ML18037A082
| ML18037A082 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/20/1992 |
| From: | Menning J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9208310326 | |
| Download: ML18037A082 (58) | |
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Docket Nos.
50-220 and 50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20565 August 20, 1992 LICENSEE:
Niagara Mohawk Power Corporation FACILITY:
Nine Mile Point Nuclear Station Units 1
and 2
SUBJECT:
SUMMARY
OF AUGUST 10,
- 1992, MEETING TO DISCUSS CURRENT AND ANTICIPATED LICENSING ISSUES FOR NINE MILE POINT UNITS 1
AND 2 A meeting was held in the NRC One White Flint North Office in Rockville, Maryland, with Niagara Mohawk Power Corporation (NMPC) and NRC staff representatives to discuss current and anticipated licensing issues for Nine Nile Point Units 1 and 2.
The licensee had requested this meeting.
Enclosure 1 is a list of the meeting attendees.
Enclosure 2 is a copy of the handout material provided by NHPC and includes the latest version of NMPC's 5-year licensing plan for Nine Mile Point Units 1 and 2.
Initial discussions concerned certain current and potential licensing issues that were of particular interest to the NRC staff.
The-initial areas of discussion and the status of related licensee activities are summarized below.
1.
Potential Recei t and Stora e of Fuel from Shoreham NHPC had previously informed the NRC'staff that slightly irradiated fuel from Shoreham could be shipped to Nine Hile Point Nuclear Station for possible use in Unit 2.
'During the subject meeting NMPC advised the NRC that no decision has been made on whether to ship the spent fuel to Unit 2.
NHPC also stated that this spent fuel would not be used in the Unit 2 reactor if it were received at their facility. If the Shoreham spent fuel is received it would most likely be stored in a dry spent fuel storage facility.
NHPC indicated that they have no immediate plans to receive the spent fuel and no active project to construct a dry spent fuel storage facility.
2.
BWR Reactor Vessel Water Level Instrumentation Issue On July 24,
- 1992, the NRC issued Information Notice 92-54, "Level Instrumentation Inaccuracies Caused by Rapid Depressurization,"
to alert licensees to potential inaccuracies in water level indication during and after rapid depressurization events.
Related concerns for BWR reactor vessel water level instrumentation were the subject of a meeting between the NRC staff and the BWR Owners Group (BWROG) Regulatory
Response
Group on July 29, 1992.
During the subject meeting the NRC staff asked NMPC to discuss their current involvement with the this issue.
NHPC 920831032b:,920820 PDR ADOCK"I05000220 P
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August 20, 1992 responded that they had participated in the meeting on July 29,
- 1992, and were reviewing and commenting on materials presented by the industry at that meeting.
NMPC also stated that they were reviewing material that the BWROG committed to provide to the NRC staff subsequent to that meeting.
The NHPC representatives also stated that they were evaluating their compliance with related guidance from General Electric.
Generic Letter 92-01 The NRC staff has performed a preliminary review of NHPC's response to Generic Letter 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)," for Nine Mile Point Unit 1.
The response stated that the Charpy upper shelf energy (USE) of two beltline plates of the reactor vessel is predicted to be below the 50 ft lb screening criteria in Appendix G,
10 CFR Part 50, at the present time when NRC-approved methods are used to calculate the Charpy USE.
The response also stated that NMPC performed an additional calculation using an alternate
- method, the results of which predict that both plates'harpy USE will not fall below 50 ft lb prior to the end of the Unit 1 operating license.
During the subject meeting the NRC staff advised NMPC that, as discussed in an August 6,
- 1992, telephone conference call, the alternative calculational method is not fully acceptable since it is based on a very limited amount of data.
Therefore, the NRC staff recommended that NMPC perform an elastic-plastic fracture mechanics analysis to demonstrate that these plates have margins of safety against fracture equivalent to those required in Appendix G of the ASME Code.
Guidance for performing this analysis was subsequently transmitted to NMPC in a letter dated August 12, 1992.
Generic Letter 88-01 Generic Letter (GL) 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," was issued January 25, 1988.
NRC staff review of this GL remains open for Unit 2 pending incorporation of the NRC staff position on leak detection included in the GL into the unit's technical specifications.
NMPC has delayed incorporation of the NRC staff's position anticipating that the BWROG would develop an alternate position on leak detection that would be acceptable to the NRC staff.
During the subject meeting the NRC staff advised NMPC that it understood that the BWROG has decided not continue to pursue an alternate position on leak detection.
In view of the BWROG's decision, the NRC staff encouraged NHPC to expeditiously submit a license amendment request that would incorporate the NRC staff position into the Unit 2 technical specifications.
