ML20248C152
| ML20248C152 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/31/1988 |
| From: | Pleniewicz R COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 89-0511, 89-511, NUDOCS 8906090278 | |
| Download: ML20248C152 (4) | |
Text
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C a;
N Commonwrith Edison
) Byron Nucizzr Ststion.
C'
' 4450 North German Church Road Byron, Hlinois 61010
, May 30,.1989 LTR BYRON 89-0511
-Dr., Thomas.E. Murley,' Director
-Nuclear Reactor Regulation
.U.S. Nucletar-Regulatory Commission
' Washington, D.C.'.20555 Dear Dr. Murley.
Pursuant to requirements to' report on an annual basis, as stated in:10 CFR 50.50, Byron Station (license numbers NPF-37 and NPF-66) has submitted a report describing changes, tests and experiments.and a summary of'.the safety evaluation of each. Byron Station is supplementing that report to include two additional changes. completed in 1988 that were inadvertently omitted from the annual: report.
Sincerely, a
I. Plenie icz R
i
. Station Manager
' Byron Nuclear Power Station RP/PV/bf Enclosures l-L. N. Olshan, NRR Project Manager cc:
Regional A&ninistrator NRC, Region III j.
NRC Resident Inspector,' Byron
.M.
C. Parker, IDNS
' CECO Distribution List 609027e 881231 C
R ADOCK 0500 g
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(1679Z/31)
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1 BYRON NUCLEAR POWER STATION
. ANNUAL 10 CFR 50.59 REPORT-SUPPLEMENT 1988 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 50-454 and 50-455 LICENSE NO. NPF-37 and NPF-66 i
(1679Z/31)
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MODIFICATION M6-1-87-126 l
l DESCRIPTION This modification replaced the welded closure plates on spare penetrations P-63, P 6's and P-74 with blind flanges. These can be removed during outages to allow access to the containment building for temporary cables and hoses.
SAFETY EVALUATION
SUMMARY
1.
The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the FSAR is not increased by this modification because the type of penetration added is the same as penetrations previously evaluated. These modified penetrations will be tested in accordance with 10CFR50, Appendix J.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR is not created because the modified penetrations are the same design as containment penetrations that currently exist as described in FSAR section 6.2.
3.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the modified penetrations will receive periodic tests in accordance with 10CFR50, Appendix J as required in Technical Specification 3/4.6.1.2. (1679Z/31)
MODIFICATION M6-1-87-140 DESCRIPTION This modification connects additional Post Accident Neutron Monitoring (PANM) system outputs to the process computer.
This provides hard copy print out of these parameters as required by Byron Station's commitment to RG 1.97.
SAFETY EVALUATION SUMMAEX 1.
The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the FSAR is not increased by this modification because the additional computer inputs provide additional information to the plant operators.
There are no changes to any system functional requirements.
2.
The possibility for an accident or malfunction of a different type than any previous evaluated in the FSAR is not created because the additional computer inputs do not effect any stfety related systems or components needed for safe reactor shutdown.
3.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the additional computer inputs are not included in the discussion of the basis for any safety limits as described in the Technical Specifications.
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(FINAL) (1679Z/31)
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