE MP&L CORRES. NUM TOPIC 0F SUEMITTAL DESCRIFTION MP&L ID NUM NEEDED TAC NUMfER 06/02/06 // SLO /ME00 SUBMIT TO NRC INTEGRATED PACIAGE OF FINAL PROPOSED TS AECM-86/0160 AECM-86/0129 CHANGESFORCORESTABILITY/ SLO &ME00.
ID 60974 J
06/04/86 YES // NPD & PSRC CHANGES SUEMIT TO Nic PROPOSED AMENDMENT TO OPERATING LICENSE AECM-86/0168 X PROVIDING CHANGES TO NPD ORGANIZATION CHART AND COMPOSITION ID 60975 0F PLANT SAFETY REVIEW COMMITTEE.
06/05/86 04/16/86 HDSFRT/HISSUES SUBMITREPORTOFHDSFRT/HISSUESTONRC.
AECM-86/0176 PMI-86/2511 1 ID60796 06/05/86 . // HDSFR TS CHANGES SUBMITTONRCTSCHANGESTOTS3/4.7.9.1AND5.6.3 AECM-86/0176 AECM-86/00ll CONCERNING INSTALLATION OF HIGH DENSITY SPENT FUEL RACKS.
ID60976 06/09/86 06/02/86 OPERATOR QUALIF SUBMIT ADDITIONAL MEDICAL INFORMATION ON WILLIAM M. SHELLY AECM-86/0173 PMI-66/4220 TO REGION II.
ID 60955 l
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e 4
MP&L LICENSING ACTIVITIES - FORECAST FOR NEXT 3 MONTHS S
J10 MISC 86061201 - 6
MP&LNUCLEARLICENSENS& SAFETY DATE: 06/12/86 ACT10N TRACIlNG MANAGEMENT SYSTEM FORECAST MPEL LICENSING ACTIVITIES PAGE: 1 SCHEDULED DATE NEC REQUEST DATE MF&L ID NUM RESPONSE MP&L CORRES. NUM T0FIC 0F SUBMITTAL DESCRIFTION NEEDED TAC NUMBER 06/13/Se 06/03/86 UFSAR NRC ACTION PREFARE AECM DOCUMENTING JGC DISCUSSI6s WITH LLI ON ID 60958 MTO-86/0167 PREFARING 50.59 TO RESOLVE II.I.I.10 CONCERN ON OPERAEILITY TESTING.
06/13/86 06/03/86 UFSAR NRC ACTION PREPARE AECM NOTIFYING REGION II 0F UFSAR STATUS.
ID 60959 MTO-86/0167 06/15/86 05/23/85 HYDR 96EN IGNITORS SER SUPPL. 3 ITEM 22.2 CONTAINS COMMITMENTS FOR HYDR 0 GEN ID$1291 PMI-85/5183 IGNITOR TESTING IN ADDITION TO TECH SPEC REQUIREMENT.
WRITE LETTER TO NRC TO CLARIFY.
06/19/86 03/21/86 LOSS OF POWER SUBMIT COMMENT ON PROPOSED SLACIOUT ROLE TO NRC.
ID 60669 51FR9829 06/20/06 05/01/86 RACEWAY SUPPORTS SUBMIT AECM IN RESPONSE TO NRC QUESTIONS RE: AFFENDIX R ID60915 MAEC-86/0137 RACEWAY SUFFORT EVALUATION.
06/20/86 06/10/86 ISI 10 YR PROG. NLS TO SUBMIT CLARIFICATION FOR RELIEF REQUEST AND ID 60981 MTO-86/171 JUSTIFICATION. THIS WILL CLARIFY THAT A SYSTEM LEAK CHECK WAS INTENT AND NOT A HYDRO AT EACH OUTAGE.
06/23/86 04/01/86 METER 0 LOGY SUBMIT COMMENT ON DRAFT REV 2 0F REG GUICE 1.23.
ID 608e6 RG 1.23 REV 2 06/26/06 // APP R EXCEPT SUSHIT FIRE AREA 25 EXCEPTANCE AND REVISIONS TO FIRE 2ONES ID 60923 AECH-86/0123 1A305 AND 1A211 TO NRC, 06/27/86 '06/10/86 ISI 10 VR. PROG. NFE TO PROVIDE TO NLS ADDITIONS TO THE 10 TR. ISI PROGRAM.
ID 60982 MT0-86/171 NLS TO SUEMIT THIS INFORMATION TO THE HRC.
06/30/86 YES 05/07/86 TECH SPEC CHG TRANSMIT THROUGH PSRC AND SRC RHR TO LIQUID RADWASTE ID 60978 PMI-86/0357 06/30/86 10/24/85 TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC AND SRC CHANGING SURVEILLANCE ID 60131 FMI-85/9449 REQUIREMENTS FOR DRYWELL AIRLOCK LEAK TEST AND SUEMIT TO NRC.