Power U rate NMPC had previously advised the NRC staff that they were participating in generic BWR power uprate evaluations which determined that a
4 percent power increase was feasible for Unit 2 without any major plant modifications.
During the subject meeting NMPC advised the NRC staff
c
August 20, i992 that they are currently planning to submit a 'power uprate license amendment request in August 1992.
- However, NHPC indicated that the submittal could be delayed if a decision is made to implement the uprate during the fourth rather than the third refueling outage.
NHPC subsequently briefed the NRC staff representatives on the latest update of the 5-year licensing plan for Nine Nile Point Units 1 and 2.
NHPC then discussed the status of both planned and submitted licensing requests.
As part of these discussions the NRC staff reviewed with NHPC the status of open TACs and identified those closed TACs that require confirmation by NHPC that implementation has been completed.
At the close of the meeting the NRC staff encouraged NMPC to allow sufficient time for NRC staff review of submitted items, particularly those of lower priority.
The NRC staff representatives also encouraged NHPC to continue to advise the NRC staff of changes in their plans for licensing submittals.
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout Haterial John E. Henning, Project Hanager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures:
See next page
Niagara Mohawk Power Corporation CC:
Hark J. Wetterhahn, Esquire Winston
& 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 Allendale 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 13211 Nine Mile Point Nuclear Station Unit Nos.
1 and 2
Hr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Hr. Hartin J.
HcCormick 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 Mr. 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 Hr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Hr. Richard H. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, New York 12210
~
~
ENCLOSURE 1
ATTENDANCE LIST August 10,
- 1992, Meeting to Discuss Current and Anticipated Licensing Issues for Nine Mile Point 1
and 2
Name Donald S.
Brinkman Cheryl Beardslee Robert A. Capra Jose A. Calvo John E. Menning Nick A. Spagnoletti Joseph F. Firlit David K. Greene W. David Baker Position Senior Project Manager Reactor Engineer (Intern)
Project Director Asst. Director for Region I Reactors Project Manager Program Director U-1 VP Nuclear Support Manager Licensing Program Director U-2 Or anization NRC/NRR/PD I-1 NRC/Region I NRC/NRR/PD I-1 NRC/NRR/DRP-I/I I NRC/NRR/PD I-1 Niagara Mohawk Niagara Mohawk Niagara Mohawk Niagara Mohawk
~
~
ENCLOSURE 2 NIAGARAMOHAWKPOWER CORPORATION NUCLEAR DIVISION NINE MILEPOINT NUCLEAR STATION UNITS 1 AND 2 FIVE YEAR PIAN OF NRC RELATED ISSUES 1992 1997 June 1992
A
~
I
FlVE-YEAR PLAN OF NR 'ELATFDl~"JE IN 0
UCTfO The Nuclear Division Business Plan is a road map to guide efforts toward improvements in four key performance areas, i.e., Safety, Commercial, Regulatory, and Professional.
Strategy C of Objective 3 (Regulatory Performance) provides for the development of a comprehensive 5-year plan to address all NRC-related issues.
This document is the product resulting from the Strategy C Action Plan.
Additional actions to present the plan to the NRC and to perform continuing maintenance of the plan will be carried out as required by the Business Plan.
A comprehensive 5-year plan of NRC-related issues was included in the Business Plan to focus additional attention on the number of issues facing each unit, scheduling of those issues, and the impacts on resources.
It is expected that this document will aid in improving communications within the Nuclear Division, between Niagara Mohawk and the NRC, and will provide information for overall planning efforts.
Through this document, Niagara Mohawk hopes to communicate a broad overview of the regulatory environment, Niagara Mohawk commitments and Niagara Mohawk/industry initiatives being undertaken by and for the Nine Mile Point stations.
The NRC should then be better able to plan its resources in support of Niagara Mohawk.
Niagara Mohawk will also be in a better position to manage its current workload and commitments, and to plan future efforts.
DEVEL PAfENT:
A number of potential sources for "NRC-Related" issues were reviewed for issues to include in the plan.
Among those reviewed were:
Nuclear Division Business Plan Nuclear Commitment Tracking System Technical Specification Amendment Request Lists Recently Issued Generic, Letters/Bulletins Recently Issued Regulations BWROG/NUMARC Initiatives FSAR Issues 001 724LL
L
FIV -YEAR PLAN OF NR RELAl'Ef3 l8~~VES DEVELOPMENT: (Continued)
Literally hundreds of issues could have been selected from these sources.
Consequently, in order to make this document as meaningful and useful as
- possible, a set of guidelines was developed to assist in selecting which issues would be included in the 5-year plan.
The guidelines are included as Attachment A.
Once selected for inclusion, each issue was identified in the 5-year plan by unit (or site), by year, and by calendar quarter within the year.
