ML18040A025

Summary of 930422 Meeting W/Util in Rockville,Md to Discuss Status of Design Basis Reconstitution Program & Current Licensing Issues for Both Units.List of Attendees & Handouts Encl

ML18040A025
Person / Time
Site:	Nine Mile Point
Issue date:	04/28/1993
From:	Menning J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9305030057
Download: ML18040A025 (64)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 1993 Docket Nos.

50-220 and 50-410 LICENSEE:

Niagara Mohawk Power Corporation FACILITY:

Nine Mile Point Nuclear Station Unit Nos.

1 and 2

SUMMARY

OF APRIL 22,

1993, MEETING TO DISCUSS STATUS OF THE DESIGN BASIS RECONSTITUTION PROGRAM FOR NINE MILE POINT NUCLEAR STATION UNIT 1 AND CURRENT LICENSING ISSUES FOR NINE MILE POINT NUCLEAR STATION, UNIT NOS.

1 AND 2 A meeting was held in the NRC One White Flint North Office in Rockville, Maryland, with Niagara Hohawk Power Corporation (NMPC) and NRC staff representatives to discuss the status of the Design Basis Reconstitution (DBR) program for Nine Mile Point Unit 1

and current licensing issues for Nine Mile Point Units 1

and 2.

The licensee had requested this meeting.

Enclosure 1 is a list of meeting attendees.

Enclosure 2 is a copy of the handout material provided by NHPC.

Although not an agenda item, the attendees initially discussed the function of the rupture discs associated with the newly installed Unit 1 hardened vent.

These discs had actuated at approximately 7 psig during the recent Unit 1

startup as primary containment inerting was in progress.

The staff questioned why the rupture discs actuated at a pressure significantly below the design pressure of the containment.

The NMPC representatives indicated that the discs are intended to protect the nonpressure qualified ductwork and fan rather than the containment.

The specifications for the discs require that they actuate at no greater than 10 psig.

NHPC also indicated that a root cause analysis is being performed on the disc actuation event.

The NRC staff stated that they woul'd follow"up" on the matter after NMPC has completed the root cause analysis.

NMPC agreed to provide the staff additional information regarding the operatton of the discs.

NMPC then provided an-update on the status of the Unit 1

DBR program.

This program iIivolves the development of "System Design Basis Documents" (SDBDs) for importaat 'p'lant'ysteIIIs; the development of "Topical Design Criteria Documents" (TDCDs); the verification of as-built configurations via plant walkdowns; and the reconstitution, evaluation, and reconciliation of design basis documents.

NMPC had previously planned to prepare 38 SDBDs.

However, after reassessing the importance to safety of these 38 systems based on Probabilistic Risk Assessment

insights, NHPC has decided to prepare SDBDs for 25 systems and expects to complete this work by the end of 1994.

NHPC had previously planned to complete 30 TDCDs.

However, NHPC has reassessed the scope of this effort and now plans to prepare 22 TDCDs., This work is scheduled to be completed by the end of 1993.

9305030057 930028 FDR ADOCK 05000220 FDR

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April 28, 1993 NHPC subsequently described the process by which discrepancies identified as a

result of DBR activities are resolved.

All such discrepancies are reviewed by a senior'engineering review team (SERT).

The SERT has scheduled meetings;

however, emergency sessions may be called if required.

Deficiency/Event Reports (DERs) are only initiated if a discrepancy could result in a reportable or inoperable condition or creates a personnel safety hazard.

Other discrepancies are processed by changing configuration documents or through work orders, so as not to overburden the DER system.

DERs are processed in accordance with established procedures, which require operability and reportability reviews by shift operations personnel.

The meeting attendees then discussed the current and anticipated licensing issues for Unit 1.

NHPC identified 10 planned license amendment requests that they expect to submit to the NRC by June 30, 1993.

Although not listed in the enclosed handout material, NHPC stated that they expect to submit an amendment request by early Hay 1993 that essentially represents an administrative reissuance of the Unit 1 Technical Specifications.

This submittal will not include any substantive changes to the technical specifications, only administrative type changes, e.g., deletion of out-of-date references, correction of typographical

errors, etc.

The current and anticipated licensing issues for Unit 2 were the last items to be discussed.

NHPC identified four license amendment requests that will be submitted to the NRC in the very near term and four other amendment requests that are scheduled to be submitted by June 30, 1993.

Enclosures:

1.