06/30/86 01/09/86 TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC & SRC TO REVISE TABLE ID 60173 PMI-86/0511 3.3.7.5-1 TO MAIE SPECIAL REFORTING REQUIREMENTS NOT APPLICABLE TO IN0FERABLE CHANNELS AND SUEMIT TO NRC.
MP&L NUCLEAR LICENSING & 5AFETY DATE: 06/12/$6 ACTION TRACXING MANAGEMENT SYSTEM FORECAST MP&L LICENSING ACTIVITIES PAGE: 2 SCHEDULED DATE NRC REQUESTDATE MP&L ID NUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUBMITTAL DESCRIPTI0N NEEDED TAC NUMBER 06/30/86 11/10/85 TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC & SRC ON OFERATING LICEhSE ID 60178 AECM-85/0218 CONDITION 2.C(33)g.ADSPRESSUREINDICATIONANDSUBMITTD NRC.
06/30/86 01/31/86 HYDROGEN CONTROL PREPARE AND SUBMIT A REVISED SCHEDULE FOR MEETING THE ID 60231 AECM-86/0009 HYDR 0 GEN RULE REQUIREMENTS.
06/30/86 // TECH SPEC CAHNGE PROCESS A TS CHANGE THRU PSRC AND SRC ON ADDRESSING ID 60334 ROUTINE IS CHG SECONDARY CONTAINMENT INTEGAITY WHILE MOVING FUEL.
07/01/86 03/15/85 SALEM ATWS PROVIDEPLANT-SPECIFICCOMPARIS0NTONEDC-30844(TECHSPEC ID 50004 MAEC-85/0088 SURV. INTERNALS)WITHIN90DAYSOFNRCISSUANCEOF EVALUATION.
07/01/86 04/30/85 N'fDR0 GEN CONTROL SUBMIT QUARTERLY STATUS REPORT FOR DEGRADED CORE ACCIDENT ID 50543 PMI-85/4313 HIDR 0 GEN CONTROL PROGRAM.
07/14/86 03/29/55 RELOADLICENSING SUBMIT CYCLE 2 RELOAD LICENSING AMENDMENT REQUEST TO NRC, ID 60245 PMI-85/3468 INCLUDING FULL CYCLE 2 ME0D.
07/14/86 04/10/86 6'ADIO ASSAY SUBMITANALYSISOFH-3,Sr89/90ANDFeINNRCSAMPLE.
ID 60806 MAEC-86/00?6 07/15/86 YES 05/13/86 TECH SPEL CHG TRANSMIT THROUGH PSRC AND SRC FUEL PERFORMANCE - IODINE ID 60980 PMI-86/3461 SAMPLING.
07/18/56 12/19/85 TECH SPEC CHG PROCESS A TS CHANGE THRU PSRC AND SRC 10 REVISE TABLE ID 60116 PMI-85/Ill39 3.8.4.2-1 FOR INCLUSION OF M0V QlE51-F095 THERMAL OVERLOAD PROTECTION AND SUBMIT TO NRC.
07/18/86 05/30/86 SR0s PROVIDE COMMENTS ON ADVANCED RULE MAKING CONCERNING DEGREES ID 60960 51FR19561 FOR SR0s.
07/23/86 02/26/86 UFSAR NRC ACTION PREPARE AND SUBMIT UFSAR
- FACILITY CHANGE' l.! STING TO NRC.
ID 604?2 NLSAP 2.16 07/28/86 // RELOADLICENSING RELOAD LICENSING MEETING WITH NRC TO DISCUSS CYCLE 2 ID 60296 X AMENDMENT REQUEST.
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MP&L NUCLEAR LICENSlNG & SATETY DATE: 06/12/86 ACTION TRACKING MANAGEMENT SYSTEM FORECAST MP&L LICENSING ACTIVITIES PAGE: 3 SCHEDULED DATE NRC REQUEST DATE .
MPLL ID NUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUIMITTAL DESCRIPTION NEEDED TAC NUM!ER 07/31/86 YES 08/31/85 DCRDR SUMM REPORT St,BMIT DCRDR
SUMMARY
REPORT FOR NRC REVIEW IAW THE DCRDR ID 51313 ERC PROJ. PLAN PROGRAM PLAN AND THE ERC PROJECT PLAN 5.1.12.
07/31/86 YES // TECH SPEC CHG PROCESSATECHSPECCHANGEREVISINGTHEREQUIREMENTST5 ID60979 J.E. CROSS RQST SHUTDOWN IF A SRV IS STUCI OPEN FOR GREATER THAN 2 MINUTES T.S. 3.4.2.1 08/01/86 06/07/83 BULLETIN RESPONSE SUBMITREPORTCONCERNINGFIRSTREFUELINGOUTAGED/GCHECI ID S0170 AECM-83/0308 VALVE INTGRITY INSPECTION 08/30/86 04/30/85 HYDROGEN CONTROL REQUEST NRC APPROVAL ON ADEQUACY OF INSTALLED GGNS HYDROGEN ID S0549 PMI-85/4313 CONTROLSYSTEM.(PRIORTOSTARTUPRF01).