Generally, placement by year (and calendar quarter) represents when the issue will be submitted to the NRC for action, review or information. When nothing is planned to be submitted, placement represents when the issue is expected to be completed or fully implemented.
For clarity, issues have also been separated by submittal or no submittal, to assist in determining which resources may be involved.
In order to complete actions by the dates specified, naturally work must begin well in advance.
For a few select long term efforts, key milestones have also been included to give a more complete picture.
Generally, however, additional detail on individual issue schedules is available from other tracking systems.
I TENANCE:
This document is a "living"document.
This means it will be regularly updated as changes and additions become known, and issued in accordance with the Business Plan.
The same sources used in the initial development will continue to be monitored for new issues and updates.
In addition, all h,uclear Division and NRC personnel who have occasion to use this document are invited to submit updates, as well as suggestions or recommendations to make the 5-year plan more useful.
Please submit any input to the Manager of Nuclear Licensing at Salina Meadows-2.
~YEAR E
As noted above, the 5-year plan is presented by year, beginning with 1992.
All further breakdowns for each year are presented on the same page to provide an overview for the entire year.
In addition, each units'efueling outage is highlighted in the appropriate place.
Specific dates for refueling outages from 1993-1SS6 have not yet been formalized, and are therefore only provided as approximations.
001724LL l2)
FIVE-YEAR PLAN OF NRC RELATED IS UES
~YA E
N:
1C i
d)
Each of the issues included on the 5-year plan are obviously abbreviated.
In order to provide some clarification, Attachment B has been included.
This attachment details from what source items were identified. If you need additional information on a particular item, you may consult that source or those responsible for the issue.
Items that were completed since the last issue of this plan have been shaded.
Items that were planned but not completed since the last issue of this plan remain
- unshaded, and a new planned completion quarter is indicated in parenthesis, e.g.
(4Q92).
These items are then repeated in the new quarter.
In addition, future items whose completion schedule has changed have simply been moved.
M1724LL I3)
4 I ~
l
f1992) CALENDARQUARTERS PAGE 1 0/
UNIT 1 SUBMITTAL
~
SRM/IRM Calibration Amendment (4Q92)
~
Tech. Spec. Bases 3.5.3 (3Q92)
~
Refuel Outage Amendmonts (3Q92) gp>OQpfpF<'Pra 0;;:):RsspottstI
~
Reactor Coolant Amendment IDELAYED) fp/lii)i,:;,:riii(r'0!YiJNwoly~
s~i5s'Aiiiui'iirsi'i
~ T.S. Bases 3.5.3
~
Refuel Outage Amendments
~
3D Monicore Amendment
~
Revise SORC/SRAB Req.
Amend.
~
Remove PM Appl. of Procedures Amendment
~
Radioactive Eff. Rel. Rpt.
~
Tech Spec 6.9.3 Spoc Rpt Am.
~
Spent Fuel Storage Capacity Amendment
~
Instrumentation Amendment
~
SRM/IRM Calibration Amendment
~
Identify Required Inspections for Refuel Outage II(0
~
EDG Reliability Program (4Q92) ggblllfariip;:epanieiiiiYiitesri 8ll784jsi,',iriiii
~~". 'otP@lÃsw7Ãwfjipj
~
GL 92.01 (RPV Integ)
Response
~
CRD Stub Tube Cracking Fix Dovelopment
~
EDSFI Followup Actions Milo
~
Outage Safety Review
~
~
Blue Markup Process Review
~
EDG Reliability Program
~
SBO Procedure Changes
~
PM Plan for Succoss
~
Tech Spec Improvement Rpt.
UNIT2 SUBMITTAL
~
Shoraham Fuel Amendment (HOLD)
~
31 Day Position Verification Amendment (DELAYED)
'iP...:;.0Pco i:p'Cl'31'b:II:,:A'msndma j
+";:~Of~8$,p','(P',.',"I:Rssporxra
~
GEXL Amendment (4Q92)
~
~
Powor Uprate Amendment
~
Revise SORC/SRAB Req.
Amend.
~
Removo PM Approval of Procedures Amondmont
~
Inoperable Seismic Monitor Amend.
~
~
Radioactive Eff. Rel. Rpt.
~
~
Drawdown Amendment
~
increased MSIV Leakage Amendment
~
Leakage Detection (IGSCC)
Amendment
~
GEXL Arnerxlment
~
ERDS Survey
~
FSAR Update NO
~Oiife~ge:
iiifÃsAW'i SUBMITTAL gCA":A'eerrcjat07~>>'AX)
,~@@OP.fij jp'ftamrf 4"""i'-.'u~~~~
~>, GL-',99" O'j
- 4. ":B"-,'Trtm~s".'I(pot:Ci)tr a
Check Valve Program Admin. Procedures
~
GL 92%1 (RPV Integ)
Response
~
l8 C Procedure Rewrite
~
Maintenance Procedures Rewn e
~
UPS Modificiations
~
Adv. Sys. Training i "i SA -'. K
~
SBO Procedure Changes
~
PM Plan for Success
~
Tech Spec Improvement Rpt.