List of Attendees 2.

Licensee Handout Haterial John E. Henning, P

ject Hanager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures:

See next page

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4

Niagara Mohawk Power Cor poration CC:

Nine Nile Point Nuclear Station Unit Nos.

1 and 2

\\

Hark J. Wetterhahn, Esquire Winston 5 Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382

Oswego, New York 13126 Hr. Neil S.

Cams Vice President Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126

Lycoming, New York 13093 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendal'e Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor

Albany, New York 12223 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212 Hr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Mr. Hartin J.

McCormick Jr.

Plant Manager, Unit 2

~

Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Paul D.

Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza

Albany, New York 12223 Hr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, New York 12223 Hr. Richard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue

Albany, New York 12210

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ENCLOSURE 1

A ril 22 1993 Status of the Desi n Basis Reconstitution DBR Pro ram for Nine Mile Point Unit 1

and Current Licensin Issues for Nine Mile Point Units 1

and 2-ATTENDANCE LIST Name Jose Calvo Robert Capra Donald Brinkman John Henning Richard Lobel Eric Leeds J.

D. Wilcox S.

K. Mitra James Houghton Dave Wigginton Carl Terry David Greene W. David Baker Denise Wolniak Bill Yeager Lee Klosowski Rob Oleck Position Assistant Director Project Director Seni,or Project Manager Project Manager Section Chief Section Chief Team Leader Electrical Engineer Plant Systems Engineer Lead. Project Hanager-Generic DBR Vice President Nuclear Engineering Licensing Hanager

.Program Director Supervisor - Licensing Support Manager Nuclear Engineering for Unit General Supervisor-Nuclear Design Program Manager - DBR Niagara 1

Niagara Mohawk Mohawk Niagara Mohawk Or anization NRC/NRR/ADR1 NRC/NRR/PD I-1

, >,~ NRC/NR8/.PDI-I NRC/NRR/PD I-1 NRC/NRR/SCSB NRC/NRR/PDLR NRC/NRR/RSIB NRC/NRR/EELB AEOD/DSP/TPAB NRC/NRR/PDIV-1 Niagara Mohawk Niagara Mohawk

". Niagara Mohawk Niagara Mohawk

V MAGAR U MOHAWK ENCLOSURE 2 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT DESIGN BASIS RECONSTITUTION/CONFIGURATION MANAGEMENT PRESENTATION TO NRC

)

APRIL 22, 1993

I

YNIAGAR U MOHAWK E

EN ATI INE INTRODUCTION C.

D. TERRY DESIGN BASIS RECONSTITUTION STATUS UPDATE R.

F. OLECK DISCREPANCY RESOLUTION EXAMPLES '

L A. KLOSOWSKI CLOSING REMARKS C.

D. TERRY

W MAGAR U MOHAW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT, UNIT 1 DESIGN BASIS RECONSTITUTION PROGRAM STATUS UPDATE PRESENTED BY R.

F.

OLECK, JR.

V NIAGAR U MOHAW NINE MILE POINT UNIT ¹1 DESIGN BASIS RECONSTITUTION..STATUS UPDATE

~

MARCH 1991 LAST NRC PRESENTATION

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SCHEDULE/SCOPE CHANGES

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ACCOMPLISHMENTS TO-DATE

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OPEN ITEMS

J

V NIAGAR U MOHAWK DE I

B E

N TIT TI N

NFI RATI N NA EME R

R IVI PROGRAM APPROACH COORDINATE ACTIVITIES OF ALL UNIT 1

NMPC DESIGN BASIS RECONSTITUTION AND CONFIGURATION MANAGEMENT ACTIVITIES (I.f.,

INTEGRATE)

DEVELOP "SYSTEM DESIGN BASIS DOCUMENTS" FOR EACH MAJOR SYSTEM OF THE PLANT DEVELOP "TOPICAL DESIGN CRITERIA DOCUMENTS" FOR THE PLANT VERIFY THE AS-BUILT CONFIGURATION OF THE PLANT - WALKDOWNS RECONSTITUTE, EVALUATE AND RECONCILE DESIGN BASIS DOCUMENTS

T MAGAR 4 MDHAWK E

OE I

N BA I

D MENT TABLE OF CONTENTS, 1.0 SYSTEM OVERVIEW System Functions 1.2 General Design Description 1-2 2.0 SYSTEM REQUIREMENTS 2.1 System Functional Requirements 2.2 Performance Requirements 2.3 System Configuration

& Interface Req.

