ML17059A054
| ML17059A054 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/28/1993 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9310010074 | |
| Download: ML17059A054 (56) | |
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Docket Nos.
50-220 and 50-410 0
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 September 28, 1993 LICENSEE:
Niagara Mohawk Power Corporation FACILITY:
Nine Mile Point Nuclear Station, Units 1 and 2
SUBJECT:
SUMMARY
OF SEPTEMBER 23,
- 1993, MEETING TO DISCUSS CURRENT LICENSING ISSUES FOR NINE MILE POINT, UNIT NOS.
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 planned licensing issues for Nine Mile Point, Unit Nos.
1 and 2.
The licensee had requested this meeting.
Enclosure 1 is a list of meeting attendees.
Enclosures 2-5 are copies of the handout materials provided by NMPC.
The. meeting attendees discussed the current licensing issues open on both units.
NHPC identified four submittals (TAC Nos.
- H86378, H86186,
- H86185, and M86110) for which completion of the NRC staff's review is requested to support the refueling outage scheduled to begin on October 1,
1993.
The NRC staff representatives stated that it expects to complete these reviews in sufficient time to support NMPC's needs.
NRC staff reviews of the other open licensing issues are progressing in a satisfactory manner.
NHPC representatives briefed the NRC staff representatives on planned licensing submittals.
Enclosures 2 and 3 are lists of license amendment requests for Units 1 and 2, respectively, that are expected to be submitted by December 31, 1993.
NMPC representatives also provided the NRC staff representatives with copies of the latest update of the 5-year licensing plan for Units 1 and 2.
Enclosure 4 is a copy of the latest update of this plan.
The NRC staff representatives were informed that during NHPC's review of material involving Generic Letter 92-01, "Reactor Vessel Structural Integrity," NMPC had determined that the NRC's Power Reactor Embrittlement Data Base does not contain the most updated surveillance data for the Unit 1
reactor vessel.
The details of NMPC's findings regarding this issue are
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931001 0074930928 PDR ADOCK'5000220 P
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September 28, 1993 described in Enclosure 5.
The NRC staff thanked NMPC for bringing this to our attention and agreed to provide a copy of Enclosure 5 to Oak Ridge National Laboratory so that the updated information can be entered into the data base.
Donald S.
Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Attendees 2.
List of License Amendment Requests Unit 1
3.
List of License Amendment Requests - Unit 2 4.
Five-Year Plan of NRC Related Issues 5.
Details of NMPC's findings Regarding Surveillance Data for NMP-1 Reactor Vessel cc w/enclosures:
See next page
1
Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit Nos.
1 and 2
CC:
Mark 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 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
, '\\
Ms.
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 Hohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Mr. Kim Dahlberg Unit 1 Station Superintendent Nine Nile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Hr. John H. Hueller 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 Mr. 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
P I
ENCLOSURE 1
A ENDANCE LIST S
P EMBER 23 993 MEE G
ITH NIAGARA MOHAWK POWER CORPORATION ISCUSS CUR IC S
NG SSUES OR IN 0
U~NDL 1
NO Name Donald S.
Brinkman Robert A. Capra W. David Baker Denise V. Wolniak William C. Drews David K. Greene John E. Menning Position Sr. Project Manager Director Program Director Supervisor - Licensing
. Support Licensing Engineer Manager Licensing Project Manager Or anizatio NRC/PD I-1 NRC/P0 I-1 NHPC NHPC NHPC NHPC NRC/PDI-1
UbHT 1 - ATTACHMENTA (Page 1 of 1)
Amendment Requests Planned but not Submitted to NRC NO.
ITEM I
Part 20 2
Delete APRM Downscale Revise Flow Comparator Quarterly Surveillance to Refuel Removal of MSL Rad Monitor and Delete Table 3.6.2 Shutdown Requirements 5
Delete tables through Generic Letter Liquid Poison Minimum Volume Limit Revise Setpoints for Undervoltage Relays Revise Bases for HPCI Surveillance/Delete HPCI 9
Redundant Diesel Generator Testing 10 Diesel Loading Bases 11
.Allow SGTS to Run in Refuel SUBMITTALSTO BE COMPLETED BY 12/31/93 X
X X
X X
X X
X STATUS/COMMENTS Awaiting Generic Letter No amendment yet identified; on hold awaiting Engineering In engineering Drafted; on hold awaiting Eng. work for mod.
