ML20044D930
| ML20044D930 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/17/1993 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-92-08, GL-92-8, TAC-M85581, NUDOCS 9305210115 | |
| Download: ML20044D930 (5) | |
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UNITED STATES (lo
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May 17, 1993 Docket No. 50-219 k
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Mr. John J. Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 l
Dear Mr. Barton:
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - RESPONSE TO GENERIC LETTER 92-08, " THERM 0-LAG 330-1 FIRE BARRIERS," (TAC NO. M85581)
By letter dated April 15, 1993, you provided a response to Generic Letter (GL) 92-08 for Oyster Creek Nuclear Generating Station. Your response states that i
the Thermo-Lag fire barriers installed at Oyster Creek Nuclear Generating Station were qualified by the vendor based on the vendor's understanding of the NRC guidance in existence at the time of installation and that the fire barrier configurations installed at the plant are consistent with the qualification test assembly configurations. -
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In your letter you stated that the values chosen for cables protected by Thermo-Lag 330-1 were based (according to TSI Brochure 7.14) on a combination of tests and analyses.in accordance with IPCEA/ NEMA Publication P-54-440, Cables in Open-Top Cable Trays, and NEMA publication No. WC 51-1975, c
Ampacities Cables in Open-Top Cable Trays. The staff noted that the above references are applicable to cable tray installations not the application (i.e., cables in conduit) stated in the subject response. Therefore, the staff would request that you provide within 30 days of receipt of this letter the following information for additional clarification:
1.
A copy of the TSI Brochure 7.14 and other related documentation i
which would assist in the identification of the TSI test report (s) used as a technical basis for the ampacity derating values 7.3%
(1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire barrier) and 10.3% (3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barrier) for cables in conduit enclosed by Thermo-Lag 330-1 material.
a 2.
Please state what industry standard (e.g., IPCEA, NEMA) is applicable in the ampacity determination for cables in conduit at Oyster Creek.
Although Thermo-Lag barriers were evaluated and may have been considered
.l qualified, the results of recent tests and inspections indicate that further actions are now necessary to address fire endurance and ampacity derating of
-t Thermo-Lag barriers. Your response states that appropriate actions to resolve
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coordinated by NUMARC and you would apply the results of the industry program,
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when completed, to the Therro-Lag 330-1 installations at Oyster Creek Nuclear Generating Station. Compensatory measures for these inoperable barrier are in place and will remain in place until the fire barriers can be declared operable. Your response to GL 92-08, however, did not provide a schedule by which corrective actions would be completed.
In your response to GL 92-08 you indicated that the actions necessary to restore (or confirm) the operability of these barriers will be based on the results of the NUMARC program. The staff expects that licensees referencing this program, will review the testing results and, within 30 days after the completion of this test program, inform the NRC of the actions necessary and the schedule for restoring the operability of these fire barriers.
For those plant specific or unique configurations that are not bound by the NUMARC program, please provide within 30 days from the receipt of this letter, your schedules for site specific fire endurance testing of these unique configurations and the implementation of any potential barrier upgrades resulting from this testing.
In accordance with the reporting requirements of GL 92-08, you are also requested to confirm in writing, completion of the corrective actions.
l The information requested by this letter is within the scope of the overall burden estimate in Generic Letter 92-08 which was an average of 300 person-hours for each addressee's response. This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, Original signed by Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation cc: See next page
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Mr. John J. Barton May 17,1993 coordinated by NUMARC and you would apply the results of the industry program, when completed, to the Thermo-Lag 330-1 installations at Oyster Creek Nuclear Generating Station. Compensatory measures for these inoperable barrier are in place and will remain in place until the fire barriers can be declared operable. Your response to GL 92-08, however, did not provide a schedule by which corrective actions would be completed.
In your response to GL 92-08 you indicated that the actions necessary to restore (or confirm) the operability of these barriers will be based on the results of the NUMARC program. The staff expects that licensees referencing _
this program, will review the testing results and, within 30 days after the completion of this test program, inform the NRC of the actions necessary and the schedule for restoring the operability of these fire barriers.
For those plant specific or unique configurations that are not bound by the NUMARC l
program, please provide within 30 days from the receipt of this letter, your schedules for site specific fire endurance testing of these unique configurations and the implementation of any potential barrier upgrades resulting from this testing.
In accordance with the reporting requirements of GL 92-08, you are also requested to confirm in writing, completion of the corrective actions.
The information requested by this letter is within the scope of the overall burden estimate in Generic Letter 92-08 which was an average of 300 person-hours for each addressee's response. This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, I
Y Alexa der W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page
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Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station CC*
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts &-Trowbridge e/o U.S. Nuclear Regulatory Commission 2300 N Street, NW.
Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering CN 415 BWR Licensing Manager (renton, New Jersey.08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop:
Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731
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