2.4" Surveillance Testing

& Inservlce Inspection Requirements 2.6 Instrumentation and Control Requirements 2.6 Electric-Requirements 2.7 Structural Requirements 2.8 Quality Assurance Requirements 2.9 Codes and-Standards 2.10 Environmental Quallflcatlon Requirements 2.11 Fire Protection Requirements 2.12 AddNonal Requirements 2-1 2-2 2-3 2-5 2-7 2-9 2-9 2-10

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V NtAGAR 4 MOHAWK EM DE I

N BA I

D MENT

\\

TABLE OF CONTENTS (CONTINUED) 3..0 SYSTEM DESIGN DESCRIPTION 3.1 Detailed Description 3.2 Performance Characteristics 3.3 Arrangement 3.4 Component Design 3.5 lnstrumentatlon

& Control 3-15 3-16 3.6 Electrical Systems and Power Supplies.

3.7 Structural Design 3.8 Special Material and System Chemistry Considerations 3.9 System Boundaries and Interfaces 3.9.1 System Functional Interfaces r

3.9N Physical Boundaries Interfaces 3.10 Environmental Qualification 3.11 Rro Protection 3-25 3-26 3-28 3-29 3-29 3-31 3-31 3-32

V MAGAR lfMQHAwK TE DE I

N BA I

D MENT TABLE OF CONTENTS (CONTINUED) 4.0 SYSTEM OPERATION 4.1 Limiting Conditions for Operation 4.2 Testing and Surveillance 4.3 Operating Notes and Precautions 4-1 5.0 SYSTEM MAINTENANCE CONSIDERATIONS 5.1 Maintenance Approach 5.2 Preventive/Predictive Maintenance 5.3 Inservlce Inspection and Testing 6.0 SYSTEM REGULATORY CONSIDERATIONS 6.1 NRC Regulations 6N Regulatory Guides 6.3 Other Licensing Commitments 7.0 SYSTEM MODIFICATION

SUMMARY

7-1

8.0 REFERENCES

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2 3

4 MEC SSFI+IPE 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 2

3 4

1 3

4 2

3 4

5 6

3 4

5 6

Serv Wtr RBCLC TBCLC EDG DC125V MEC MEC MEC ELE ELE GL 89-1 3+IPE GL 89-1 3+IPE GL 89-1 3+IPE EDSFI+IPE IPE+EDSFI+SBO

<Reconstttuson

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8 9

10 11 12 13 14 15 16 17 18 19 7

8 9

10 11 12 13 14 15 16 17 19 18 2l 22 23 SECONDYR Cont Spray Primary Cant Emerg Cond ADS instr Air AC4160V AC120V THiRD YR Contain(Syste SD Cool RPS CRD/ATWS Neutr Mon Feedwtr/HPCI FOURTH YR RPV Ins.

Condens Tnsf RB HVAC Main Steam Remote Shtd DC24V FlFTH YR MEC MEC MEC M/I&

MEC ELE ELE MEC MEC 1&C M/I&

l&C MEC I&C MEC MEC MEC l&C ELE IPE+Lake temp IPE+ Torus Corro IPE+Fuels+MOV IPE+FUELS GL 88-1 4 IPE+ EDSFI GL91 ~.IPE,RG1.

IPE IPE+Safety IPE+ Safety IPE+ Safety Fuels+Reliability IPE+ Reliability+C IPE+RG 1.97 IPE+ Reliability IPE+ Safety Fuels+ ReNablNty Safety+ RG1.97 Safety+RG1.97 1

2 3

4 1

2 3

4 1

2 3

4 2

3 4

1 2

3 4

2 3

4 1

2 3

4 1

3 4

3 4

1&C MEC MEC MEC MEC MEC i&C i&C MEC i&C MEC MEC M/I&

Proc Comp Uq. Poison Recirc RWCU Oif Gas CR HVAC Proc Rad Mo ARM RV internal SPOS Circ Wtr Spent Fuel Past Acc Sam IPE+ Safety Safety Safety Safety Safety