NOTE:
Six alternate amendments were submitted during the first half of 1992 In support of Un)t 1.
0017tcLL
f1992) CALENDARQUARTERS PAGE 2 CF.'UBMITTAL
'i"-:.=:..PO":;8,,I't
'Qjj~iiOI'w~i'eiiiii'870eetl 4".:.,'~"."'.Rn~,v:Opiret'f~~N,A
~
FFD Report NO SUBMITTAL
~e:::edti81,,,lX~!JNS'.I'.
eee
+>porose.'ttt.. metier:..
~~"~-I~9TA'e":NUMi(lie'Aeeee'emcee
" '"ee'"::~
4~+Rmi4ahIlitg:.Antdto4
~
Annual Emergency Exercise
~
ISTA/Present to NRC
~
5-Yr Plan Update
~
Business Plans 1993-1996 0017100.
~,, ~
(1993J CALENDAR QUARTERS PAGE 1 OF.
UNlTf SUBMITTAL
~
NO SUBM(TTAL T.S. Amendments es Required Radioactive Eff. Rel. Rpt.
Perform Torus Thickness Measurements GL 89-13 (SW) Report GL 88-14 (IA) Rpt. - Phase 2 GL 89-16 Hardened Vent Mod.
B&0-13 Insp.(Core Spray Inep.)
DCRDR/RG1.97 NUREG 0819-FW flow Report VT FW Spargers/UT Nozzle ERDS Implementation MSIV Room Access-VA Req.
GL 87<5 Rx. Mead Cav. DLFS Begin 8-Downcomer Bny/1'orus Mod.
8&8%4 CS Pump/Recirc Op Tost LPP Discharge Check Valve RPV Boltline lnstalllTest Redo Turbine Eff. Mod.
FW Control Valve Repl.
Containment H202 Monitoring Mod Two CR Withdrawal Mod GL 89%8 (E/C) lnsp. Plans
~
T.S. Amendmonts as Required
~
FSAR Updato
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
10CFR20/RP Program Amendmont
~
~
Perform Torus Thickness Measurements
~
GL 89-08 (E/C) Insp. Plans
~
Outage Safety Review 4
l
~
T.S. Amendments as Requirod
~
S/C Leakage Amendment
~
EDSFI Followup Actions Milestone UNIT2 SUBM(TTAL T.S. Amendments as Required Refuel Outage Amendments Radioactive Eff. Rel. Rpt.
MPCS flaw Fracture Mechsigcs; Justification to Operate SBO Actions Complete
~
T.S. Amendments as Required
~
~
Right-Sized USAR
~
Check Valve Actions Complete T.S. Amendments as Required 10CFR20/RP Program Amondment Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
FSAR Update NO SUBMITTAL issue 1993 Refuel Outage Preplan EROS Implementation Begin 24-Month Cycle P(nn
~
Powor Uprete Implementation
~
Adv. Sys. Training
~
Implementation - Complete
~
CR Annuncietors (Bal.)
~
~
BOP Annunciator Cabinots,
~
GL 88-14(IA) Complete g;;,8'~.
Nw%4~'"i NR~~~M$Mk~
cot 710LL
(1993) CALENDARQUARTERS PAG=-2 OE SITE SUBMITTAL NO SUBMITTAL FFD Report Occupation Exp. Report Present 5-Yr. Plan to NRC Implement LLRW Interim Storage Plan 10CFR20 - RP Program Implementation ReliebTiity Centered Maintenance Program implementation
~
Red. Env. Operating Report
~
QATR/FPQAP Update
~
ISTA
~
FFD Report
~
Annual Emergency Exercise
~
ISTA/Present to NRC 001710LL
f1994) CALENDARQUARTERS PAGE'
~~r'-.
P c
2 UNIT 1 SUBMITTAL
~
T.S. Amendments as Roquired
~
Radioactive Eff. Rel. Rpt.
~
Perform Torus Thickness Measurements
~
T.S. Amendments as Required
~
FSAR Update T.S. Amondments as Required Refuel Outage Amendments Radioactive Eff. Rol. Rpt.
Perform Torus Thickness Messuremonts
~
T.S. Amendments as Roquired NO SUBMITTAL Doc. RG 1.97 Compliance Begin 4-Downcomor Bay/Torus Mod.