Drafted Drafting Drafted; At SRAB Evaluating Justification Final Proofing Drafted Need PRA Study
0 1
NO.
ITEM UMT2 - ATTACHMENTA (Page 1 of 2)
- Amendment Requests Planned but not Submitted to NRC, SUBMITTALSTO BE COMPLETED BY 12/31/93 STATUS/COMMENTS 10 12 13 Part 20 Amendment Relocated TSV Testing H,O, Accident Monitoring/1.97 Increased Allowable MSIV Leakage Shift Work; ASSS Title Change Battery Charger Footnotes Removal of MSL Rad Monitor Revise 31-day Diesel Fuel Oil Analysis Resilient Seal IV Allowable Leakage Increase Purge Capability, 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> limit ATWS - RPT Action from place in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 14 days Revise AOT for remote shutdown from 7 days to 30 days Revise Purge Valve Action Statement X
X X
X Awaiting Generic Letter SRAB approved Drafting; Improved Tech. Spec. Item Submit mid-1994 Drafting Drafting with //14 and 115 Disapproved at SORC due to inactivity on modification, decision to pursue Improved Tech. Spec. Item Determining possible revisions Need Engineering Analysis, Engineering to scope work Improved Tech. Spec. Items m
I CD CJI m
003 190LL1
,(
UNIT2 - ATTACM4ENTA (Page 2 of 2)
Amendment Requests Planned but not Submitted to NRC NO.
14 15 ITEM Revise Battery Electrolyte Temperature Revise Bases 6-5 from AP 8.8 to NIP-DES-04 and Delete Isolation Times SUBMITTALSTO BE COMPLETED BY 12/31/93 X
X STATUS/COMMENTS Mock EDSFI finding, drafting with ¹6 and
¹15 Drafting with ¹6 and ¹14 003 190LL2
i r
NIAGARAMOHAWKPOWER CORPORATION l
l NUCLEAR DIVISION NINE MILE POINT NUCLEAR STATION UNITS 1 AND 2 FIVE YEAR PLAN OF NRC RELATED ISSUES 1993 1997 JUNE 1993
1
t t
FlVE-YEAR PLAN OF NR RELATED I E
I~TR Tl N:
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.
D~EVEL EVENT:
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 7
Nuclear Commitment Tracking System Technical Specification Amendment Request Lists Recently Issued Generic Letters/Bulletins Recently Issued Regulations BWROG/NUMARC Initiatives FSAR Issues 003351LL
{p. 1 of 3)
r
FIVE-YEAR PLAN F NR RELATED I E
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.
~NAINTENAN 8 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 Nuclear 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.
- EA As noted above, the 5-year plan is presented by year, beginning with 1993.
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 1995-1997 have not yet been formalized, and are therefore only provided as approximations.
003351LL Ip,2of3)
t
FIVE-YEAR PLAN F hlRC RELATED ISSUE Fi Y-PI:
[C Each of the issues included on the 5-year plan are obviously abbreviated.
In order to provide some clarification, Attachment 8 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 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. (4092).
These items are then repeated in the new quarter.
In addition, future items whose completion schedule has changed have simply been moved.
003351 LL (p. 3 of 3)
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(1993) CALENDAR QUARTERS PAGE 10F 2 UNIT 1
~
SUBMITTAL NO SUBMITTAL N;.:-.;.'=,";;,Bad'rosctIva':gff:::,fl'aI:;Spy
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I)19-FW flow Report (4Q93)
~
VT FW Spargers/UT Nozzle (4Q93)
':,'-."."WIVRqI)'tt) Q4'iNii V'A,:::,Rat('1 j4".:04":O'I4g;:~,,:,'"';;:;CD'"'..Q;F8 4~~N8'44'CS:,$$r'rt'pNi'Ai:.Oj::;VeN
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5'NgfU6i~ovY4664 sc44%x~N'MP5
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
10CFR20/RP Program Amendment
~
~
Perform Torus Thickness Measurements
~
B93-03 (Vessel Water Level Inst.) Response/Actions
~
T.S. Amendments as Required
~
NUREG 0619.FW flow Report
~
~
EDSFI Followup Actions Milestone
~
Temperature Monitoring-Tharmal Cycling in Emer.