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Optional Systems I

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NOTES

1. Ailsystems important to safety ts1t covered by the scope of systems Meted.

0

, January. 13, 1993, INITIALYEAR TYPE PR RESPO 1 991 OGRAM YEARS 1 992 1

2 3

4 3

4 1

2 3

4 1

2 3

4 1

2 1

DCD-1 01 2

DCD.1 09 3

DCD-1 1 6 4

OCD-1 20 6

OCD-208 8

DCD-301 7

DCD-306 8

DCD-31 1 9

DCD-31 7 10 DCO~

Pipe Supports Primary Containment Seismic Analysis External Events Piping Design &Analys DC Electrical Dlstrlbutlo Electric Cable Design AC Load Electrical Isolation VitalArea Access SECOND YEAR Struc Str/M Struc Struc Mech Elec Elec Elec Elec HP MPR MPR IMPELL IMPELL IMPELL IMPELL GILBER IMPELL NMPC 2

3 4

1 2

3 4

le slip Schedu 3

4 Schedu le slip 4

1 2

11 DCD-1 02 12 DCD-1 10 13 DCD-1 14 1 4 DCD-204 1 6 DCD-206 16 DCD-31 8 17 DCD-31 9 18 DCD~

19 DCD-117 20 DCD-1 1 9 2l DCD-21 3 22 DCD-306 23 OCD~

Seismic Classmcatlon Reinforced Concrete Steel Structures Hydraulic Design &An Heat Transfer Design l&CSelpolnt Design Fusing Design Accident Loadln THIRD YEAR Fire Protection Cable Tray &Duct Sup HVACGeneral Design Nuclear &Process Instr Source Term Struc Struc Struc Mech Mech Elec Elec Fuels Struc Struc Mech Elec Nuc MPR IMPELL IMPELL IMPELL IMPELL GILBER GILBER SU Open Opne OPEN GILBER SYMME 1

2 3

4 1

2 3

4 4

1 2

FOURTH YEAR

( Optional 24 DCD-1 11 26 DCD-1 1 8 26 DCD-202 27 DCD-203 28 DCD-303 29 DCD-304 30 DCD~7 Masonry Block Structur Component Supports Component Fu1ctlonal Pipe Break Loads Electric MotorOcelgn Component ~ot Safety ClassNc~ns OPEN OPEN Open Open OPEN OPEN OPEN FIFTH YEAR (Optional)

OPEN OPEN OPEN OPEN OPEN

V NIAGAR V MOHAWK NINE MILE POINT UNIT g1 DESIGN BASIS RECONSTITUTION STATUS UPDATE ACCOMPLISHMENTS:

13 SYSTEM DESIGN BASIS DOCUMENTS WALKDOWNS AND AS-BUILT DRAWINGS 17 TOPICAL DESIGN CRITERIA DOCUMENTS COMPLETE 12/92 COMPLETE 12/92

~

MAJOR RECONSTITUTION ITEMS:

DIESEL GENERATOR TRANSIENT ANALYSIS CONTAINMENT / SPRAY ANALYSIS SERVICE WATER THERMAL / HYDRAULICS INSTRUMENT AIR LOAD LIST Sc WALKDOWNS CABLE & RACEWAY DATABASE UPDATED PIPE STRESS

- ISI SYSTEMS COMPLETE AS OF 12/92 12/92 4/93 4/93

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12/93 12/93

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CONFIGURATION MANAGEMENT UPGRADE:

12/94 MASTER EQUIPMENT.LIST FOR 13 SYSTEMS

=

VERIFIED OTHER COMPONENTS

= -

. DRAWING,

-TAKEOFF

0

Y MAGAR U MOHAW DBR OPEN ITEM:

Any walkdown observation, not ln accordance with existing configuration information, or lack/conflict of design basis Information discovered ln preparation of a system or topical design basis document.

~

FOR 13 SYSTEMS TO-DATE:

Walkdown Observations (Open Items)

=

1,449 System Design Basis (Open Items)

Topical Design Basis (Open Items)

= 921 141 TOTAL OPEN ITEMS 2)611

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MOST OF THESE ARE'rawing and other document Inconsistencies/corrections Mlsslng calculations

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.D,,>>

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EPN (Component ID) inconsistencies or none assigned Interface

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MOST WILL BE CLOSED BY 12/94

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DER'S (DEVIATION EVENT REPORT)

ARE WRITTEN FOR SAFETY SIGNIFICATN ISSUES 34 DER's written to<ate

Y MAGAR V MOHAWK DISCREPANCY RESOLUTION PROCESS AND

=" " EXAMP-LES BY:

L. A. KLOSOWSKI I

0 Pil'A

V MAGAR U MOHAW F

P TENTIAL DI REPAN Y IDENTIFI ATI DEVELOPMENT OF DESIGN BASIS DOCUMENTS RECONCILIATION OF DATABASES

~

I

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IN-PLANT AS-BUILT VERIFICATION WALKDOWNS

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h

Y MAGAR U MOHAW DB Dl REPAN Y RE L Tl N

SERT DISCIPLINE EXPERTS REVIEW ALL IDENTIFIED DISCREPANCIES TSD OR NTSD (TECHNICALLY OR NON-TECHNICALLY.

