ML17055D475
| ML17055D475 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/04/1988 |
| From: | Benedict R, Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-87-09, GL-87-9, NUDOCS 8801140135 | |
| Download: ML17055D475 (20) | |
Text
January 4, 1988 Docket Nos:
50-220 and 50-410 LICENSEE:
FACILITIES:
SUBJECT:
DISTR UBT ION NRCPDR Local PDR RCapra Niagara Mohawk Power Corporation (NMPC)
MHaughey RBenedict Nine Mile Point Nuclear Station, Units 1 and 2
PDI-I Rdg.
SUMMARY
OF MEETING WITH NIAGARA MOHAWK POWER CORPORATION ON NOVEMBER 17, 1987 TO DISCUSS LICENSING ISSUES FOR NINE MILE POINT, UNITS 1 AND 2 Qfogaa OGC EJordan JJohnson ACRS(10)
HBClayton JPartlow The NRC staff met with representatives of Niagara Mohawk Power Corporation (the licensee) on November 17, 1987 to discuss licensing issues for Nine Mile Point, Units 1 and 2
(NMP-1 and NMP-2).
Enclosure 1 contains a list of meeting attendees.
Enclosure 2 is a copy of the meeting agenda.
Enclosure 3
contains details relating to the discussion of each of the issues listed on the agenda.
Besides the issues listed on the agenda, also discussed was the subject of maintaining a negative pressure in the NMP-2 secondary containment with respect to the outside ambient air.
Recent calculations by the licensee have determined that, although pressure transmitters may indicate that a 0.25 inch vacuum is being maintained in the vicinity of the pressure transmitter (as required by Technical Specifications),
the 0.25 inch vacuum may not be being maintained in the upper region of the containment where there is a greater temperature differential with respect to the ambient temperature.
The licensee maintained that, although it is considering relocating the pressure transmitters, it does not believe that the Technical Specifications have been violated.
This issue is expected to be a subject of a future meeting.
Mary F. Haughey, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II Robert A.Benedict, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II
Enclosures:
As stated cc:
See next page 8801.i40i35 8SO>oe I
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Mr. 'C.
V.. Mangan Niagara Mohawk Power Corporation Nine Mil-e Point Nuclear Station
. Unit 2 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner E 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, Hew York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau Hew York State Department of Law 2 World Trade Center
'ew York, New York 10047 Resident Inspector Hine Mile Point Nuclear Power Station P. 0.'ox 99
- Lycoming, New York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, Hew York 13212 Don Hill Niagara Mohawk Power Corporation Suite 550 4520 East West Highway
- Bethesda, Maryland 20814 Regi ona 1 Administrator, Regi on I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Paul D.
Eddy New York State Public Serice Comnission Nine Mile Point Nuclear Station-Unit II P.O.
Box 63
- Lycoming, New York 13093 Mr. Richard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, New York 12210 Mr. Richard Abbott, Unit 2 Station Superintendent Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P.
Q.
Box 32
- Lycoming, NY 13093 Mr. Thomas Perkins, General Supt.
Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.
Box 32
- Lycoming, NY 13093
Mr. C. V.'Mangan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.
1 CC:
Troy B. Conner, Jr., Esquire Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.
W.
Washington, D.
C.
20006 Frank R. Church, Supervisor Town of Scriba R.
D. f2
- Oswego, New York 13126 Mr. Thomas Perkins General Supt.-Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, Hew. York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
, Lycoming, New York 13093 Mr. Gary Wilson, Esouire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, Hew York 13202 Regional Administrator, Region I U.'. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Mr. Thomas W.
Roman Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093
Enc1osure 1
NOYEMBER 17, 1987 MEETING TO DISCUSS LICENSING ISSUES FOR NMP-1 AND NMP-2 ATTENDEES J.
Johnson R. Benedict M. Haughey P.
Francisco R.
Capra K. Thomas A. Za11nick ORGANIZATION NRC NRC NRC NMPC NRC NMPC NMPC
/
DV OZ '87 89:57 NNPC SYRACUSE NUCLEAR DIVISION Enclosure 2
NRR -
NHPC HEETING AGENDA I.
Introductions
t
. ~G1 T
A.
NHPC Licensing Organization B.
Coordination between NRR, Region and NHPC C.
Schedule for Future NRR Inspectiqns D.
Processing of License'mendments III. Unit 1 Issues A.
Status of Appendix 3 Submittal B.
RAGEMS C.
SPDS D.
Status of Unit 1 ISI/IST Programs E.
Reload 11 Submittal F.. License Extension Submittal G.
Spiral Off Loading SER H,
Items for 1988 Outage 1)
Technical Specification Refuel Definition 2)
Technical Specification ATHS 3)
Technical Specification - Min. Temperature for Pressurization I.
Priority Review Issues 1)
Service Hater Discharge z)
Technicai Specification - Coastdown 3928G
IV.
Unit 2 Issues e A.
Hestinghouse Fuel Submittal B.
24-h1onth Refueling Cycle C.
FSAR Update D.
Technical Specification Changes expected to b submitted by end of year 1)
Setpoint Changes as a result of Startup Tests 2)
GL 87-09 3)
Battery Corrosion, change to refleci GT~ (corrvsivn vr resistance) 4)
HSIV Leakage Increase E.
Priority Review Issues 1)
Downcomers 2)
Service Hater Technical Specifications 3)
ISI /I ST 3928G
EncIosure 3
Detailed Discussion of A enda Items from the ovem er eet n
on scenssn Issues or one s
e o nt n1ts an
~6" "
1 T
A.