Condenser UNIT2 SUBMITTAL NO SUBMITTAL e:::~~-'7~8Ã.
nrfmsnte'as:II~(r" (3Q93)
~
Drawdown Amendment (Delayed) i;-';;:;::,R~O',;()ut,;IAltta'rKImanta i"-:.:='::.H8$.'.:',Ri~;,Fiamrs.::.Qachan(cs;
~a'<<6(aiiiii'm:..'t'o-,:Op'a)s'to="'.:-!~~$80%4%:::~i(:
>~/~;:,.9 Sereteeeiouiiej Fiesi'ii (DELAYED)
~PNC~~4fiSerA<<do'itti~%ornj(a<ac
~
T.S. Amendments as Required
~
10CFR20/RP Program Amendment
~
Radioactive Eff. Rel. Rpt.
~
Power Uprate Amendment
~
B93%3 (Vessel Water Level Inst.) Response/Actions
~
T.S. Amendments as Required
~
FSAR Update
~
Adv. Sys. Training
~
Implementation - Continues
~
CR Annunciators (Bsl.)
~
~
BOP Annunciator Cabinets
~
GL 88-14(IA) Complete eAKFVEk',":OU'fA'6Ki"'".':.-,'.
NOTE: Tech Spec amendment schedules are determined in meetings with the Plant Managers periodically throughout the year.
The schedule/priorities change based on plant needs.
Therefore, only amendments committed to NRC and select others willbe included in the 5-Year Plan.
003351ll
(1993) CALENDARQUARTERS PAGE2 OF 2 3
SITE SUBMITTAL
'i.,':P-,FFD.':~.
i'.PgRiid,'",;E'nv,::;OjYeridij'j:~
~
FFD Report NO SUBMITTAL
~
Integrated Long-Range Plan (DELAYED)
N~t&
w5~~~)$
+A'RAoYIee'~;8~8'eliabili'ty Centered Maintenance Program-Deveiopment
+~knnueI:.Erne'rqego Y',.A'erlriee Busineee Ha'ne '1994-1'99'I 00335 1ll
(1994) CALENDAR QUARTERS PAGE 1 OF 1 3
UNIT 1 SUBMITTAL
~
T.S. Amendments as Required Radioactive Eff. Rel. Rpt.
Perform Torus Thickness Measurements Refuel Ou Amendments
~
T S Amendments as Required
~
FSAR Update
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
Perform Torus Thickness Measurements
~
T.S. Amendments as Required NO
~
Doo. RG 1.87 Compliance SUBMITTAL
~
Economio Analysis Corporate Commitments
~
Outage Safety Review
~
Issue 1995 Refuel Outage Report/Work Scope Freeze
~
FSAR Verification Program
~
EDSFI Followup Actions Milestone
~
08R Program Complete Q/I//7 g SUBMITTAL
~
T.S. Amendments as Required
~
T.S. Amendments as Required
~
Refuel Outage Amendments
~
Radioactive Eff. Rel. Rpt.
~
Rightsized USAR
~
Radioactive Eff. Rel. Rpt.
~
~
4-Yr. Simulator Cert.
~
T.S. Amendments as Required
~
FSAR Update NO
~
NUREG1455 Procedure SUBMITTAL Deficiencies Corrected
~
Issue 1995 Refuel Outage Reports/Work Scope Freeze
~
Design Basis Program SITE SUBMITTAL
~
FFD R port
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC
~
Rad. Env. Operating Report
~
OA Prgm. Rnwl. Rad. Mtl. Pkg.
~
FFD Report NO SUBMITTAL
~
10CFR20 - RP Program Implementation
~
Reliability Centered Maintenance Program Implementation
~
ISTA
~
Annual Emergency Exercise
~
ISTA/Present to NRC
~
ERF Audit Corrective Actions 003351U.
(1995) CALENDARQUARTERS PAGE 1 QF 1 UNIT 1 SUBMITTAL NO SUBMITTAL
~
T.S. Amendments as Required
~
Radiosctivo Eff. Rel. Rpt.
