IR 05000336/1980010
| ML19336A453 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/25/1980 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19336A452 | List: |
| References | |
| 50-336-80-10, NUDOCS 8010230157 | |
| Download: ML19336A453 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-336/80-10 Docket No.
50-336 License No.
DPR-65 Priority
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Category C
Licensee:
Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 i
Facility Name:
Millstone Nuclear Energy Station, Unit #2 Inspection at: Berlin, Connecticut Inspection conducted:
July 28-30, 1980 Inspectors:
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- P- / 5~-70 A. E. Finkel, React 6r Inspector date signed date signed
date signed 8[M//f)
Approved by:
P w
S. D! Ebneter, Chief Engineering Support date sfgned Section No. 2, RC&ES Branch Inspection Summary:
Inspection on July 28-30, 1980 (Report No. 50-336/80-10)
Areas Inspected: Routine announced inspection of qualification data for the electrical equipment inside containment associated with the Reactor Coolant System, and Safety Injection and Containment Spray System as defined in the Millstone Nuclear Power Station, Unit No. 2 Class IE submittal of July 15, 1980.
The inspection involved 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> onsite by one regional based NRC inspector.
Results: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
801028o jy 7
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h DETAILS 1.
Persons Contacted Northeast Utilities
- Mr. L. Davison, Generation Engineering
- Mr. R. DeRosa, Generation Engineering
- Mr. R."Kacich, Licensing Mr. R. McCarthy, Engineering, Instrumentation and Control
Mr. R. McGinness, Licensing Mr. D. Nordquist, Quality Assurance i
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- Mr. A. Roby, Generation Engineering
- Denotes those present at the exit interview.
2.
IE Bulletin 79-01B Qualification Data Verification Insoection
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i The inspector on July 28-30, 1980 performed a verification inspection of i
the qualification ' documentation of the components listed in Table 1 of this report.
The inspection of the qualification documentation was per-formed in accordance with the inspection instruction entitled " Inspection Requirements for Verifying Reactor Licensee Responses to IE Bulletin No.79-018."
3.
Low Voltage Electrical Penetrations The licensee stated that the low voltage electrical penetrations, l
plant ID No. SWX, SWI, SEX, and SEI which are General Electric series 100 will be replaced with the Conax Model Type EC1, EC3, WC3 and WC5.
l The Conax penetrations were qualified as indicated in test report
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IPS 313.
The inspector reviewed the test and profile data which formed part of the IPS 313 report.
The test data indicated that the licensee's requirements were complied with.
The licensee stated that t.he replacement penetrations were scheduled to be installed during the August-September 1980 outage.
During this outage period the
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installation will be verified by the NRC.
l The inspector reviewed the General Electric qualification test l
report 25203-39026 for the Series 100 low voltage penetration and
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determined that they are qualified in accordance with Milestone 2 l
requi rements.
b.
ASCO Solenoid Valves This system uses the ASCO valve type 206-381-3F which was qualified as a generic family of valves in ASCO reports No. AQS21678/TR Revision B.
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The inspector reviewed this report and verified that the test data complies with the requirements of Millstone 2 profiles as listed in the July 16,1980 IEB 79-01B report.
~~'"ici~~NAMCO^timit Switches
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The inspector reviewed the Acme-Cleveland Development Company qua-lification report for the Namco Limit Switch EA-180 Revision 1 dated September 5, 1978 and EA-740 Revision 1 dated February 22, 1979.
The qualification report indicates that the profile requirements were complied with.
Table II list the valves that these limit switches are used on at the Millstone 2 site.
d.
Conax Connector The connector used on the Namco Limit Switches is a Conax connector part Nos. N-11001-32 and N-11001-33.
The Conax connector qualifica-tion is documented in a report entitled " Qualification Repott for Connector Modules for Arkansas Nuclear One Unit 2, Arkansas Power and Light Company", dated March 8, 1979.
(Conax Report No. IpS-409.)
The test data and profiles of this report are within the Millstone 2 profile envelope requirements.
e.
Cables The inspector reviewed the qualification report for the Kerite Cable
- Company prepared by the Franklin Institute Research Laboratories F-C4020-2 dated March 1975.
This report indicates that the test data and profiles are within the envelope requirements of Millstone 2.
Table III liststhe other cables and qualification reports associated with the cables for this site.
The data profiles for thase cables are within the Millstone 2 requirements for the containment environment and are listed in the July 16,1980 IE 79-01B submittal.
f.
Set Screw Connectors The inspector reviewed the qualification data referenced in letters GEE-78-358 dated July 18, 1978 and GEE-79-214 dated April 5,1979 which discusses LOCA testing and accelerated aging of Ideal set screw connectors. The parameters used in the tests referenced above are different from those specifically applicable to Millstone 2.
