ML20011A571
| ML20011A571 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/30/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008G042 | List: |
| References | |
| NUDOCS 8110220032 | |
| Download: ML20011A571 (4) | |
Text
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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
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Docket Nos. 50-295
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and 50-304 COMMONWEALTH EDISON COMPANY
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(Zion Station, Unit Nos. I and 2)
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EXEMPTION I.
The Commonwealth Edison Company.the licensee) is the holder of Operating License Nos. DPR-39 and DPR-48 (the licenses) which authorize operation of the Zion Station, Unit Nos. 1 and 2 located in Zion, Illinois, at steady state reactor core power levels not in excess of 3250 megawatts thermal (rated power).
These licenses provide, among other things, that they are subject to all rules, regulations and Orders of the Commission now or hereafter in effect.
II.
Section 50.54(o) of 10 CFR Part 50 requires that primary reactor containments for water cooled power reactors be subject to the requirements of Appendix J to 10 CFR Part 50. Appendix J contains the leakage test requirements, schedules, and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment.
Appendix J was published on February 14, 1973 and in August 1975, each licensee was requested to review the extent to which each facility met the requirements.
On September 29, 1975, Commonwealth Edison Company (CWE but now referred to as CECO) submitted their evaluation of the Zion Station Unit Nos.1 and 2, Dresden' Station Unit Nos.1, 2, and 3, and Quad Cities Station Unit Nos.1 and 2.
This T
I( o T r e e T 2_. #
7590-01 i Exemption addresses only the Zion Station Unit Nos. I and 2; the remaining Stations will be addressed by separate Exemptions, if necessary. The CECO submittal for the Zion Station was supplemented by letters on January 31, 1977, May 11, 1977, and July 7,1980.
In these submittals, CECO requeshed that certain penetrations and components be exempted from Appendix J requirements.
The Franklin Research Center, as consultant to the NRR, has reviewed the licensee's submittals and prepared a Technical Evaluation Report on their findings. The NRC staff has reviewed this report and in its Safety Evaluation Report dated September 30, 1981, the staff has concurred in the report's bases and findings. The exemption requests Tound to be acceptable are as follows:
1.
CECO requested an exemption to perform local valve leakage rate tests (Type C tests) prior to the integrated prim' ry containment leakage rate a
test (Type A test) and to back-correct the results of the Type A test with the results of the Type C test. This is an exemption to the method of leakage calculation and based on our evaluation is conservative in that all measured local leakage from the Type C tests will be assumed to be in a direction out of the containment when back-correcting the results of the Type A test. Without this exemption, the 1.icensee estimates an additional three days would be required at refueling outages without gaining test accuracy nor additional reliability of the containment leak testing. We agree that additional time would be required and would be an unnecessary cost in outage time for the licensee and in replacement power cost to the public.
Therefore, this exenption should be granted.
_e
I j
7590-01 4
, 2.
CECO requested an exemption to exclude nitrogen line isolation valves A0V-SI 8880 from Type C testing. Our evaluation concluded that there was insufficient justification for the exemption and that these valves should be included in the Type C testing program. However, we are advised by CECO that Type C testing of these valves (one on each unit) will require the installation of special high pressure valves which cannot be done until the refueling outages scheduled for the spring of 1982 for Unit 1 and fall of 1982 for Unit 2.
This is due to the lead time required to engineer and purchase the quality valves, supports 'and connections. This schedule, if approved, will require an exemption of Type C testing of the valve in Unit 2 during the refueling outage scheduled to begin in September 1 981. Hithout this exemption, the Unit 2 refueling outage scheduled to begin in September 1981 would be extended until a suitable procedure and equipment could be obtained to conduct the test.
This valve in Unit 2 was last tested in July 1980 in the Type A test. Based i
on the acceptable tests results to date of these valves which has indicated no unacceptable leakage, and the unnecessary cost in outage time for the licensee and replacement power costs to the public, the exemption should be granted to extend the Type C testing requirement on Unit 2 until the fall 1982 refueling outage. No exemption is raquired for Unit 1.
o 7590-01
. III.
Accordingly, the Comission has determined that, pursuant to 10 CFR 50.12, an exemption is authorized by law and will not endanger life or property or the comon defense and security and is otherwise in the oublic intemst. The re-fore, the Comission hereby approves the exemption request identified above.
The NRC staff has determined that the granting of this exemption wil.1 not result in any significant environmental impact and that pursuant to' 10 CFR 51.5(d)(4), an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.
OR THE NUCLEAR REGULATORY COMMISSION r
a e ector Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland titis 30th day of September,1981.
Attachments:
1.
Safety Evaluation Report j
2.
Technical Evaluation Report i
l l
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