ML17054C079

Summary of 870424 Meeting W/Util in Bethesda,Md Re Status of Certain Licensing Issues & Opportunity to Meet New NRC Staff Due to Reorganization.Util & NRC Organization Charts & Agenda Encl

ML17054C079
Person / Time
Site:	Nine Mile Point
Issue date:	05/04/1987
From:	Neighbors J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8705070301
Download: ML17054C079 (78)

Text

May 4, 1987 Docket Nos.

50-220 and 50-410 LICENSEE:

FACILITY:

Niagara Mohawk Power Corporation Nine Mile Point Units I and 2

SUMMARY

OF MEETING HELD ON APRIL 24, 1987 WITH NIAGARA MOHAWK POWER CORPORATION (NMPC)

The meeting was held with NMPC in Bethesda,

Maryland, on April 24, 1987.

Enclosure 1 provides a list of attendees.

Enclosure 2 provides the agenda for the meeting.

The purpose of the meeting was to provide NMPC the opportunity to meet the staff members who will be responsible for the Nine Mile Point plants in the new organization and for NMPC to discuss the status of certain licensing issues on both units.

presented by each.

Enclosures 3 and 4 provide the organizations of NMPC and NRC hi h an, w

c were Other topics discussed briefly were the outstanding issues for h

1 t g

(

sure

2) and in Enclosures 5 and 6.

It is expected eac p an as at additional meetings will be held to discuss licensing issues in more detail.

The licensee stated that its goal is to improve its licensing process process.

Enclosures:

As stated cc:

See next page PDI-1 ~

PD CVogan DN bo s

4/yO/87 g'87 os h D. Neighbo

, Project Manager Project Directora I-I Division of Reactor Projects I/2 870507030 k 870504 PDR ADOCK 05000220 PDR

g'll v

l i

E K

Mr. C. V. Mangan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:

Mr. Troy B. Conner, Jr.,

Esq.

Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.W.

Washington, D.C.

20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New Yak 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.

Box 99

Lycoming, New York 13093 Mr. John W. Keib, Esq.

Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Mr. James Linville U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Don Hill Niagara Mohawk Power Corporation Suite 550 4520 East West Highway

Bethesda, Maryland 20814 Regional Administrator, Region I

U.S. Nuclear Regulatory Coomission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Paul D.

Eddy New York State Public Serice Corltrission Nine Mile Point Nuclear Station-Unit II P.O.

Box 63

Lycoming, New York 13093 Mr. Richard N. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue

Albany, New York 12210

A l

%f

ENCLOSURE 1

NRC S.

Varga B. Capra A. Thadani M. Haughey R. Benedict J.

Joyce W. Hodges B. Clayton J.

Johnson D. Neighbors LIST OF ATTENDEES AT APRIL 24, 1987 MEETING NIAGARA MOHAWK POWER CORPORATION W. Donlon T.

Lempges C.

Mangan S. Wilczek C. Terry A. Zallnich M. Wetterhahn

S V

ENCLOSURE 2

AGENDA FOR APRIL 24, 1987 MEETING BETWEEN NIAGARA MOHAWK AND NUCLEAR REGULATORY COMMISSION I.

INTRODUCTION -

H. J. Donlon-II.

ORGANIZATIONS Niagara Mohawk C.

D. Terry Nuclear Regulatory Commission III.

NIAGARA MOHAWK PHILOSOPHY S.

H. Hilczek, Jr.

work together NRR/Region Roles IV.

NINE MILE POINT UNIT 1

OUTSTANDING ISSUES S.

H. Hilczek, Jr.

Append) x J SAFER/GESTAR Reload ll CRD Stub Tubes Technical Specifications (Outstanding/Upcoming Requests)

V.

NINE MILE POINT UNIT 2 OUTSTANDING ISSUES C.

D. Terry/A. F. Eallnick/

S.

H. Hilczek, 3r.

Status of MSIV Change out Status of NRC Revie~ of MSIV Submittals Full Power Technical Specifications (Outstanding/Upcoming Requests)

Safety Evaluations for Modifications (50.59)

Input for Full Power License Westinghouse Fuel VI.