SIGNIFICANT DISCREPANCY)

OER REQUIRED (DEFICIENCY EVALUATION REPORT)

EMERGENCY SERT (SENIOR ENGINEERING REVIEW TEAM)

REGULARLY SCHEDULED SERT

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DER'S INITIATED ONLY WHEN DISCREPANCY COULD RESULT IN REPORTABLE OR INOPERABLE CONDITION OR CREATES A PERSONNEL SAFETY HAZARD

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OTHER DISCREPANCIES PROCESSED BY CHANGING CONFIGURATION DOCUMENTS OR WORK ORDER (DON' OVERBURDEN DER SYSTEM)

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DER'S PROCESSED IN ACCORDANCE WITH DIVISION PROCEDURES REPORTABILITY AND OPERABIUTY REVIEWS PERFORMED BY SHIFT OPERATIONS

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SERT PROVIDES RECOMMENDED OPERABILITY DETERMINATION

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OPERABILITY DETERMINATION CONSISTENT WITH GL 91-18

14 1a

VNIAGAR U MOHAWK I A I

E E

IE ED gllET L

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DER 1-91%806 ELECTRICAL FUSING NOT CONTROLI ED FUSE REPLACEMENTS NOT DONE IN ACCORDANCE WITH DESIGN OR LACK OF DESIGN DIRECTION FOR APPROPRIATE FUSE REPLACEMENT

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OPERABILITY EACH DISCREPANCY EVALUATED ON CASE BASIS TO VERIFY SYSTEM OPERABILITY OVERALL PLANT OPERABILITY DEMONSTRATED BY SUCCESSFUL OPERATION AND SURVEILLANCE TESTING CORRECTNE ACTIONS ELECTRICAL SPECIFICATION E-152.ISSUED TO PROVIDE CONTROL OF FUSE REQUIREMENTS AND APPROPRIATE REPLACEMENTS DISCREPANCIES RESOLVED BY UPDATING FUSE SPECIFICATION OR WORK ORDER TO REPLACE FUSE IN FIELD

lg III

TNIAGAR 4 MOHAWK EXAMPLE F

NIFI AN I

E REVIEWED BY ERT (CONT'D)

E H

DER 1-92<183 TEMPERATURE ELEMENTS LOCATED INCORRECTLY C

TEMPERATURE ELEMENTS FOR PROCESS COMPUTER POINTS LOCATED ON RBCLC INLET TO SDC PUMP COOLERS INSTEAD OF OUTLET OF PUMP COOLERS

~

OPERABILITY TEMPERATURE SWITCHES FOR ALARMS ARE APPROPRIATELY LOCATED ON OUTLET OF PUMP COOLERS TEMPERATURE ELEMENTS FOR PROCESS COMPUTER POINTS DO NOT PERFORM SAFETY RELATED FUNCTION CORRECTIVE ACTIONS RELOCATE TEMPERATURE ELEMENTS TO OUTLET OF SDC PUMP COOLERS

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1 ~

~

V MAGAR 4 MOHAW I NIFI A T REVIEWED ERT (CONT'D)

~

DER 1-93-0602 INADEQUATE PIPE SUPPORTS ON EMERGENCY SERVICE WATER LINES SEVERAL PIPE SUPPORTS NOT INSTALLED PER DESIGN, LACK OF SUFFICIENT SUPPORTS PIPE SUPPORT STRESSES EXCEED ORIGINAL CODE OF CONSTRUCTION

~

OPERABILITY PIPE SUPPORTS ANALYZED TO MEET CRITERIA OF ASME SECTION III APPENDIX F SOME PLASTIC DEFORMATION OF PIPE SUPPORTS WOULD OCCUR PIPING CONTINUES TO MEET ORIGINAL CODE OF CONSTRUCTION ANSI B31.1 1955

