IR 05000220/1981009
| ML17053C677 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/14/1981 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053C676 | List: |
| References | |
| 50-220-81-09, 50-220-81-9, NUDOCS 8106160627 | |
| Download: ML17053C677 (34) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE. OF INSPECTION AND ENFORCEMENT Region I Report No.
50-220/81-09 Docket No.
50-220 License No.
DPR-63 Priority Category Licensee:
Niagara Mohawk Power Corporation 300, Erie Boulevard West Syracuse, New York 13202 Facility Name:
i Mi Inspection at'-
Scriba, New York Inspection conducted:
April 20 - 23, 1981 Inspectors: e/. 4-Zewc/)
. A. McBr'earty, Reactor tospector
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date signed date signed A
Approved by:
L. E. Tripp', Chief, Materials and Processes Section, Engineering Inspection Branch date signed
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date signed Ins ection Summar
Inspection on April 20-23, 1981 Re ort No'. 50-220 81-09 A~Id:
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Feedwater Nozzles and Core Spray Spargers including review of procedures, records, observation of work in progress and interviews with licensee representatives.
The inspection involved 23 inspector-hours onsite by one regional based NRC inspector.
Results:
No items of noncompliance or deviations wer e identified, Region I Form 12.
(Rev. April 77)
81 961868V
DETAILS Persons Contacted Nia ara Mohawk Power Cor oration
"M: D'Angelo, Licensing
"D. K. Greene, Licensing F.. A. Hawksley, Supervisor - Mechanical
& Maintenance T., E.
Lempges, V.P. Nuclear Generation
- T. J. Perkins, General Superintendent, Nuclear Generation
"T. Roman, Station Superintendent General Electric Com an D. L. Richardson, Engineer - NDE Level III Nuclear Ener Services Inc.
S.
L. Foote, NOE Engi.neer
~CT C
C. Grant, V.P. Engineering and Design
"Denotes those present at the exit meeting.
2.
Nondestructive Examination of Feedwater Nozzles During routine inservice inspection (ISI) activities the four feedwater nozzles were ultrasonically examined by Nuclear Energy Services, Inc.,
(NES), the licensee's ISI contractor.
The nozzles are identified as follows:
Northeast nozzle (NE) - 45 azimuth position Southeast nozzle (SE)
135 azimuth position Southwest nozzle (SM)
225 azimuth position Northwest nozzle (NM) - 315 azimuth position The SE nozzle was found to display an ultrasonic (UT) indication requiring further evaluation.
A plot of the UT data showed a reflector approxi-mately l-l/2 inches long and 3/4 inch deep located at an existing excavation in the nozzle inner surfac The excavation resulted from eliminating defects by grinding subsequent to the removal of nozzle cladding in 1977.
The nozzle was examined using liquid penetrant and ultrasonic techniques after the grinding operation in 1977, and was found to be free of defects at that time.
Based.
on the 1981 ultrasonic examination results, NES recommended to the licensee that the SE nozzle sparger be removed and that a visual examination and a liquid penetrant examination be performed of the nozzle inner surface.
prior to sparger removal the licensee requested the General Electric Company (GE) to perform an ultrasonic examination of the nozzle using techniques developed by GE for the examinations done in 1977.
GE complied with the request and their examination, done by personnel associated with the 1977 examinations, verified the NES findings Following sparger removal a liquid penetrant examination of the nozzle inner surface was performed, part of which was observed by the inspector.
The examination, done by GE personnel, revealed no indications in the area of the suspected ultrasonic reflector, but the inspector noted small indications at other locations.
The indications were documented and subsequently removed by surface grinding.
The licensee reported that a maximum of 20 mi ls of metal was removed to eliminate the penetrant indications.
Indication removal was confirmed by liquid penetrant examina-tion of the final surface.
The inspector suggested to the licensee that, as a supplement to the ultrasonic and liquid penetrant examinations, a magnetic particle examination of the carbon steel nozzle surface at the location of the
'uspected defect would aid in evaluating the 'condition of the nozzle.
A magnetic particle examination of the suspected area was performed by GE personnel using a
DC magnetic yoke and dry magnetic particles.