~
PT/UT FW Nozzle
~
PT A Nozzle Bore/inner Radius B88%4 Install Recirc. Une App. J Containment Spray Mod.
B80.13
. (Core Spray Insp.)
DCRDR Follow Up B8848 Emergency Cooling System Mode GL 88-14 (1A) Complete or Downgrade GL 89-10 (MOV)-
Implementation - Begin Integrated Leek Rato Test RPV Beltline Insp.
4@8~ENB-:",;.OSQR+
~
T.S. Amendments as Required
~
FSAR Update
~
T.S. Amendments ss Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
4-Yr. Simulator Cart. Report UNIT2 SUBMITTAI.
~
T.S. Amondments as Required
~
.T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
~
T.S. Amendments as Required
~
Rsdioactivo Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
FSAR Update NO SUBMITTAL
~
Outage Safety Review
~
Power Uprste Implementation
~
24-Month Cycle Commences (DELAYED)
":"HER%I'QAA@ek~~l
~
Implementation - Complete SITE SUBMITTAL
~
FFD Report
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC NO SUBMITTAL
~
Rad. Env. Operating Report
~
ISTA
~
FFD Report
~
Annual Emergency Exercise
~
ISTA/Present to NRC
'SO-'l3 Insp. (Core Spray Insp.)
00335 1 LL
I
(1996) CALENDARQUARTERS PAGE 1 OF 1 UNIT 1 SUBMITTAL
~
T.S. Amendments as Required
~
Rsdiosctivo Eff. Rel. Rpt.
~
Refuel Outago Amendments NO SUBMITTAL
~ T.S. Amendments as Required
~ FSAR Update
~
T.S. Amendments as Required
~
Radioactive Eff. Rol. Rpt.
~
GL 88-20 IIPEEEI Report
~
Msint. Rule Implementation
~
T.S. Amendments as Requirod
~
Imploment Spent Fuel Storage Plan UNIT2 SUBMITTAL
~
T.S. Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~ T.S. Amendmonts as Required
~
T S Amendments as Required
~
Radioactive Eff. Rel. Rpt.
~
T.S. Amendments as Required
~
FSAR Update NO SUBMITTAL
~
Outage Safety Review
~
Msint. Rule Implementation
~
Issue 1997 Rofuel Outago Preplan SITE SUBMITTAL
~
FFD Report
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC NO SUBMITTAL
~ Rad. Env. Operating Report
~ ISTA
~
FFD Report
~
Annual Emergency Exerciso
~
ISTAIPresent to NRC 003351u.
(1997) CALENDARQUARTERS PAGE 1 OF 1 UNIT 1 SUBMITTAL
~
T.S. Amendments as Required
~
Radioactive Eft. Rol. Rpt.
~
T.S. Amondments as Required
~
FSAR Update
~
T.S. Amendments ss Roquired
~
T.S. Amendments as
~
Radioactive Eff Rel Rpt Required NO SUBMITTAL Outage Safety Review GL 89-10 (MOV)
Implementation - Complete HP/LP Turbine Overhaul Integrated Lpak Rate Test
'offfA68~+l~:
UNIT2 SUBMITTAL
~
T.S. Amendments as Requirod
~
T.S. Amendments as Required
~
T.S. Amendmonts as Required
~
T.S. Amendments as
~
Radioactive Eff. Rel. Rpt.
~
Radioactive Eff. Re. Rpt.
Required
~
FSAR Update NO SUBMITTAL
~
Outage Safety Review g/7p SUBMITTAL e
FFO R p ~
~
Occupational Exp. Report
~
Present 5-Yr. Plan to NRC NO SUBMITTAL gggfggg~ggfgjgg~<'y+'
Rsd. Env. Operating Report
~
ISTA
~
FFD Report
~
Annual Emergency Exorciso
~
ISTA/Present to NRC
~
Rightsizing Complete 003 351u.
4 r
ATTACHMENTA IVllVIARY F UIDELINE FOR IN L
I N IN
-YEAR PLAN An issue will be considered for inclusion in the 5-year plan of NRC-related issues if it meets:
ONE OR MORE OF THE FOLLOWING:
A submittal is required for NRC action/review/information based on:
Commitments Regulations Needs of an NMPC Initiative A submittal is not required, but the issue represents implementation of a prior commitment or regulation/other requirement.