NIAGARA MOHAWK GOALS FOR 1987-88 S.

H. Hilczek, Jr.

3024G

V J

CEO J.

G.

HAEHL PRESIDENT N. J.

DONLON EXECUTIVE V.P.

J.

N.

ENDRIES SENIOR V.P.

SENIOR V.P.

SENIOR V.P.

J N

HAYNES J.

P.

HENNESSEY C. V. NANGAH SENIOR V.P.

N. P.

RANALLI SEHIOR V.P.

R. F.

TORREY SENIOR V.P.

GENERAL COUNSEL 8t SECRETARY J.

H.

TERRY VICE PRESIDENT J.

A.

PERRY (OA)

UI/

SENIOR VICE PRESIDENT C. V.

NAHGAN MANAGER NUCLEAR EHGINEERIKG & LICEHSIHG C.

D.

TERRY VICE PRESIDENT NUCLEAR GENERATION T.

E.

LENPGES

)

1 I

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MANAGER NUCLEAR ENGINEERING & LICENSIHG C.

D.

TERRY HAHAGER HUCLM CONPLI ANCE ANO VERIFICATIOH J. J.

BEBKO HANAGER NUCLEAR ENGINEERING G. J.

GRESOCK NAHAGER NUCLM TECHNOLOGY S.

W. WILCZEK, JR.

MANAGER NUCLEAR STAFF SERVICES A. P.

BALEHO

f

)

NANAGER NUCLEAR EHGINEERIHG 5 LICENSING NANAGER HUCLM ENGINEERING G. J.

GRESOCK NANAGER NUCLEAR DESIGN (UNIT 2)

K. D.

WARD NAHAGER NUCLEAR DESIGN (UNIT 1)

L. A.

KLOSOWSKI NAHAGER NUCLEAR PROJECTS E.

R.

KLEIH

y

MANAGER NUCLEAR ENGINEERING & LICENSING NANAGER-NUCLEAR TECHNOLOGY S.

W. WILCZEK, JR.

MANAGER FUELS AHD PLANT PRODUCTIVITY D. K.

GREENE NANAGER LICEHSIHG A. F. 2ALLHICK LICENSING SAFETY EVALUATIONS CORPORATE HEALTH PHYSICIST N. SPAGNDLElTI NANAGER CONSULTING R. J, PASTERHAK PROGRANS TECHNICAL SPECIALISTS

I n

ENCLOSURE 4 I.

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lp F

NRC REORGANIZATION 04/87 PURPOSE:

1.

Realign the NRC to reflect the change from construction and licensing reviews to assuring operational safety.

2.

Streamline functions and eliminate duplication of effort.

MAJOR CHANGES AFFECTING REACTORS Commission Level Offices New Office of Governmental and Public Affairs Harold Denton Congressional Affairs John Bradburne Public Affairs - Joe Fouchard

- International Programs Jim Shea State, Local 6 Indian Tribe Programs Carlton Kammerer 2.

Office of Investigations remains the same Ben Hayes Office of the EDO 1.

Deputy EDO - Jim Keppler / Jim Taylor Acting 2.

Deputy EDO for Regional Operations - Jim Taylor Regional Coordinator for each Region Region I Brent Clayton CRGR Function transferred to AEOD Office of Enforcement Jim Lieberman Office of Special Prospects

- Jim Keppler 3.

Office for Analysis and Evaluation of Operational Data Director Ed Jordan / Deputy Jack Heltemes

- Division of Operational Assessment Lee Spessazd Division of Safety Programs Tom Novak Office of Nuclear Material Safety and Safeguards Director Hugh Thompson / Deputy Bob Bernaro No longer responsible foz reactors except for transportation and out-of-reactor spent fuel storage Office of Nuclear Regulatory Research

- Director Eric Beckdord

- Deputy Director for Research Denny Ross Deputy Director for Generic Issues Themis Speis New Function: Resolution of Safety Issues Develop and Promulgate all Technical Regulations

6.

