IR 05000220/1990021
| ML17056B120 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/07/1990 |
| From: | Anderson C, Bhatia R, Roy Mathew NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056B119 | List: |
| References | |
| 50-220-90-21, 50-410-90-23, NUDOCS 9011200219 | |
| Download: ML17056B120 (14) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION I
50-220/90-21 Report Nos. 50-410/90-23 50-220 Docket Nos.
50-410 DPR-63 License Nos.
NPF-69 Licensee:
Nia ara Mohawk Power Cor oration Facility Name:
Nine Mile Point Nuclear Station Units 182 Inspection At:
Scriba New York and Salina 'Meadows-Cor orate Office New York Inspection Conducted:
October 9-12 1990 Inspectors:
R.
K. Mathew, Reactor Engineer, Plant Systems Settion, EB, DRS date R. Bhatia, Reactor Engineer, Plant Systems Section, EB DRS ti I/9o date Approved by:
//g go C. J.
Anderson, Chief, Plant Systems Section date Engineering Branch, DRS, RI Ins ection Summar
Ins ection on October 9-12 1990 Combined Re ort Nos.
50-220/90-21 and 50-410/90-23)
Tt i action on previously identified inspection findings.
Results:
No violations or deviations were identified.
Of the eight unresolved items reviewed, five items were closed.
Three items remained 'unresolved.
These are discussed in sections 3.0 and 4.0.
9011200219 90110+
PDR ADOCK 05000220
PNU
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DETAILS 1.0 Persons Contacted 1. 1 Nia ara Mohawk Power Cor oration K. Thomas, Supervisor, Site Licensing J.
T. Pavel, Engineer, Site Licensing G. Montgomery, Technical Assistant to Plant Manager
"A. Pinter, Site Licensing
"G. Brownell, Nuclear Regulatory Compliance C. Becknam, Manager, QA Operations M. Dooley, Supervisor Regulatory Compliance
"R. B. Abbott, Station Superintendent, Unit 2
- K. Dahlberg, Station Superintendent, Unit
- G. J.
Doyle, NMPC, Quality Assurance
"L. Dick, NMPC, Quality Assurance
'K. B. Thomas; NMPC Licensing J.
R. Jirousek, EQ Manager A. Freeland, Electrical Engineer A. Julka, Assist.
Manager, Electrical and Controls D. J. Jakubowski, Electricl Engineer 1.2 U.S. Nuclear Re viator Commission W. Cook, Senior Resident Inspector R.'emps, Resident Inspector
- Denotes personnel present at the exit meeting on October 12, 1990.
2.0
~Pur ose The purpose of this inspection was to review and verify the licensee's corrective actions for previously identified NRC findings.
3.0 Followu of Previous Ins ection Findin s
Unit 2 3. 1 Cl osed Unreso1 ved Item 50-410/88-32-01 During the previous RG 1.97 instrumentation inspection, the inspectors noted that the range for fuel zone level instruments, 2ISC*LI13A and B installed in the control room did not agree with the FSAR.
The range of the variable was found to be -165 to +35 inches of water, whereas the range specified by the FSAR was 230.69 to 430.69 inches of wate e
During this inspection, the inspectors noted that the licensee reviewed the design and determined the. as-built condition to be correct.
FSAR Table 7.5.2 was revised to reflect the actual field condition of -165 to
+35 inches of water.
The inspector verified the document changes and instruments at the control room and determined that this documentation was adequate to resolve the issue.
This item is closed.
3.2 Closed Unresolved Item 50-410/88-32-02 This item pertains to the lack of sufficient documentation for the RG 1.97 instrumentation range for cooling water flow to the ESF system.
During the previous inspection, the inspectors noted that the range for instruments 2SWP'FI13A and B was 0-8000 gpm; whereas the FSAR specified 0-10,000 gpm.
For instruments 2SWP*FI76A, B and 2SWP*FI535, i't was noted that the ranges were 0-1400 gpm and; 0-1000 gpm respectively whereas the FSAR specified 0-860 gpm During this inspection, the inspectors noted that the licensee reviewed the design and determined that the range (0-10,000 gpm for instruments 2SWP'FI13A and B) specified in the FSAR to be correct and meets the recommended zero to 110 percent design flow range specified by RG 1.97.
The instrument scales for these instruments were replaced to match the design requirement.
FSAR Table 7.5.2 was revised to reflect the actual field condition of 0-1400 gpm and 0-1000 gpm for instruments 2SWP*FI76A, B and 2SWP'FI535 respectively.
The inspector verified the documentation and instruments at the control room and determined that the licensee adequately addressed the NRC'concerns.
This item is closed.
3.3 Closed Unresolved Item 50-410/88-32-03 This item pertains to the lack of sufficient documentation for the RG 1.97 instrumentation range for Low Pressure Coolant Injection ( LPCI) System Flow.
During the previous inspection, the inspectors noted that the range for instruments 2RHS*FI14A, 2RHS*FI14B and C
was 0 to 10,000 gpm; whereas the FSAR specified 0 to 8,400 gpm'and
to 8,000 gpm respectively.
Also, the documentation did not establish the recommended 0-110 percent design flow range specified by RG 1.97.
During this inspection, the inspectors noted that the licensee reviewed the design and determined that the as-built condition (0-10,000 gallons)
to be correct and it meets the recommended 0-110 p'ercent design flow range specified by RG 1.97.