The results of an internal initiative that typically are made available (not submitted) to the NRC for their review/information.
An industry initiative that has been committed to on behalf of NMPC.
AND ONE OF THE FOLLOWING'ny issue whose development and/or implementation spans more than one quarter (i,e., three months).
QR Any issue which occurs more than once.
An item meeting the guidelines above may still be excluded from the 5-year plan.
This decision will typically be based on judgement considering the significance of the issue, the need for NMPC resources to complete the item, or expected NRC action following NMPC completion.
003351LL (p.
1 of 1l
~
ATTACHMENTB
~
RCE F l E
UNIT 1:
10CFR20/RP Program/Amendment (BP 1.B.3, 502850) 3D Monicore Amendment (Tech Spec Amendment Requests)
B 80-13 Inspection - Core Spray Sparger and Piping (500456-02)
B 88-04 CS Pump/Recirc Line Operability Test (502086-07)
B 88-04 Install Recirc Line (502086-09)
B 88-08 (Thermal Stratification) Emergency Cooling System Modification (502202)
B 93-03 (Vessel Water Level Inst.) Response/Actions (503735)
Blue Markup Process Review (502932-01)
Containment H202 Monitoring Modification (502937-01)
CRD Stub Tube Cracking (BP 1.A.5)
DBR (Design Basis Reconstitution) Program Complete (BP 3.C.6)
DCRDR/RG 1.97 - Follow up Report (502672)
Delete RETS Amendment (Tech Spec Amendment Requests)
Document RG 1.97 Compliance (500489-03)
Economic Analysis Corporate Commitments (BP 2.C.4)
EDG Reliability Program (502603-07)
EDSFI Followup Actions (502906) - Milestones h
ERDS Implementation (502866)
Feedwater,Control Valve Replacement (Engineering Plans)
FSAR Update (Regulations)
FSAR Verification Program (502589-02) 003351LL Ip.
1 of 7)
I
ATTACHMENTB RCE F I E
~NiT 1: (Continued)
GL 87-05 Reactor Head Cavity Drain Line Flow Switch (500675-05)
GL 88-14 (IA) Report - Phase 2 (BP 1.A.3, 502470) - Generic Letter on Instrument Air System GL 88-16 Hardened Vent Mod (502533)
GL 88-20 (IPE) Report (503647)
Gl. 88-20 (IPEEE) Report (BP 1.A-.3, 503647-03)
- Generic Letter on Individual Plant Evaluations for External Events 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 (502539-07)
GL 89-13 (SW) Report (BP 1.A.3, 502539) - Generic Letter on Service Water Systems GL 89-15 (ERDS) Implementation (502569-02)
GL 91-11 (Proc.) Response (502862)
GL 92-01 (RPV Structural Integrity) Response (502938-00)
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 (BP 2.A.1, 502818)
IVISIV Room Access - Vital Area Requirements (502692) 0033 51LL (p. 2 of 7)
')
ATTACHMENTB R
E FI E
QNI7 1: (Continuedi NUREG 0619-Feedwater Flow Report (502772-01)
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 (502096)
RPV (Reactor Pressure Vessel) Beltline Installation/Test (503186-01)
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 1.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) 003351LL Ip. 3 of 7)
0
'i
~
ATTACHMENTB S
RCE F IS E
QNIT 1: (Continued)
Tech Spec Improvement Report (BP 3.C.3)
Temperature Monitoring - Thermal Cycling in Emergency Condenser (502202-11)
Turbine Efficiency Mod (Engineering Plans)
Two CR (Control Rod) Withdrawal Mod (502898-01)
VT Feedwater Spargers/UT Nozzle (502415)
QIIIIT2:
10CFR20/RP Program/Amendment (BP 1.B.3, 502850) 24-Month Cycle Plan (BP 2.B.1) 31-Day Position Verification Amendment (Tech Spec Amendment Requests) 4-Year Simulator Certification (502687-02)
Advanced System Training (503232)
B 93-03 (Vessel Water Level Inst.) Response/Actions (503735)
