ML17055E331
| ML17055E331 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/10/1988 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8811170277 | |
| Download: ML17055E331 (6) | |
Text
DISTRIBUTION Local PDR RCapra OGC-Rockville BGrimes CVogan (NMP-1)
November 10, 1988 Docket No. 50-220 Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.
1 LICENSEE:
FACILITY:
SUBJECT:
SUMMARY
OF MEETING WITH NIAGARA MOHAWK POWER CORPORATION ON SEPTEMBER 19, 1988 TO DISCUSS THE INSERVICE INSPECTION (ISI)
PROGRAM FOR NMP-1 NRCPDR PDI-1 Rdg
'Haughey EJordan ACRS(10)
RBenedict RHerman MHum GJohnson BBrown JBHenderson RMcBrearty JJohnson HBClayton On September 19, 1988, the NRC staff met with representatives of Niagara Mohawk Power Corporation (the licensee) to discuss the ISI program for Nine Mile Point Unit 1.
Specifically, the status of inspections and relief requests for the first 10 year program was discussed.
The inspections required by the 10 year program were required to be completed by the end of the 1986 outage.
- However, as a result of problems discovered with the program in December 1987 the plant has remained in an extended outage while the extent of these problems are identified and inspections are completed.
In a letter dated April 1, 1987, the licensee submitted relief requests applicable to the first 10 year program.
- However, as a result of the recent review of the program, the licensee indicated that additional relief reauests would be submitted and a number of relief requests submitted April 1, 1987 would be revised.
Consequently, the staff halted its review of the ISI program for NMP-1 in August 1988.
During the meeting on September 19, 1988 the licensee indicated that it expected to complete the inspections needed to conclude the first 10 year interval by the end of October 1988.
The licensee also discussed in detail the status of and the expected changes to the relief requests as listed in Enclosure 1.
A number of the relief requests will not be able to be finalized by the licensee until the inspections are completed and the inaccessible welds are identified.
The staff indicated that it would consider granting relief on the basis of inaccessibility ot impracticability as allowed by the regulations.
The staff further indicated that any relief that was requested solely because an inspection was missed during the first outage would not be considered.
The licensee indicated that it planned to submit the revised and new relief requests within 3 months after the inspections were completed.
Furthermore, it indicated that it planned to restart NMP-1 before the requests were submitted and approved.
The staff indicated that this position had been discussed during the August 30, 1988 licensing status
- meeting, however the staff had not yet agreed that restart could occur before the reliefs were granted.
The staff requested that the relief requests be submitted as they are finalized.
The staff also indicated that additional discussion would be required concerning the subject of restarting NMP-1 before the relief requests were approved.
Subsequent to the meeting the staff informed the licensee SS11170277 SS1110 (DR ADOCK 05000220 PDC fo
that relief requests for the first 10 year period would need to be approved before the plant was restarted.
The licensee indicated that the revised program for the second 10 year interval would be submitted by the end of the year if the outage is not still in progress and that no examinations would be double counted (applied to both 10-year intervals).
During the meeting the licensee also discussed its position on ASME Code Interpretation X-1-86-30.
The licensee has identified a number of component supports that reouire corrective action.
It was the licensee's position that if the structural integrity of the system is not affected by the identified condition (i.e., the support is not needed for the structural integrity of the system) then no additional supports will be examined as a result of the problem identified.
ASME Section XI requires sample sizes to be expanded if problems are found.
The staff stated that while it may be acceptable to determine the support is not needed for structural integrity, the sample size should still be expanded in accordance with the code when a problem is found.
A copy of meeting attendees is included as Enclosure 2.
original signed by
Enclosures:
As Stated Mary F. Haughey, Project Manager Proiect Directorate I-I Division of Reactor Projects, I/II cc: w/enclosures:
See next page PDI-1 LA:CVogan fgl~0/88
~ ~"I PDI-1 PM:MHaughey:dig
)i/g /88 PDI-1 PD:RCapra gl/P/88
P E
t Mr., C. V. Mangan Niagara Mohawk Power Corporation Nine Mi oint Nuclear Station, Unit No.
1 CC:
Pr. Troy B. Conner, Jr.,
Esquire Conner Pi Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.
W.
Washington, D.
C.
20006 Mr. Frank R. Church, Supervisor Town of Scriha R.
D. P2
- Oswego, New York 13126 Mr. James L. Willis General Supt.-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 Mr. 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 Mr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York l3093 Mr. Peter E. Francisco, Licensing Niagara Mohawk Power Cnrporation 301 Plainfield Road
- Syracuse, New York 13212 Charlie Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul D.
Eddy New York State Public Service Commission Nine Mile Point Nuclear Station-Unit 2 Post Office Box 63
- Lycoming, New York 13093
F