The examination was done after completion of the final liquid penetrant examination and revealed an indication free surface.
In addition to the observation discussed above, the inspect'or interviewed GE and NES personnel with respect to nondestructive examinations which were performed on the feedwater nozzles in 1977, 1979 and during the current refueling outage'upplemental to the interviews, the inspector reviewed examination procedures, reports and data associated with the various examinations.
This was done to ascertain compliance with licensee commitments and regulatory requirements.
The inspector's review included the following:
Summary Report - 1977 Feedwater Sparger Replacement Project-Nine Mile Point Nuclear Station Unit 1, dated November 1977.
Automation Industries Drawing Number 80E4020, Feedwater Nozzle-Full Scale NES UT calibration data sheets for the UT examinations on March 14, 1981 of the feedwater nozzles
- GE liquid penetrant examination reports dated April 20, 1981 and April 21, 1981 GE magnetic particle test report dated April 22, 1981 GE report of the UT examination of the SE feedwater nozzle inner radius and bore, dated March 23, 1981 GE magnetic particle examination procedure number 18XA1701, revision
GE UT examination procedure number E50YP33, revision 0 for feedwater nozzle, zone
Prior to the inspector's site visit the licensee had met with NRC licensing (NRR) staff members and reported the detecti'on of the UT indication in the 'SE nozzle and of two indications in the SW nozzle at the location of an existing excavation similar to the SE nozzle grindout.
The NRC had suggested further examination of the SW nozzle based on the location of the reported indications.
The licensee informed the inspector of his report to NRR and stated that the report was in error in that the SW nozzle indications were not coincident with the excavation.
He further stated that his ISI contractor, after reexamination, concluded that the indications were of a geometric nature and were considered non-relevant.
The inspector's review of the ISI contractor's report and associated data sheets confirmed the above.
On April 22, 1981, the inspector contacted the NRR Licensing Project Manager for Nine Mile Unit 1 to apprise him of licensee's actions to date and to discuss the inspector's findings relative to the SW nozzle.
At the exit meeting the inspector stated that available information did not indicate the need for the examination of additional feedwater nozzles as specified by NUREG 0619.
He further stated that the final determination of this would be based on the evaluation and disposition of the ultrasonic indication reported in the SE nozzl The licensee stated that additional nondestructive examination of the SE nozzle incorporating eddy current techniques was planned upon the arrival on site of the necessary equipment..
The examination results are expected to aid in the disposition of the UT indication.
The inspector stated that the item is considered unresolved pending evalua-tion and disposition of the UT indication and NRC review of the associated documentation.
(220-81-09-01)
During a telephone conversation on Nay 4, 1981 with the licensee, the inspector was informed that, following an eddy current examination of the suspected area, an evaluation and disposition was. made of the UT indication in the SE nozzle.
The eddy current results were negative.
The inspector stated that the item-would remain open pending the inspector's review of the associated documentation.
3.
Core S ra S ar er Examination Visual examination of the core spray spargers using underwater TV equip-ment was done by the CTS Corporation.
Data were recorded on video tape.
and evaluated by General Electric Company personnel.
An indication noted on the "A" sparger was evaluated to be a crack and was reported by the licensee to the. NRC.
The inspector reviewed selected tapes to ascertain the clarity and resolution of the images used to determine the severity of the crack.
The following tapes were included in the inspector's review:
Tape number 81-7 Tape number 81-25 Tape number 81-35 The reviewed tapes contained various views of the cracked portion of the
"A" sparger above nozzle number 26A and of the calibration fixture used to determine the maximum resolution attained by the equipment.
The inspector found that a one mil diameter wire was adequately displayed and the clarity of the tapes used to determine crack severity was consistent with the calibration.
The inspector noted that the reported crack appeared to emanate from an area of the sparger which showed apparent grinding marks and suggested a possible weld repair of the are In response to the inspector's question the licensee stated that he would examine relevant records for the sparger to determine whether welding was done on the pipe.
On April 29, 1981, the licensee representative contacted the inspector by telephone to report that all available records had been reviewed and that no evidence of a weld repair was found.