Issue 1995 Refuol Outage Preplan
~
FSAR Verification Program
~
EDSFI Followup Actions Milestone UNIT2 SUBMffTAL
~
T.S. Amondmonts as Required
~
Radioactive Eff. Rel. Rpt.
~
GL 88-14IIA)-Report Ph. Ill NO SUBMITTAL
~
T.S. Amendments as Required
~
Refuel Outage Amendments
~
Radioactive Eft. Rel. Rpt.
4-Yr. Simulator Cert.
~
T.S. Amendments as Required
~
FSAR Update SITE SUBMITTAL
~
FFD Report
~
Occupational Exp. Roport
~
Present 5-Yr. Plan to NRC NO SUBMITTAL Rad. Env. Operating Report
~
QA Prgm. Rnwl. Red. Mtl. Pkg.
QATR/FPQAP Update
~
ISTA FFD Report
~
Annual Emergency Exorcise
~
ISTAIProsent to NRC 00 I710u.
e-4
~ /I>>
l"
(1995) CALENDARQUARTERS PAGE 7.jF UNIT 1 SUBMITTAL
~
T.S. Amendments as Required Radioactive Eff. Rel. Rpt.
PT/UT FW Nozzle PT A Nozzle Bore/Inner Radius B88%4 Install Recirc. Line App. J Containment Spray Mod.
~
T.S. Amondments as Required
~
FSAR Update
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
4-Yr. Simulator Cert.
Repoit'O
~
DCRDR Follow Up,
~
B88%8 Re-oval. Emer.
Condonser Linos for Thermal Stratification
~
Implementation - Begin
~
~
RPV Beltline Insp.
44FvgL<oN;AQUA@'.. "~':
~
688-08 IStrstification) Monitor
~
Emergency Cooling System implement Spent Fuel Intorirr Storage Plan DBR Program Complete i I
I UjV/72 SUBMITTAI
~
T.S. Amendments as Required
~
T.S. Amendments es Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendmonts as Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amondmants es Required
~
FSAR Update NO SUBMITTAL SITE SUBMITTAL e
"FD Report
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC NO SUBMITTAL
~
Rad. Env. Operating Report
~
QATR/FPQAP UPDATE
~
ISTA
~
FFD Report
~
Annual Emergency Exercise
~
ISTA/Present to NRC ool 71 ou.
A"
~x I,'
,0 E
f1996) CALENDARQUARTERS PAGE 1 QF UNIT 1 SUBMITTAL
~
T.S. Amendments es Required
~
Radioactive Eff. Rel. Rpt.
~ T.S. Amendments as Required
~ FSAR Update
~
T.S. Amendments as Required
~
Refuel Outage Amendments
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Roquirod
- Z NO
~
Maintenance Program Review SUBMITTAL
~
Issue 1997 Refuel Outage Preplan
~
Maint. Rule Implementation
~
GL 89-10 (MOVI Implementation - Complete
~
HP/LP Turbino Overhaul
~
UNIT2 SUBMITTAL
~
T.S. Amendments as Required
~ T.S. Amendments as Required
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Roqc
~
FSAR Update NO SUBMITTAL
~
Maintenance Program Roview
~
Maint. Rule implementation Ki@rieiL~
SITE SUBMITTAL
~
FFD Report
~
Occupational Exp. Report
~
Prosent 5-Yr. Plan to NRC
~ Rad. Env. Operating Report
~ aATR/FPaAP Updates
~
FFD Report NO SUBMITTAL
~ ISTA
~
Annual EmergencY Exercise
~
ISTA/Present to NRC 001710ll
. $pV-
~
4 a
~
f
~ t I
ll
(1997) CALENDARQUARTERS PAGE 1 OF Q/I/IT f SUBMITTAL
~
T.S. Amendments as Required
~
T.S. Amendments as Roquirod
~
T.S. Amendments as Required
~
T.S. Amendments as
~
Radioactive Eff. Rol. Rpt.
~
FSAR Update
~
Radioactive Eff Rol Rpt Required NO SUBMITTAL UNIT2 SUBMITTAL
~
T.S. Amendments es Required
~
T.S. Amendments as Requirod
~
Radioactive Eff. Rel. Rpt.
NO SUBMITTAL
, ; +88%84";.';OQFAQE' T.S. Amendmonts as Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
FSAR Update SITE SUBMITTAL
~
FFo Report
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC NO SUBMITTAL
~
Rad. Env. Operating Report
~
QATR/FPQAP Updates
~
ISTA
~
FFD Report
~
Annual Emergency Exorcise
~
ISTA/Present to NRC 001710u.