~

CORRECTIVE ACTIONS MODIFY AND ADD SUPPORTS AS NECESSARY TO MEET DESIGN BASIS CODE ALLOWABLES FOR PIPE SUPPORTS

0

Y MAGAR U atomw N

L I

N

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THE DBR DISCREPANCY EVALUATION METHODOLOGY IS CONSISTENT WITH'UMARC DESIGN BASIS PROGRAM GUIDELINES NRC REQUIREMENTS AND EVALUATION GUIDANCE NMPC DIRECTIVES AND PROCEDURES

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THE DBR APPROACH IS FORMAUZED AND WELL DOCUMENTED

~

USING THE DBR APPROACH, APPROPRIATELY QUALIFIED PERSONNEL WILL PROMPTLY AND CONSISTENTLY IDENTIFY, EVALUATE AND CORRECT SIGNIFICANT DISCREPANCIES

~

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V MAGAR U MOHA

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NMPC WILL BE COMPLETING A SIGNIFICANT INITIATIVE TO RECOVER/RECONSTITUTE THE DESIGN BASIS OF NMP-1 BY THE END OF 1994 SIGNIFICANT RESOURCES HAVE BEEN BUDGETED THROUGH THE END OF 1994 NMPC WILL KEEP NRC APPRISED OF DEVELOPMENTS AND PROGRESS

~

SIGNIFICANT BENEFIT OBTAINED FROM INTEGRATION OF EFFORTS FROM EXISTING PROGRAMS

~

HELPFUL IN-HOUSE ENGINEERING TOOL/RESOURCE

AYI'ACHMENTA (Page 1 of 1) ent Requests Submitted and Awaiting NRC Approval NO.

ITFM TAC NO.

SUBMITTALDATE NEED DATE STATUS 1

SORC/SRAB Composition and T.S. 6.4.1 2

3D - Monicore 11/24/92 11/24/92 6/1/93 003409LLl

II

ATTACM4ENTB (Page 1 of 2)

NO. IM SUBMITTALSTO BE COMPLETED BY 6/31/93 STATUS/COMMENTS 1

Delete APRM Downscale 2

Revise Weekly CRD Exercising to Monthly 3

Revise Flow Comparator Quarterly Surveillance to Refuel 4

Removal of MSL Rad Monitor and Delete Table 3.6.2 Shutdown Requirements 5

Revise Rx Building Leakage Rate 6

Spent Fuel Storage Capacity 7

Liquid Poison Minimum Volume Limit 8

Revise Setpoints for Undervoltage Relays 9

Revise Bases for HPCI Surveillance/Delete HPCI 10 Redundant Diesel Generator Testing 11 Diesel Loading Bases X

X X

X X

No amendment yet identified; George Inch working In engineering; scheduled for second quarterly test Drafting Review committed to NRC in LER; meeting pending Drafted; needed for 1996-97 Outage Drafted; awaiting'esolution from Engineering. on five loads Drafting

L

A1TACHMRNTB (Page 2 of 2)

NO.

H'EM 12 Add 7-day LCO for UPS's 162A & B and 172A & B 13 Add 7-day LCO for SC 161A & B and 171A & B SUBMITTALSTO BE COMPLETED BY 6/31/93 STATUS/COMMENTS 14 Remove Plant Manager Approval of Proaxiures 15 Revise STA/SSS T.S. Requirements 16 STA/SSS Normal Working Hours (8-12 hr. Shift); ASSS to Control Room Supervisor)/Reactor Analyst Change 17 Eliminate Supervisor Operations Position 18 Revise SRV Pressures to Reference COLR 19 Delete Hot Shutdown Requirements for Hydrostatic Testing Above 200'F 20 Remove Liquid Poison in Refuel X

X X

Awaiting U2; SRAB reviewed final proofing Drafting; to be included in ¹15 To be included in ¹15 Drafted; next outage 003409LL3

4

NMP2 ATFACERVH<NTA (Page 1 of 2)

NO.

ITFM TAC NO.

SUBMITI'ALDATE NEED DATE STATUS 1

SORC/SRAB Composition 2

Improved TS Topical Reporfs 11/24/92 12/7/92 3/4/93 6/1/93 Not specified Under NRC review; expecting approval 6/93 NRC shooting for 3/93 approval 3

GL 88-01, Leak Detection 4

Control Rod Withdrawal During Modes 3/4 5

Increased Core Flow/GEXL 12/30/92 2/12/93 2/27/93 Not specified Not specified Outage related 7/1/93 6

Revise 24-hour DG Test 7

SAFER-GESTAR 8

Delete CRD Accumulator Check Valve Test 9

Delete SLC Mode 5 Requirements 3/30/93 3/22/93 4/7/93 4/7/93 9/1/93 10/15/93 9/1/93 9/1/93 Outage related Outage related Outage related Outage related 003]90LL1

A1TACHMENTA (Page 2 of 2)

NO.