"B" Transformer Root Cause (502874-01)
BOP Annunciator Cabinets (502869-08)
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)
Design Basis Program (BP 3.C.9)
Drawdown Design/Amendment (503154-05)
EDG Reliability Program (502603-06) 003351LL lp. 4 of 7)
-l e
'I
ATTACHMENTB OURCE F t UE
@NIT 2: (Continuedi EOP Inspection Items (502822-04) - Emergency Operating Procedure Inspection Open Items ERDS Survey (502569-01)
- Emergency Response Data Systems ERDS Implementation (502569)
Erosion-Corrosion (502540) - Part of the Service Water Generic Letter FSAR Update (Regulations)
GEXL Amendment (Tech Spec Amendment Requests)
- Phase III (BP 1.A.3, 502470) - Generic Letter on Instrument Air System GL 88-20 (IPE) Report (502532-01)
- Generic Letter on Individual Plant Evaluations GL 88-20 (IPEEE) REPORT (BP 1.A.3, 502532-03) - Generic Letter on Individual Plant Evaluation for External Events 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)
ILC Procedure. Rewrite (502780-02)
Increased MSIV Leakage Amendment (Tech Spec Amendment Requests)
Inoperable Seismic Monitor Amendment (Tech Spec Amendment Requests)
Issue Refuel Outage Preplan (BP 2.B.4) 003351 LL (p. 5 of 7)
ATTACHMENTB OURCE F l E
tiNIT2: iContinuedi Leakage Detection (IGSCC) Amendment (Tech Spec Amendment Requests)
License Condition 2.C(3)b.ii (See Shoreham Fuel Amendment)
Maintenance Procedure Rewrite (502941-01)
Maintenance Rule Implementation (BP 2.A.1, 502817)
NUREG-1455 Procedure Deficiencies Corrected (502869-11)
Outage Safety Review (BP 1,A.2, 502908)
PM (Plant Manager') Plan for Success (502941-09)
Power Uprate Amendment (Tech Spec Amendment Requests; GE Settlement)
Power Uprate Amendment/Implementation (BP 2.A.2; GE Settlement)
Radioactive Effluent Release Report (503296-05)
Refuel Outage Amendments '(Tech Spec Amendment Requests)
- Select Based on Outage Needs Remove PM (Plant Manager) Approval of Procedure (Tech Spec Amendment Requests)
Right-Sized USAR (BP 3.C.2)
Revise SORC/SRAB Requirements Amendment (Tech Spec Amendment Requests)
SBO (Station Blackout) Action Complete (502413-22)
SBO (Station. Blackout) Procedure Changes (502413)
Shoreham Fuel'Amendment (Tech Spec Amendment Requests) 003351 LL Ip. 6 of 7)
I P
~
ATTACHMENTB ~
S R
E Fl UE gNI~2: (Continued)
Tech Spec Improvement Report (BP 3.C.3)
UPS Modifications (502882-03)
- Review of UPS Loads and Replacement of some of the UPS Units Involved in the 8/13/91 SAE.
~T:
10CFR20/RP Program/Amendment (BP 1.B.3, 502850-00) 5-Year Plan Presentation to NRC (BP 3.C.1)
Access Authorization Rule (502847)
Annual Emergency Exercise (EP Plans)
Business Plans 1994-1997 (BP 2.C.2)
ERF Audit Corrective Actions (503335, 502348)
FFD (Fitness for Duty) Report (502656)
GL 91-14 (ENS Phones) Upgrade (502902)
Integrated Long-Range Plan (BP 2.C.3)
ISTA (BP 3.A.1) - Internal SALP-Type Assessment LLRW (Low Level Radwaste) Storage Plan (BP 1.C.1)
NUMARC Procurement Initiative (502682-01)
Occupational. Exposure Report (503401)
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)
Reliability Centered Maintenance Program (BP 2.A.1)
Rightsizing Complete (BP 2.E.1) 003351LL Ip. 7 of 7I
1
ENCLOSURE 5
September 23, 1993
SUBJECT:
NRC PO'HER REACTOR - EMBRZTTLEMENT DATA BASE (PR-EDB)
SURVEILLANCE DATA UPDATE FOR NMP1 During recent efforts involving Generic Letter 92-01, Niagara Mohawk has discovered that the NRC's PR-EDB does not contain the most updated surveillance data for NMP1.