0
OURCE OF I SUES gNI~7 10CFR20/RP Program/Amendment (BP 1.B.2, 502850) 3D Monicore Amendment (Tech Spec Amendment Requests)
B 80-13 Inspection - Core Spray Sparger and Piping (500456-01)
B 88-04 CS Pump/Recirc Line Operability Test (502086-07)
B 88-04 Install Recirc Line (502086-09)
B 88-08 (Thermal Stratification) Monitor Emergency Cooling System (502202-07)
Begin 8-Downcomer Bay/Torus Mod. (Engineering Plans)
Blue Markup Process Review (502932-01)
Containment H202 Monitoring Modification (502937-01, 502932-02)
CRD Stub Tube CrackinggBP 1.A.5)
DBR (Design Basis Reconstitution) Program Complete (BP 2.C.3)
DCRDR/RG 1.97 - Follow up Report (502672)
Delete RETS Amendment (Tech Spec Amendment Requests)
Document RG 1.97 Compliance (500489-03)
EDG Reliability Program (502603-07)
EDSFI Followup Actions (502906) - Milestones ERDS Implementation (502866)
Feedwater Control Valve Replacement (Engineering Plans)
FSAR Update (Regulations)
FSAR Verification Program (502589-02) 001724LL
0 pf>l
+:
4p
'5 \\
J'
ATTACHMENT8 R
E Ft E
Qil/IT 1: (Continued)
GL 87-05 Reactor Head Cavity Drain Line Flow Switch (500675-05)
GL 88-14 (IA) Report - Phase 2 (502470) - Generic Letter on Instrument Air System Gl 88-16 Hardened Vent Mod (502533)
GL 88-20 (IPE) Report (503647)
GL 89-10 (MOV) Implementation - Generic Letter on Motor Operated Valves (BP 1.A.6)
GL 89-08 (E/C) Inspection Plans (502501)
GL 89-13 (SW) Perform PAT (50253S-07)
GL 89-13 (SW) Report (502539) - Generic Letter on Service Water Systems GL 89-15 (ERDS) Implem8ntation (502569-02)
GL 91-11 (Proc.) Response (502862)
GL S2-01 (RPV Structural integrity) Response (502938-00)
Identify Required Inspections for Refuel Outage (502966)
Instrumentation Amendment (Tech Spec Amendment Requests)
Integrated Leak Rate Test Issue Refuel Outage Preplan (BP 2.B.3)
LPP (Liquid Poison Pump) Discharge Check Valve Test (502380-05)
Maintenance Program Review/Rule Implementation (502818)
MSIV Room Access - Vital Area Requirements (502692)
NUREG 0619-Feedwater Flow Report (502772-01) 001724LL (2)
ATTACHMENTB OUR E
F I E
ggllT 1: (Continued)
Outage Safety Review (BP 1.A.2, 502908)
PM (Plant Manager') Plan for Success (502941-08)
PT/UT Feedwater Nozzle (502415-05, 502415-07)
PT "A" Nozzle Bore/Inner Radius (502415-01)
Perform Torus Thickness Measurements (BP 1.A.4)
RPV (Reactor Pressure Vessel) Beltline installation/Test Radioactive Effluent Release Report (503294-04)
Reactor Coolant Amendment (Tech Spec Amendment Requests)
Refuel Outage Amendments (Tech Spec Amendment Requests)
- Select Based on Outage Needs Remove PM (Plant Manager) Approval of Procedures (Tech Spec Amendment Requests)
Revise SORC/SRAB Requirements Amendment (Tech Spec Amendment Requests)
Revised 2nd 10-Year ISI Program Plan (502356)
SBO (Station Blackout) Procedure Changes (502413-16)
S/C (Secondary Containment) Leakage Amendment (502952-03)
\\
SRM/IRM Calibration Amendment (Tech Spec Amendment Requests)
Spent Fuel Interim Storage Plan (BP 'I.C.2)
Spent Fuel Storage Capacity Amendment (Tech Spec Amendment Requests)
Tech Spec Bases 3.5.3 (Tech Spec Amendment Requests)
Tech Spec 6.9.3 Special Reports Amendment (Tech Spec Amendment Requests) 001 724LL
ATTACHMENTB S
URGE OF ISSUES
@NIT 1: (Continuedi Tech Spec Improvement Report (BP 3.C.2)
Turbine Efficiency IVlod (Engineering Plans)
Two CR (Control Rod) Withdrawal Mod (502898-01)
VT Feedwater Spargers/UT Nozzle (502415) gNIT2:
10CFR20/RP Program/Amendment (BP 1,B.2, 502850) 31-Day Position Verification Amendment (Tech Spec Amendment Requests) 4-Year Simulator Certification (502687-02)
Advanced System Training (503232)
"B" Transformer Root Cause (502874-01)
BOP Annunciator Cabinets (502869-08)
Begin 24-Month Cycle Plan (BP 2.A.4)
Blue Markup Process Review (502932-14)
CR Annunciators (503117) - Modifications to Control Room Annunciators to Reduce Number of Nuisance Alarms; "Black Board" Concept.