RegiOn I

- New Administrator Bill Russell

- Deputy Regional Administrator - Jim Allen

- Division of Reactor Prospects Still Bill Kane NMP 1&2 Branch Chief - Bob Gallo Section Chief Jon Johnson Division of Reactor Safety - Bill Johnston (Acting)

- Division of Radiation Safety

& Safeguazds Still Tim Martin 7.

Office of Nuclear Reactor Regulation

,(Reactor Responsibilities formerly performed by NRR, IE NMSS)

- Director Tom Murley

- Deputy Director Jim 'Sniezek Associate Director for Prospects Frank Miraglia Division of Reactor Prospects I/II Steve Vazga' Assistant Director Region I Bruce Boger

'Four Prospect Directorates)

Pzogqct Directorate I-1 Bob Capra

- NMP-1

- Bob Benedict / Sid Miner NMP-2 Mary Haughey/Don Neighbors Fitzpatrick Indian Point 2&3

- Calvert Cliffs 1&2 Division of Reactor Prospects III, IV, V & Special Prospects Dennis Cructhfleld Associate Director for Inspection

& Technical Assessment Rich Starostecki Division Engineering

& System Technology Larry Shao Division of Operational Events Assessment Ernie Rossi Division of Reactor Inspection

& Safeguards

- Jim Partlow Division of Radiation Protection

& Emergency Preparedness Frank Congel I

Division of Licensee Performance

& Quality Evaluation-Hub Miller (Acting)

1

DIVISION OF REACTOR PROi>ECTS, I/II Steven A. Varga, Director Bruce A. Boger, Assistant Director For Region I Reactors Robert A. Capra, Director Project Directorate I-l Project Manager for Nt1P-I Robert Benedict Project Manager for NMP-2 Mary Haughey/Don Neighbors

'l n

DIVISION OF ENGINEERING 8

SYSTFMS TECHNOLOGY L. Shao, Director J. Richardson, AD for En ineerin A. Thadani, AD for S stems C.

Y. Cheng, Materials Eng.

Branch Vacant, Instr.

& Control Branch L. Marsh, Mech.

Eng.

Branch F. Rosa, Elec.

Sys.

Branch

- G. Bagchi, Structural Eng.

Branch J. Craig, Plant Sys.

Branch M. W. Hodges; Reactor Sys.

Branch

ENCLOSURE 5

IV. NINE MILE POINT UNIT 1

OUTSTANDING ISSUES Appendix J SAFER/GESTR Reload 11 CRD Stubtubes Technical Specifications (Outstanding/Upcoming Requests)

APPENDIX J

NINE MILE POINT UNIT 1 LEAK RATE TEST PROGRAM I

ORIGINAL PROGRAM A.

BASIS APPENDIX A TO PROVISIONAL OPERATING DPR-17 (8/22/69)

APPENDIX A TO FULL TERM OPERATING LICENSE DPR-63 (12/26/74)

B.

TYPE C TESTING OF ISOLATION VALVES PRIMARY CONTAINMENT ISOLATION VALVES TABLE 3.3.4 MAIN STEAM ISOLATION VALVES REACTOR COOLANT SYSTEM ISOLATION VALVES TABLE 3.2.7 NOT INCLUDED

NINE MILE POINT UNIT j, LEAK RATE TEST PROGRAM I I APPENDIX J A.

NRC LETTER (8/7/75)

REQUESTED DETERMINATION IF CONDUCTING LEAKAGE TESTING IN FULL COMPLIANCE WITH APPENDIX J.

LEAKAGE TESTING PROGRAM MAY BE IN COMPLIANCE WITH TECHNICAL SPECIFICATIONS BUT NOT APPENDIX J.

B.

NNPC LETTER (0/77)

IDENTIFIED REACTOR COOLANT ISOLATION VALVES REQUIRING TYPE C TESTING.

PROVIDED EXEMPTION REQUESTS INCLUDING EMERGENCY CONDENSER.

AND SHUTDOWN COOLING.

C.