These differences are noted in Table IV.
They were reviewed by the inspec-tor and considered to be acceptable.
g.
Electrical Penetration Terminal Blocks General Electric's letters No. G-EH-8-16 and G-EH-9-141 state the environments that the CR-151 terminal block was tested to.
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qualification profiles that General Electric provided for these terminal blocks appear to be within the qualification requirements for the Millstone 2 site.
No items of noncompliance were identified.
Safety Injection (SI) and Containment Spray (CS) System
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The SI and CS systems contained components of the same type, or generic family type, as those components contained in the Reactor Coolant System.
The qualification data and documentation reviewed and discussed in para-graph 3 for the components of the Reactor Coolant System are also appli-cable to the components of the SI and CS system.
5.
General The following components have been identified as requiring licensee follow-up action as result of the review of the licensee's IEB 79-01B submittal.
System Component ID No.
Manufacture Engineered Safeguard Room Air Recirculating -
HV8306 Honeywell Damper Motor HV8312 Containment Spray Pump Motor - 4160 Volts P-43A General Electric P-43B a.
Damper Motor - The damper motor is a continuous operating component that provides damper positioning for the safeguard room ventilation system.
The licensee has been unable to obtain qualification data on this component.
The licensee has contacted the manufacturer to obtain qualification documentation.
If qualification documentation is not available, the licensee plans to qualify existing equipment or replace it with qualified equipment.
b.
Pump Motor - 4160 Volts - The Containment 3 pray Pump Motor require-ment for radiation was calculated as 8.11 x 10s rads.
Service con-ditions in the licensee specification for this motor (specification No. 7604-E-10, Revision II dated June 19, 1974) are:
Service Condition 40 years 450C 10 5 rads 1 month 45 C 106 rad.
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General Electric informed the licensee that this motor uses a MICAMAT BINDER material that is good for 4 x 10s rads.
The licensee is inves-tigating this problem with General Electric.
6.
Licensee Event Repcrt (LER)
As defined in item 6 of IE Bulletin 79-01B, "the licensee is required to submit an LER for any Class IE electrical equipment item which has been determined as not being capable of meeting environmental qualification requirements for service intended." The components identified in this report as being investigated, or to be verified by the licensee will be required to meet item 6 of IE Bulletin 79-01B if the information in the qualification documentation cannot be verified.
7.
Safety Evaluation Report Input
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The acceptability of qualification documentation identified in this report will be documented in the Safety Evaluation Report (SER) that is to be written for Millstone 2.
The SER is planned to be issued by February 1981.
8.
Exit Interview At the conclusion of the inspection on July 30, 1980, a meeting was held at the Berlin, Connecticut corporate office with representatives of the licensee.
Attendees at this meeting included personnel whose names are indicated by. notation (*) in paragraph 1.
The inspector summarized the results of the inspection as described in this report.
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Containment System Components Inside Outside Reactor _ Coolant System h*b "$anple Valve Electrical Penetration X
Limit Switches X
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. Conax Connector X
Set Screw Wire Connector X
Electrical Penetration -
Terminal Blocks X
Safety Injection and Con-tainment Spray Systems hf Olve S-628 Electrical Penetration X
Limit Switches X
Conax Connector X
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Set Screw Wire Connector X
Electrical Penetration -
Terminal Blocks X
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TABLE I Systems and Components Selected for Qualification Data Verification
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-Namco Limit Switch No.
Valve Identification Model EA-180 CH-515 S1-614 CH-516 SI-624 CH-517 SI-634 CH-518 SI-644 CH-519 SI-618 EB-88 S1-628 EB-89 S1-638 AC-5 S1-648 AC-6 Model EA-740 LRR-43.1 SSP-16.1 RC-003 GRR-11.1 RC-001 EB-91 CH-506 RC-002 EB-100 Table II-Installed Namco Limit Switches
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Manufacturer Type Qualification Report Kerite - FR Insulation, Control Cable FIRL F-C4020-2
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FR Jacket Anaconda - EPR Insulation Low Voltage Power FIRL F-C4350-3 CSPE Jacket Cable Rock Bestos' Company Instrument Cable, Cerro Data dated February 1,
- XLPE Insulation 1977 Newoprene Jacket Boston Insulated Wire Instrument Cable Letter of October 16, 1972 (BIW) RG-59R, (Coax)
with data RG 71B/U Table III Electrical Cables
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GEE-78-358 Environments GEE-79-214 Millstone 2 LOCA:
Temperature 2680F 2890F
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Chemical Spray 2640 PPM 1720 PPM Radiation 5 x 106 Rads 1 x 107 Rads
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S Table IV i
Ideal Set Screw Wire Connectors Test Data of GEE-78-358 and GEE-79-214 vs Millstone 2 Environmental Profiles
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