Check Valve Program Administrative Procedures(Actions (502897)
Drawdown Design/Amendment (5031 54-05)
EDG Reliability Program (502603-06)
EOP Inspection Items (502822-04)
- Emergency Operating Procedure Inspection Open Items'RDS Survey (502569-01)
- Emergency Response Data Systems 001 724LL I4)
sf 4
ATTACHMENTB URCE OF ISS E
UNIT2: (Continued)
ERDS Implementation (502569)
Erosion-Corrosion (502540) - Part of the Service Water Generic Letter FSAR Update (Regulations)
GEXL Amendment (Tech Spec Amendment Requests)
- Phase III (502470) - Generic Letter on Instrument Air System GL 88-20 (IPE) Report (502532-01) - Generic Letter on Individual Plant Evaluations GL 89-13 (SW) Report (502540) - Generic Letter on Service Water Systems GL 89-10 (MOV) Implementation (BP 1.A.6)
GL 91-11 (Proc.) Response (502870-00)
GL 92-01 (RPV) Structural Integrity Response (502944-00)
HPCS Flaw Fracture Mechanics - Justification to Operate (502782)
HPCS, Nozzle Weld Replacement (502782-19)
IRC Procedure Rewrite (502780-02)
Increased MSIV Leakage Amendment (Tech Spec Amendment Requests)
I Inoperable'Seismic Monitor Amendment (Tech Spec Amendment Requests)
Issue Refuel Outage Preplan (BP 2.B.3)
Leakage Detection (IGSCC) Amendment (Tech Spec Amendment Requests)
License Condition 2.C(3)b.ii (See Shoreham Fuel Amendment)
Maintenance Procedure Rewrite (502941-01) 001 724LL (5)
<<l
ATTACHMENTB 0
RCE OF lSSUE QNIT 2: (Continued)
IVlaintenance Program Review/Rule Implementation (502817)
Outage Safety Review (BP 1.A.2, 502908)
PM (Plant IVlanager's) Plan for Success (502941-09)
Power Uprate Amendment (Tech Spec Amendment Requests; GE Settlement)
Power Uprate Amendment/Implementation (BP 2,A.3; GE Settlement) r Radioactive Effluent Release Report (503296-05)
Refuel Outage Amendments (Tech Spec Amendment Requests)
- Select Based on Outage Needs Remove PM (Plant IVlanager) Approval of Procedure (Tech Spec Amendment Requests)
Right-Sized USAR (BP 3.Ck3)
Revise SORC/SRAB Requirements Amendment (Tech Spec Amendment Requests)
SBO (Station Blackout) Action Complete (502413-22)
SBO (Station Blackout) Procedure Changes (502413)
S/C (Secondary Containment) Leakage Amendment (Tech Spec Amendment Requests)
Shoreham Fuel Amendment (BP 2.B.6; Tech Spec Amendment Requests)
Tech Spec Improvement Report (BP 3.C,2)
UPS Modifications (502882-03)
- Review of UPS Loads and Replacement of some of the UPS Units Involved in the 8/13/91 SAE.