NHPC Licensing Organization
'aresh Aqarwal (formerly of Stone and Webster Engineering Corp.)
has been assigned the lead responsibility for the on-site licensing activities at the NHP site.
'ete Francisco is the licensing lead at NHPC headquarters and the contact for SIMs.
'ike Hosier is the safety evaluation lead
'HPC expects to phase out consultants who are filling licensing positions.
B.
Coordination between NRR, Region and NHPC
'esident inspectors are the first line of contact.
C.
Schedule for Future NRR Inspections
'ew inspections are announced in advance unless they involve major effort and, therefore, would be more effective if pre-announced.
D.
Processing of License Amendments
'RR categorizing of amendment requests was discussed Category I:
Category 2:
Category 3:
Insufficient information:
return to licensee Simple request involving no significant hazards:
project managers will process (this category also includes reload analyses even though technical support is required)
Technical support required or no significant hazards finding cannot be made:
notice for prior hearing.
NMP-I ISSUES A.
Status of Appendix J Submittal The licensee is anxious for the results of the review of the Appendix J submittal as new valves reauired to pass Appendix J requirements have an 18 month lead time and the nexr. refueling outage is scheduled for Spring of 1988.
The staff expected to release an SER, at least in part, sometime in November.
B.
If NMP-I cannot meet Appendix J requirements as determined in the SER then NMPC may need to apply for a schedular exemption.
RAGEMS C.
D.
Because the RAGEMS system is somewhat unreliable the licensee has been using an alternate system but can return to RAGEMS if necessary.
In their letter of June 29, 1984 the licensee took exception to including a Technical Specification on RAGEMS and, therefore, the Technical Specifications do not contain action statements in the event the RAGEMS system is inoperable.
It is, therefore, unclear how Generic Letter 83-36 is being met with the RAGEMS system inoperable.
SPDS The SPDS (safety parameter display system) was declared operable following the Spring of 1986 refueling outage.
Status of Unit 1 ISI/IST Programs
'ST (Inservice Testing)
Program responses are expected to be issued by the end of November.
E.
'he staff expects to issue soon a request for additional information concerning the ISI (Inservice Inspection)
Program.
Reload II Submittal The Safer Code is being used for the reload ll submittal.
The August 21, l987 submittal reflects a proposed new methodology to be used on current fuel.
The licensee plans to submit a new package on new fuel using the new methodology for reload 11.
License Extension Submittal The NMP-I license was issued for 40 years from the issuance of, the construction permit.
The licensee plans to submit a request for an extension to 40 years from the issuance of the operating license (an extension of about 4 years) patterned after requests from other licensees.
G.
Spiral Off Loading SER A May 7, 1987 letter from General Electric indicates that core loading should be done starting from the source range monitors (SRMs) rather than from the core center because of SRM sensitivity.
The licensee's evaluation determined there was no substantial safety hazard associated with this change.
H.
Items for 1988 Outage l.
Technical Specification (TS) Refueling Definition - As hydrostatic testing will need to be done at 221'F this refueling outage, the licensee will need a change to the Technical Specifications to allow them to do scram time testing at the higher temperature.
2.
TS ATMS - The licensee will be submitting a change to allow them to use enriched boron to meet the requirements of 10 CFR 50.62.
3.
TS Minimum Temperature for Pressurization
- The NRC expects to issue an evaluation of this issue shortly.
4.
Core spray piping system (not on agenda)
- The licensee wants to use a weld overlay to repair IGSCC indications; an exception to the ASME code may need to be submitted in accordance with 10CFR50.55a.
I.
Priority Review Issues The staff is presently reviewing submittals on the sleeve repair of the service water discharge and a TS change on coastdown.
NMP-2 ISSUES A.
Mestinghouse Fuel Submittal The licensee presently plans to use 8 lead test assemblies in unlimited regions of the core for the first core reload.
A meeting to discuss this issue is planned for early January.
B.
24 Month Refueling Cycle The licensee plans to submit Technical Specification changes to extend 18 month surveillances to 24 months to accomodate the 24 month refueling cycles.
These changes will bc reviewed on a case-by-case basis.
C.
FSAR Update Licensing staff will meet at a later date to discuss the FSAR Update.
D.
Tcchnical Specification Changes I.
The licensee will be submitting setpoint changes determined during the power ascension program.
4 0
2.
The licensee plans to submit Technical Specification changes in accordance with Generic Letter 87-09.
3.
The licensee plans to submit a change to the Technical Specifications concerning the operability of batteries.
The Technical Specifications currently state that there will be no visible corrosion.
The proposed change will specify a resistance level to determine operability.
4.
The licensee plans to submit a Technical Specification change to increase the allowable leakage rate for the mainsteam isolation valves (MSIVs) and to increase the drawdown time.
As the control room doses, as calculated by the NRC, are presently at the limit, the licensee was told that in order to make the proposed changes acceptable, the doses needed to be reduced in other ways (e.g.
reduced bypass leakage for other valves).
E.
Priority Review Issues 1.
Downcomers - A meeting was held for December 7, 1987.
2.
Service Mater Technical Specifications - The licensee needs to submit additional information.
The licensee stated this information would be submitted by November 23, 1987.
3.
Inservice Testing (IST) - A meeting on IST is planned for December 3 and 4 on site.
4.
Inservice Inspection - A request for additional information was issued December 2,
1987 on the July 30, 1987 submittal from the licensee.
'