FSAR Table 7.5.2 was revised by the licensee to reflect the actual field condition.
The inspector verified the documentation and instruments at the control room and determined that the licensee adequately addressed the NRC concerns.
This item is close e
3.4 0 en 0 en Item 50-410/88-201-01 During previous inspection 88-201, the NRC inspector identified problems concerning testing of safety-related molded case circuit breakers at NMP Unit 2.
Specifically, licensee's preventive maintenance procedure N2-EPM-GEN-V582 did not provide adequate acceptance criteria for the magnetic (instantaneous)
trip tests.
Additionally, the procedure required setting the adjustable trip to the minimum position (maximum excluded) for testing and then returning the trip setting to the as-found position prior to installation in the plant.
Also, Niagara Mohawk Power Corporation could not indicate in any design documents where the actual trip settings should be for any particular installation.
During this inspection, the inspector noted that the test procedure N2-EPM-GEN-V582 was revised to incorporate the necessary acceptance criteria for magnetic trip tests.
The licensee is in the process of adding relevant trip setting information into the design drawings.
This item remains open pending licensee's completion of all the issues identified in Report 88-201-01 and NRC review of this information.
4.0 Followu of Previous Ins ection Findin s
Unit
4.1 Closed Unresolved Item 50-220/89-17-003 pertains to the lack of qualification documents for Raychem WCSF-N splice used to seal the Endevco Accelerometer connector assembly against moisture intrusion.
Also, the Wyle Assessment Report ( 17655-CON-1) for qualifying hard line cable to hardline cable contained a number of discrepancies.
During this inspection, the inspector reviewed the licensee's evaluation and analysis to support qualification of the above deficiencies.
The licensee's Qualification Report File No.
EQ236 and Wyle Report No.
17655-ACC-1 establish the qualifications of acceleromenter and cable splice installations.
The inspector noted that the qualification test configuration agrees with the actual installation and test results.
The test demonstrated the configuration qualification to operate in a LOCA/HELB environment.
The inspector reviewed the licensee's docu-ments 17655-SPL-1, SPL1. 1, ACC-1, ACC-1. 1 and CON-1. 1 which demonstrated the qualification of hard line to hard line cable splices.
These
.
documents provided a resolution to the discrepancies identified in Wyle Assessment Report No.
17655-CON-l.
In view of the qualification data furnished by the licensee, this item is closed.
4.2 0 en Unresolved Item 50-220/88-34-08 pertains to inadequate electrical and physical separation of the control room post accident monitoring (RG 1.97)
components.
During this inspection, the inspector noted that the licensee has not completed their evaluation regarding this issue.
The licensee stated that they are planning to send a
submittal to the NRC describing their action plan and commitment to resolve this issue.
This action is in response to the previous commitment made by the licensee in their submittal contained in NMPIL 0401 dated May 19, 198 This item remains open pending the licensee's completion of developing a technical basis for their variation from RG 1.97 and NRC review of this information.
4.3 0 en Unresolved Item 50-220/88-34-09 pertains to lack of identifi-cation of types A, B and C post accident monitoring instrumentation
~
at the control board in accordance with RG 1.97.
During this inspection, the inspector noted that the licensee has not completed their evaluation regarding this issue.
The licensee stated that they have identified instruments in the simulator to get the
'operator feed back and they are still in,. the process of. emluating a
suitable method to identify the instruments at the control board based on the operator response.
The licensee stated that they will notify.
the NRC regarding their action plan and commitment to resolve this issue.
This item remains open pending the licensee developing a technical basis for their variations from RG 1.97 and NRC review of this information.
Closed Unresolved Item 50-220/90-15-01 pertains to the review of the licensee's long term plan to ensure that 125 Vdc Battery 12 has sufficient capacity, including the aging factor, recommended by IEEE Standard 485 for new or replacement batteries for generating stations.
In this inspection, the inspector noted that the licensee now has a
long term plan to improve the existing 8% capacity margin of Battery 12 to some higher margin level.
The licensee's cur rent plan is to perform the capacity test on Battery 12 in the next refueling 'outage (1991) to determine the actual capacity margin.
Additionally, the licensee conceptual engineering feasibility study (Mod. Request No.
Nl-90-126) to improve the desired margins as recommended by IEEE 485 (by reducing non-IE loads and other options) is well underway.
This issue is being tracked by their Nuclear Commitment Tracking System, as item No. 503696-00 to be completed by September 1992.
Furthermore, the licensee is committed to maintain and monitor Battery 12, capacity as per the design requirements and as per surveillance procedure acceptance criteria NI-EMP-SB-4Y272, Rev.
1.
Since Battery 12 was replaced in the early part of this year and is relatively new with an 8% margin at pr esent, it should maintain 100%
capacity for the next several years without degradation under normal circumstances.
To assure the margin is maintained, a capacity test is scheduled for the next outage.
The inspector determined that the licensee is taking necessary steps to increase the present capacity margin as recommended by the IEEE standar.0 Unresolved Items Unresolved items are matters about which additional information is necessary in order to determine whether they are acceptable or they constitute a
violation.
Several unresolved items are discussed in detail under Section 3.0 and 4.0.
.D
~Ei fl The inspector met with the licensee's personnel denoted in Section 1.0 of this report at the conclusion of the inspection period on October, 12, 1990.
At that time, the scope of the inspection and the inspection results were summarized.
At no time, during the inspection, was written material given to the license e
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