The inspector stated that he had no further questions regarding this item.
4.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 2.
5.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on April 23, 1981.
The inspector summarized the purpose and scope of the inspection and the findings.
In addition to those designated in paragraph 1, Mr. S.
Hudson, NRC Resident Inspector, attended the exit meetin ~S AEVI,.
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Oocket No. 50-Z20 NUCLEAR REGULATORY COIVIMISSION
REGION I
631 PARK AVENUE KING OF PRUSSIA, PENNSYlVANIAI9406 M~Y 0 8 1983 Niagara Mohawk Power Corporation ATTN:
Mr. T.
E.
Lempges Vice President Nuclear Generation 300 Erie Boulevard West Syracuse, New York 13202 Gentlemen:
Subject:
Meeting 50-220/81-08 This refers to the meeting held at our request at the Nine Mile Point facility, Scriba, New York on April 22, 1981 to discuss the findings of the NRC Region I Systematic Assessment of Licensee Performance (SALP) Program evaluation board relating to your performance in conducting activities authorized by NRC License No. OPR-63.
The meeting was attended by you, Mr. Perkins, Mr. Roman, and other members of your staff, and by myself, and other members of the NRC Region I staff.
Subjects discussed included the results of a review board composed of myself and the NRC Region I senior staff.
It is our view that this meeting was beneficial and improved mutual under-standing of your program and our inspection efforts.
In accordance with Section 2.790, of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Oocument Room.
No reply to this letter is required; however, should you have any questions concerning this matter, we will be pleased to 'discuss them with you.
Sincerely, Boyce H. Grier Oirector
Enclosure:
Office of Inspection and Enforcement Inspection Report Number 50-2ZO/81-08 with Appendix
REGION I==
PERFORMANCE EVALUATION
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE Nine Mile Point Nuclear Station Unit 1'EGION I EVALUATION BOARD MEETING Facility:
Nine Mile Point Nuclear Station, Unit
Licensee:
Niagara Mohawk Power Corporation Unit Identification:
Docket No.
50"220 Reactor Information:
License No./Date of Issue OPR-63 December 26, 1974 Unit No.
NSS:
General Electric MWT:
1850 Assessment Period:
February 1,
1980 to January 31, 1981 Evaluation Board Meeting Date:
April 1, 1981 Review Board Members:
Other NRC Attendees:
B.
H. Grier, Director, Region I J.
M. Allan, Deputy Director, Region I E. J. Brunner, Acting Director, Division of Resident and Project Inspection, RI R. J.
Bores for G.
H. Smith, Director, Division of Emergency Preparedness and Operational Support, RI, R. T. Carlson, Oirector, Enforcement and Investigation Staff, Region I J.
W. Devlin for W.
G. Martin, Assistant to the Director, Region I P. J.
Polk, Licensing Project Manager, Operating Reactors Branch 2, NRR H. B. Kister, Chief, Reactor Projects Section 1C S.
O. Hudson, Resident Inspector, Nine Mile Point Unit L P. J.
Knapp, Chief, Facility Radiological Protection Section, OETI J.
R. White, Radiation Specialist, Facility Radiological Protection Section, OETI J.
T. Wiggins, Reactor Inspector, Reactor Projects Section 1C
ATT HMENT 1 Nine Mile Point Unit
LICENSEE PERFORMANCE DATA Assessment Period:
Feb'ruary 1, 1980 to January 31, 1981 A.
Number and Nature of Noncom liance Items 1.
Noncompliance Category Violation Severity Level I Severity Level II Severity Level III Infraction Deficiency Severity Level IV Severity Level V
Severity Level VI Deviation
0
0
4
1
2.