RESOLUTION OF OUTSTANDING ISSUE PENDING POTENTIAL MODIFICATIONS 1988 VS. 1990 REFUELING OUTAGE TIED TO IN-SERVICE TESTING PROGRAM OPEN ISSUES

E

SAFER/GESTR

SAFER,~GESTR LOCA Madel Pragra en lZOl~e um a n S

Best estimate approach to LOCA modelling Extends approved methodology to non jetpump plants Benefit:

Improved plant understanding Benefit:

Less restrictive MAPLHGR limits Needed for Reload 1

1 Core Design Application Methods SER issued by April, 1 987 NMP1 plant specific analysis submittal by July, 1 987 SER 'for above submittal by October, l 987 Reload 1

1 submittal by November, 1 987

RELOAD ll

NMP I

Relc 0

1 I

First use of GE8 an 'arrier fi =

=t NMP1 Peload batch size reduced due t=: nefits from. SAFER/GESTR LOCA I.::

I Program October 1987 NMP i specific L::A analysis SER November l 987 reload licensin=

. ech Spec submittal March 1 988 Reload/Tech Spec

==R issued March 1 988 Refueling begins May 1,988 Cycle 1 0 sta rtu p

t

CRD STUB TUBES

fr

304SS Weld 1 ~ '2 to 4.93 304SS SCab Tube (Furnace Sensi ised)

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304SS Cladding I

304SS CRD Sousing Alloy Carbon SCsel Vessel NMP-I CRD PENKTRATICN

'04 S (4eld

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'2"

<<oca I

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I 304SS Alloy Cazhon Steel vessel ROLLED AREA OF NMP-I CRD HOUSiNG

INSPECTION RESULTS FROM SPRING I 984 OUTAGE 51 47 43 39 35, 31 27 23 19 15 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50

'I Legend:

Inspected By CCTV Possible Evidence Of Prior Leak t Visible Leak Crack Visible By CCTV

0

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~ / pw 0

I I

304SS CM) Housing Alloy Carbon Steel vessel NMP-I CRD HOUSlNG ADDlTlCNALROLL=0 ARcA

l II

ROLL REPAIR

SUMMARY

Found Leaking (About 120 DPM)

Dur'ng Maintenance Outage.

Roll Repaired Week Of 8/4/86 (No Subsequent Leakage)

Evidence 0

Leak -e At 4 To 6

DPM During Recent Plant Resta""

51 47 43 39 35 31 27 23 19 15 c

07 03 02 06 10 14 18 22 26 30 Legend:

O Visually Inspected In 1984 From Inside Vease3.

O Roll Repaired 10 Housings Zn 1984 Roll Repaired 1 Housing In 1986 Rolled Two'Additional Rolls On 2 Housings Zn 1986 34 38 42 46 50 Rolled After Post Pepair-Hydrostatj.c Test Zn 1984 Rolled Two Additional Rolls After Post Repair Hydrostatic Test, Zn 1986

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PROTOTY?c MK'pq)g i)

$ c 'L A$ <'"Q) Y

r

UPPER HOUSING

([APE 316L STAINLEss STEEL)

INCONEL SHOP MELD CONSUMABLE'NSER.

/

CRO STUB-TUBE

( INCONEL 600)

INCONEL FIEi 9 INCONEL FIELD MELD LOWER HOUSING TYPE 316 N.G.

STAINLESS STEEL)

JAPANESE FIX

r I

SLEEVE ATTACHMENT WELOS CRACK DAMAGE STUS TUSE NEW STAINLESS STEEL SLEEVE STAINLESS STEEL WELD METAL i

SUILDUtON SOTTOM HEAD CLADDING hfVSOTTOM HEAD CRD HOUSINO GE Fix Stub Tube Sleeve Welded to Housing and Bottom Head