~/E'0CFR20/RP Program/Amendment (BP 1.B.2, 502850-00) 001724LL
4
ATTACHMENT8 SOURCE OF ISSUES
~E: (Continued) 5-Year Plan Presentation to NRC (BP 3.C.1)
Access Authorization Rule (502847)
Annual Emergency Exercise (EP Plans)
Business Plans 1993-1996 (BP)
ERF Audit Corrective Actions (503335)
FFD (Fitness for Duty) Report (502656)
GL 91-14 (ENS Phones) Upgrade (502902) lSTA (BP 3.A.2) - tnternal SALP-Type Assessment LLRW (Low Level Radwaste) Storage Plan (BP 1.C.1)
NUMARC Procurement irrelative (502682-01)
Occupational Exposure Report (503401-03)
QA Program Renewal for Radioactive Material Packaging (502479)
QATR (Quality Assurance Topical Report)/FPQAP (Fire Protection Quality Assurance Plan) Update (502854)
Radiological Environmental Operating Report (503213-03)
Reliability Centered Maintenance Program (BP 2.A.1) 001724LL l7)
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~
A
Attachment A
(Q'I)
ANZNDNZNT RZ UZSTS SUBWITPZD AND AWAITING NRC APPROVAL KO-',,',";.j: '.,
ITEM Appx. J. Reactor Coolant Isolation Valves, Primary Coolant System Pressure Isolation Valves, (Includes Type B
Penetrations From 2 to 3
Years)
TAC NO 79135 76986 SUBMIT DATE 2/7/92 NEED DATE STATUS Not Specified Amendment sholly'd under staff review Minimum'owncomer Submergence Lake Water Temperature 81731 9/20/91 3/12/92 June 1992 Under staff review Delete Fire Protection/GL 82560 88-12 1/7/92 ASAP Under staff review; NRC reviewing Revision 2 of FHA before approving this Amendment Emergency Cooling Bases Change 3/20/92 Not Specified Providing supplement to delete references to original FSAR 002553GG
f
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~
Attachment B
(Uh BMENDMENT RE UESTS PLANNED BUT NDT SUBMITTED TD NRC
+00 ITEM STATUS COMMENTS ESTIMATED SUBMITTAL DATE IPB RIO Spent Fuel Storage Capacity Holtec information received; 9/92 drafting 3/86 MG Set Modification SRAB approved 8/92 3/67 Revise Rx Building Recently committed to NRC Leakage Rate Scheduling 3/66 LLW Waste
- HPCI, ERV Surveillance Testing DraftingE dependent on rulemaking Drafting 10/92 10/92 3/50 3/40 Revise SRM/IRM (Neutron Monitoring Surveillance Interval)
Engineering justification due 10/92 9/92 3/34 3D-Monicore Scram
& Hydro Testing in Refuel Scheduled for SRAB 8/12/92 8/92 3/34
1:.
,A~~*
Attachment D
(Al)
RELIEF NESTS SDBNITTED AND ANAITING NRC APPROVAL IO',',-.."-',:
ITEM RELlEF REQUEST NO i-TAC NO SUBMIT DATE NEED DATE STATUS 1
Core Spray Containment Spray Pump Discharge Check Valves Emergency Diesel Generator Cooling Water Check Valves Main Steam ADS Valves CS-RR-1 CTS-RR-2 EDGCW-RR-1 MS-RR-1 10/8/91 10/8/91 5/26/92 10/8/91 ASAP ASAP ASAP ASAP Submitted supplement on 7/21/92 Submitted supplement on 7/21/92 Submitted supplement on 7/21/92 Under NRC Review 0 002553GG
ATTACIIMI:NT B (Page 1 of 4)
(tsar)
Antendntent Re uests Planned but Not Submitted to NR NO.
ITEM TARGETED SUBMITTALDATE STATU COMMENTS 1
24-Month Fuel Cycle 2
Storage of Shoreham Fuel 4
Leak Detection (GL 88-01 Commitment) 5 Drawdown TS Submittal 6
CIV 31 Day Position 7
Inoperable Seismic Monitor 8
Rod Withdrawal in Hot Shutdown 9
Improved Tech Spec Topical Reports (Instrumentation LTR's) 10 Delete Response Time Testing 8/92 Unknown 12/92 9/92 8/92 3/93 Business Plan-No action Amendment in final review In Process-awaiting Tech Review and contract Redrafting Need final design Evaluating Need-Ops Action In final proofing Drafting Drafting 002716 LL
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August 20, 1992 that they are currently planning to submit a power uprate 1'icense amendment request in August 1992.
- However, NHPC indicated that the submittal could be delayed if a decision is made to implement the uprate during the fourth rather than the third refueling outage NHPC subsequently briefed the NRC staff representatives on the, latest update of the 5-year licensing plan for Nine Mile Point Units 1 and 2.
NMPC then discussed the status of both planned and submitted licensing requests.
As part of these discussions the NRC staff reviewed with NHPC the status of open TACs and identified those closed TACs that require confirmation by NHPC, that implementation has been completed.
At the close of the meeting the NRC staff encouraged NHPC'o allow sufficient time for NRC staff review of submitted items, particularly those of lower priority.
The NRC staff representatives also encouraged NHPC to-continue to advise the NRC staff of changes in their plans forlicensing submittals.
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout Material cc w/enclosures:
See next page Original Signed By:
John E. Henning, Project Manager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DISTRIBUTION:
CDocke.t:Fille PDI-1 Reading
- JPartlow, 12/G/18 JCalvo JMenning CVogan
- EJordan, HNBB 3701 ACRS (10)
- CCowgill, RGN-1 NRC
& Local PDRs TMurley/FHiraglia, 12/G/18 SVarga RACapra DBrinkman OGC CBeardslee, RGN-1
- RLobel, EDO 17/G/21 Plant File OFFICE PDI-1: LA CVo an M NANE S /M/92 DATE OFFICIAL RECORD COPY PDI-1: PH JMennin
'y/M 92 PDI-1: PM DBrinkman f'/go/92 P
- 0, 92
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