ITI<M 1

Hydro Test Above 200'F in Mode 4 2

Remove Plant Ma>ager Approval of Procedures AllowFuel Movements with one SGTS running/SGTS Action Statement 4

SORC Responsibilities T.S. 6.5.1.7.a TAC NO.

SUBMFITALDATE NEED DATE 9/1/93 7/1/93 9/1/93 7/1/93 STATUS Desired for Outage Desired for Outage 003 190LL1

NO.

ITEM A1TACHMENTB (Page 1 of I)

-Amendment Requests Planned but not Submitted to NRC SUBMITTALSTO BE COMPLETED BY 6/30/93 STATUS/COMMENTS 1

Power Uprate 2

Testing of Redundant EDG 3

Delete APRM Rod Blocks/ELLA 4

TSV Testing Weekly to Monthly 5

Delete Response Time Testing 6

Increased Allowable MSIV Leakage 7

Resilient Seal IV Allowable Leakage 8

Shift Work; ASSS Title Change 9

Battery Charger Footnotes 10 Removal of MSL Rad Monitor 11 H,Q Accident Monitoring X

X X

X SRAB approved SORC approved SORC approved BWROG Report due 3/93; willpursue deleting entire requirement BWROG funded; topical with NRC for approval Submit after fall outage Drafting 12 Revise Battery Electrolyte Temperature Mock EDSFI finding 003190LL2

L

April 28, 1993 NMPC subsequently described the process by which discrepancies identified as a

result of DBR activities are resolved.

All such discrepancies are reviewed by a senior engineering review team (SERT).

The SERT has scheduled

meetings, however, emergency sessions may be called if required.

Deficiency/Event Reports (DERs) are only initiated if a discrepancy could result in a reportable or inoperable condition or creates a personnel safety hazard.

Other discrepancies are processed by changing configuration documents or through work orders, so as not to overburden the DER system.

DERs are processed in accordance with established procedures, which require operability and reportability reviews by shift operations personnel.

The meeting attendees then discussed the current and anticipated licensing issues for Unit 1.

NMPC identified 10 planned license amendment requests that they expect to submit to the NRC by June 30, 1993.

Although not listed in the enclosed handout material, NHPC stated that they expect to submit an amendment request by early Hay 1993 that essentially represents an administrative reissuance of the Unit 1 Technical Specifications.

This submittal will not include any substantive changes to the technical specifications, only administrative type changes, e.g., deletion of out-of-date references, correction of typographical errors', etc.

The current and anticipated licensing issues for Unit 2 were the last items to be discussed.

NMPC identified four license amendment requests that will be submitted to the NRC in the very near term and four other 'amendment requests that are scheduled to be submitted by June 30, 1993.

I

Enclosures:

1.

List of Attendees 2.

Licensee Handout Material Original 'Signed By:

John E. Henning, Project Manager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/enclosures:

See next page DISTR I BUTION:

See attached sheet LA:PD I-1 PM: PD I-1 PH'DI-1 D: PDI-1 CVo an JMennin DBrinkman RACa ra 2 f/93 "1/Wl/93

/z1/93 g /2~ 93 OFFICIAL RECORD COPY FILENAME: NM50220.MTS

C A

DISTRIBUTION LIST FOR MEETING

SUMMARY

OF 4/22/93:

Enclosure 1&2 PDocket FileD NRC

& Local PDRs PDI-1 Reading J.

Henning D. Brinkman C. Cowgill Enclosure 1

T. Hurley/F. Hiraglia, 12/G/18 J.

Partlow, 12/G/18 S.

Varga C. Hiller, Acting AD R. A. Capra C,

Vogan OGC E. Jordan, HNBB 3701 R. Lobel, 17/G/21 E.

Leeds, 13/E/4 J. Wilcox, 9/A/1 S. Mitra, 7/E/4 J.

Houghton, HNBB 9112 D. Wigginton, 13/H/3 ACRS (10)

V. HcCree,

EDO, 17/G/21 30013.3

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