TECHNICAL SPECIFICATIONS

NINE HILE POINT UNIT 1

OUTSTANDING/UPCOHING TECHNICAL SPECIFICATION CHANGE REQUESTS SUBJECT Coastdown below 70'L power ISI/IST Update to Reference Next 120-Honth Interval Protective and Radioactive Effluent Instrumentation Site Organization Changes APRH Rod Block Line Himinum Reactor Vessel Temperature for Pressurization Radioactive Effluent Honitoring Program Rod Nor 'h Hinimizer Exercising of Reactor Coolant System Isolation Valves Deletion of Fire Protection Technical Specifications Definition of Refuel Greater than 212'F APRH Calibration Snubber-Type Definition Reactor Coolant System Leakage DATE SUBMITTED 8/21/86 1/23/86 2/17/87 2/20/87 3054G

ENCLOSURE 6

MSIV STATUS - APRIL 24 f987

'HYSICAL INSTALLATION IN FINAL STAGES VALVES/ACTUATORS INSTALLED AIR ASSIST, DRAIN LINES, LIFTIHG MONORAIL TO BE DONE EARLY NEXT WEEK

'EAK TESTING PROPER EQUIPNEHT/PROCEDURES IH PLACE IF MAINTENANCE NEEDED

'REND SHOWS MAY $ 6 READY FOR HEATUP BEIHG REVIEWED DAILY RESIDENT INSPECTORS REVIEWING PROGRESS ON A REGULAR BASIS

-- DAILY REPORTS TELECOPIED TO REGION AND HRR

'RESENT SCHEDULE DOES HOT ALLOW FOR 10 DAY REVIEW BY NRC FOLLOVIING VALVES DECLARED OPERABLE SURVEILLANCE TESTING INCLUDED AS PART OF PRE-OP REVIEWIHG ALTERNATE SCHEDULE LOGIC TO INCREASE TIME BETWEEH HEATUP AND VALVE OPERABILITY

MARCH APRIL 1987 MAY JUN 1012 TA %1520tt21tbtbto I

0 5

2

~

1112 Ib 12 Ie t1222 ~ tltb

'I 5

5 2

~ 11151511 Ib 21252b27202I 2

A 0

~

10 MOD 0201 ll)NfmuTv)uvT'At REMOVE

~ALL VALVES MOD f202 STRVCTVAL 4 RIGGING 1

L 2

I(

I l1) Llod package not closed tram field.

l2) Final hanger Inbtallatlon not Included.

MOD 203 t1)

Y-PATTERN ACTVATORS RETROflT MOD 820I Y-PATTERN INSTALLATION MOD 205 AIR SVPPLY SYSTEM MOD 200 I1)

RE-WORK EXISTING fACILITIE5 MOD 8210 11)

Y-PATTERN ELECTRICAL TESTING 66M!I LAToug rITIIN 'NcLo, T

PATTCNIPtIL%

A TUAT 0$

I 55%."T'tTN5 t>>I

~L. rLUbN r NVONOI IIIIl~

III N)QO 5UIIVKILLANCK TC51INC 5/2 5/5 LINC-Ut ZJ'/12 CONTINGENCY ofc BE GIN HE ATVP C-.O.

12/ 21 IAAN5IVfClb I ){( NtrL2015 'loTAL coNTINotNcT t

CONATtuCTION/OJCNATIONb MSIV Y PAT TERN

SUMMARY

SCHEDULE

/

REQUESTED TECHNICAL SPECIF'ICATION CHANGES FOR NINE MILE POINT 2 Letter Date

~Sub 'act Status 2/3/87 reverse direction testing of MSIV drain valves (clarification) expect for FP 1/23/87 12/9/86 MSIV between seat testing typo and clarifying no longer needed expect for FP 12/9/86 and 4/10/86 fire protection uncertain, but hope to have for FP 12/10/86$

1/15 and 3/27/87 suppression pool temp.

expect for FP 12/9/86 12/10/86 12/9/86 3/11/87 etc.

SDV drain and vent valves SORC and SRAB reporting times H2 Recombiner T/C MS IV amendment expect to reject expect to reject withdrawn need prior to criticality

DISTRIBUTION NRC PDR Local PDR PDI-1 Rdg.

J. Partlow R. Capra D. Neighbors OGC-Beth E. Jordan ACRS (10)

S.

Varga A. Thadani M. Haughey R. Benedict J.

Joyce M. Hodges B. Clayton J.

Johnson

y t 1

f