The current PR-EDB database entries for NMP1 were extracted from References
[1] and
[2] as indicated in the PR-EDB.
The information contained in References
[1] and [2] was provided by Niagara Mohawk to the NRC in a letter from C. V. Mangan to D. B. Vassallo, dated August 15, 1985.
Report NMEL-90001, "Nine Mile Point Unit 1 Surveillance Capsule Program,"
January.
1991, contains the latest data and provides resolution of the previously docketed material mix-up issue for NMP1. Based on the Staff's request, a copy of this report was transmitted to the NRC on August 30,1991 (NMP1L 0604).
As discussed in NMEL-90001, all previous surveillance reports for NMP1 have been superseded by the NMEL-90001 Report.
In order to avoid any confusion regarding pending or future submittals on the integrity of the NMP1 reactor vessel, the NMEL-90001 Report should be made available to ORNL for entry into the PR-EDB.
In addition, the report should also be provided to the NRC contractor currently working on Revision 3 to Reg.
Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials."
References
[1]
- Stahl, D., Manahan, M.P.,
Landow, M.P., Jung, R.G.,
and Lowry, L.M., "Examination, Testing and Evaluation of Irradiated Pressure Vessel Surveillance Specimens from the Nine Mile Point Nuclear Power Station," Final Report to Niagara Mohawk Power Corporation, July 18, 1984.
[2]
- Manahan, M.P., Failey, M.P.,
and Landow, M.P., "Examination, Testing and Evaluation of the Nine Mile Point-Unit 1 30-Degree Azimuthal Surveillance
- Capsule, Final Report to Niagara Mohawk Power Corporation, April 23, 1985.
4
September 28, 1993 described in Enclosure 5.
The NRC staff thanked NHPC for bringing this to our attention and agreed to provide a copy of Enclosure 5 to Oak Ridge National Laboratory so that the updated information can be entered into the data base.
Original signed by:
Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Attendees 2.
List of License Amendment Requests Unit 1
3.
List of License Amendment Requests Unit 2 4.
Five-Year Plan of NRC Related Issues 5.
Details of NMPC's findings Regarding Surveillance Data for NHP-1 Reactor Vessel cc w/enclosures:
See next page
- Licensee's handouts send onl to:
Distribution:
Docket File*
NRC
& Local PDRs*
PDI-1 Readi ng*
T. Hurley/F. Hiraglia, 12/G/18 J. Partlow, 12/G/18 S.
Varga J.
Calvo R. A. Capra C.
Vogan D. Brinkman*
J. Henning*
V. HcCree, 17/G/21 C.
Cow ill, RGN-I*
PDI-1:LA PDI-1: PH PDI-1: PH PDI-1: D CVo an
)-
DBrinkman.avl JMennin RACa ra 37 93 z7 93 5qp 93 1
ee93 OFFICIAL RECORD COPY FILENAME: G: iNHP1-2iNMPI-2.HTS
ab a
September 28, 1993 described in Enclosure 5.
The NRC staff thanked NHPC for bringing this to our attention and agreed to provide a copy of Enclosure 5 to Oak Ridge National Laboratory so that the updated information can be entered into the data base.
Original signed by:
Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Attendees 2.
List of License Amendment Requests Unit 1
3.
List of License Amendment Requests Unit 2 4.
Five-Year Plan of NRC Related Issues 5.
Detail s of NMPC's findings Regarding Surveillance Data for NHP-1 Reactor Vessel cc w/enclosures:
See next page
- Licensee's handouts send onl to:
Distribution:
~Docket File*
NRC 5 Local PDRs*
PDI-1 Reading*
T. Hurley/F. Hiraglia, 12/G/18 J. Partlow, 12/G/18 S.
Varga J.
Calvo R. A. Capra C.
Vogan D. Brinkman*
J. Henning*
V. HcCree, 17/G/21 C.
Cow ill, RGN-I*
PDI-1: LA PDI-1: PM PDI-, 1: PH PDI-1: D CVo an DBrinkman.avl JHennin
~
RACa ra 0/k7 93
/~7/93 9qp 93 P8 93 OFFICIAL RECORD COPY FILENAME: G: iNMPI-2iNMP1-2.MTS
t p
~