Areas of Noncompliance Plants Operations Maintenance Committee Activities Fire Protection Radiation Protection Security Management Controls Design Changes and Modifications VIO/I/II/III/INF/OEF/ IY/V/VI/OEV o In/ o/ o / e / o / o/o/ o/ o 0 /0/ 0/ 0 / 0 /
1 / 0/0/ 1/ 0 0 /0/ 0/ 0 / 0 /
1 / 0/0/ 0/ 0 0 /0/ 0/ 0 / 2 / 0 / 0/0/ 0/ 0 0 /0/ 0/ 0 / 12/ 0 / 0/1/ 0/ 0 0 /0/ 0/ 0 /
1 / 0 / 0/0/ 0/ 0 2 /0/ 0/ 0 / 2 / 2 / 0/0/ 0/ 0 0 /0/ 0/ 0 / 0 / 0 / 0/0/ 0/
Nine Mile Point Unit 1 s
LICENSEE PERFORMANCE DATA Assessment Period:
February 1, 1980 to January 31, 1981 B.
Number and Nature of Licensee Event Re orts 1.
Type of Events A.
B.
C.
D.
E.
X.
Personnel Error Design Manufacturing, Construction/Installation Error External Cause Defective Procedures Component Failure Other
2
3
2 Total
2.
Causally Linked Events 10 events in 4 groups (3 groups of 2 events each; one group of 4 events further discussed in Functional Area No. 4)
3.
Licensee Event Reports Reviewed (Report Nos.)
LERs 80-05 through 81-01 C.
Escalated Enforcement Actions Civil Penalties EA-81-08,
$215,000 assessed:
Failure to comply with a TMI Lessons Learned Short Term Requirement.
Orders Order for Modification of License concerning environmental qualification of electrical components dated August 29, 1980, revised September 19, 198 Confirmatory Order of October 2, 1980, to confirm licensee commitments to implement requirements of IE Bulletin 80-17.
Order for Modification of License concerning environmental qualification of safety-related electrical equipment dated October 24, 1980.
Order for Modification of License (effective immediately)
and Order to Show Cause concerning a material false statement dated November 26, 1980; both subsequently withdrawn on March 20, 1981.
Order for Modification of License concerning BWR Scram Discharge System dated January 9,
1981.
Order for Modification of License and Grant of Extention of Exemption concerning suppression pool hydrodynamic loads dated January 13, 1981.
Immediate Action Letters 80-38 Confirms licensee commitments relative to the improvement of the radiation protection program.
80-40 Confirms licensee commitments relative to the Short Term Recommendations f'r Item 2.1.8.b of NUREG-0578.
80-53 Confirms licensee commitments relative to cer tain requirements of IEB 80-17 and the NRC Confirmatory Order dated October 2, 1980.
Mana ement Conferences Held Durin Past Twelve Months None Licensee Activities The plant operated at power throughout the assessment period except for several short outages including one in March in which the Safety and Relief valve acoustic monitoring system was installed, one in July due to a failure of the Main Output Transformer and one in December for ATMS Trip Hardware installation.
Ins ection Activities During the assessment period, 20 inspections were completed under the Operating Reactors Program.
These included 8 inspections by the Resident Inspectors, the Health Physics Appraisal, 'a special inspection of TMI Action Plan Category A items, a shipment inspection conducted by Region II at the Barnwell, South Carolina site and 9 inspections by the Regional Office Staff.
Inspections involved 1,367.5 inspector-hours onsit G.
Invest'i ation Activities One investigation was conducted during the assessment period to determine the basis upon which the licensee concluded that the Short Term Recommendation for Item 2. 1.8.b of NUREG-0578 was completed in compliance with licensee commitments.
The investigation involved 110 inspector-hours onsit A MENT 2 Nine Mile Point Nuclear Station Unit
INSPECTION PROGRAM CHANGES Functional Area Inspection Time and/or Scope Change From Prescribed Inspection Program Increase No Change Decrease 1.
Plant 0 erations 2.
Refuelin 0 erations 3.
Maintenance 4.
Surveillance 5.
Licensed 0 erator Training 6.
QA/
C 7.
Re or tin 8.
Committee Activities 9.
Procurement 10.
Fire Protection 11.
ISI/IST 12.
Desi n Chan es and Modifications 13.
Radiation Protection 14.
Environmental Protection 15.
Emer enc Pre aredness 16.
Radioactive Waste Mana ement 17.
Trans ortation X
18.
Securit and Safeauards 19.
Mana ement Controls x
I Re nal Director ate
0