08/30/86 12/30/85 HYDROGEN CONTROL SUBMIT 2ND QUARTER REPORT FOR 1986 REGARDING HYDR 0 GEN ID 60314 NPF-29 CONTROL ACTIVITIES.
09/01/86 09/20/82 PART 21 REPORT SUBMIT FINAL UNIT 1 10CFR21 REPORT CONCERNING STANDBY ID S0565 AECM-82/403 SERVICE WATER 'A' LOOP SYSTEM FLOW.
h
//
Enclosure 3 Schedule of Licensing Actions needed prior to and during the first refueling outage (RF01) prepared by NRC staff for the Licensing Actions meeting on June 13, 1986
- 1. Licensing Actions needed prior to RF01 Sprinkler System (2/28/86 Submittal)
Noticed 5/21/86C Issue 6/30/86T SSW Loop A modifications (5/19/86 Submittal)
Noticed 6/18/86T Issue 7/31/86T SLO & ME0D Cycle I (5/02/86 Submittal)
Noticed 7/02/86T Issue 8/15/86T High density Spent Fuel Racks (5/6/85 Submittal)
Notice Environmental Assessment 6/30/86T Renoticed 7/02/86T Issue 8/02/86T
- 2. Licensing Actions needed during RF01 Response Issue Item Date Date Vacuum Breaker Pos Ind. 07/02/86T 09/02/86T SDV Vent & Drain Valves 07/02/86T 09/02/86T Interlocks for ECCS Valves 05/30/86C 07/15/86T
- RSP Transfer Switch 04/14/86C 07/15/86T
- Strong Motion Accelerometer 03/21/86C 07/15/86T "DG Protective Trips 05/19/86C 07/15/86T
- Reload Application 07/14/86T 09/30/86T Hydrogen Control Schedule 01/31/86C 07/30/86T MSIV-LCS Instrument Lines 05/30/86C 08/30/86T Feedwater Fluid Head 05/12/86C 08/15/86T
- 3. Other Licensing Actions Target Date Inservice Inspection Program 08/15/86 Inservice Test Program 01/31/87 Fire Hazards Analysis 09/30/86 RG 1.97 Instruments 08/30/86 Salem ATWS Items 12/31/86 Humphrey Concerns 10/30/86 Diesel Generator Reliability (GL 84-15) 09/30/86 SPDS 07/15/86
- ASME Code Case N-411 11/30/86
- Drywell Air Lock Surveillance 12/31/86 Unit Organization Changes 08/31/86
- STA Staffing 07/31/86 I.G.1 Special Tests 07/31/86 RCIC Steam Flow High Setpoint 07/31/86
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. . . Enclosure 4 UCNR STATUS June 13, 1986 I. SCREENING PHASE
- 1) Status (complete) o 358 CNs reviewed o 188 CNs (554 items) required 50.59 evaluation action or comitment deletion resolution !
o 47 potential commitment deletions identified
- 2) Supporting Documents ;
o NLSAP 2.16 o UCNR Screening Log o Marked CNs o Priority review of CNs o QA audit II. EVALUATION PHASE
- 1) Status (ongoing) o 239 50.59 evaluations prepared o 24 UFSAR revisions /CRs required o 3 commitments still open a 171 to PSRC for approval o 68 in management review
J11 MISC 86061302 - I h
. a III. O&R REVIEW PHASE
- 1) Status (ongoing) o 1000 (est.) comitments identified o 130 (est.) comitments required for CR
- 2) Supporting' Documents o NLSAP 2.17 o Commitment Review Log o Example comitments IV. Programatic Improvements
- 1) NLSAP 2.2 revision (in progress) .
- 2) NPD Change Request Procedure (to be developed)
- 3) NLSAP 1.13 revision (in progress)
- s. -
II.B.5 The licensee advised that relief may be needed regarding operator license exam applications because of revised Form 398 which became effective April 1,1986. This form does not allow training to be counted in meeting the experience requirement. The licensee is in touch with Region II staff regarding this matter.
The NRC staff questioned the referencing of the updated FSAR in licensing documents by the acronym FSAR because that is the acronym used for the original FSAR. The updated FSAR is substantially different in organization from the original FSAR because of the incorporation of answers to questions and letters of commitments into the updated version and because ir, some cases description of equipment is updated. The reason the licensee prefers use of the same acronym is so that a multitude of plant procedures and evaluations that reference the FSAR will not have to be reviewed and modified to use a new designation such as UFSAP., Subsequent to the meeting, the NRC staff discussed the matter internally and concluded that the updated FSAR should continue to '
be referenced by the acronym FSAR. Absent a more specific reference or date, such a reference will be taken to mean the latest version of the updated FSAR.
Odginsi signed by L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION Docket File; NRC PDR LPDR PD#4 Rdg.
WButler LKintner M0'Brien Young, 0GC Edordan BGrimes ACRS(10)
( NRC Participants PD#4/PM PD#4/D LKintner:lb (WButler 07/2 y86 07/gj/86
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