ML20096A546
| ML20096A546 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/23/1984 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8408310163 | |
| Download: ML20096A546 (3) | |
Text
m-O Commonwealth Edison One First Nationri PFn. Chic go, litenora l Addt ss Rf ply to. Post Offics Box 767 Chicago. lilinois 60690 August 23, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Technical Specifications NRC Docket Nos. 50-454 and 50-455
Dear Mr. Denton:
The following information provides additional justification to support proposed Technical Specification changes for Byron Station as agreed upon at an August 13-16, 1984 meeting between the NRC and Commonwealth Edison.
1.
Subject:
Diesel Oil Sampling D. G. Eisenhut's letter to "All Applicants for Operating Licenses and Holders of Construction Permits for Power Reactors" dated July 5,1983 (Generic Letter 83-26) contained revised Technical Specification Surveillance Requirements for the diesel fuel impurity level tests.
Through discussions with other utilities, Byron Station was made aware of efforts being purcued by the Standardized Nuclear Unit Power Plant System (SNtPPS) to propose more prudent Technical Specification Surveillance Requirements with respect to diesel fuel impurity level tests. Having reviewed the NRC Technical Specification revisions and the recommended surveillance requirements / supporting technical justifications resulting from the SNLPPS efforts, we request that the Byron Unit 1 Nuclear Plant Technical Specifications Sections 4.8.1.1.2(d) and (e) be revised as previously submitted July 26, 1984.
In addition, we request Sections 4.7.1.2.3(b), 4.7.5.3(b) and 4.7.10.1.2(b) be revised in accordance with the above mentioned Section 4.8.1.1.2(d) and (e) to reference ASTM-D4057-1981 instead of ASTM.-D270-1975. This change in standards provides relief to the station in the sampling methods of the diesel oil due to the physical tank configurations.
The change will be consistent with the recommended surveillance requirements and supporting technical justifications,resulting from the SNtPPS effort as identified in the referenced report, for the sampling of new fuel prior to addition into the tank.
2.
Subject:
Containment Pressure Hi-1 In conformance with NUREG-0737 requirement II E.4.2 (Containment Isolation Dependability) we propose to reduce the Containment Pressure High Trip Setpoint as noted in Table 3.3-4 item Ic from 4 5.0 psig to 42.7 psig.
Based on this change, the Total Allowance value becomes 6.8 iisig.
8408310163 040823 od'/
PDR ADOCK 05000454 A
'A
R. Denton August 23, 1984 The proposed value of 2 7 PSIG is based on the follo i w ng considerations:
a.
Maximum normal containment pressure as given in Technical Specification 3.6.1.4 and also used as an annunciator setpuint in the Control Room 0.3 PSIG b.
Channel Statistical Allowance from Statistical Setpoint Study (CAW 6785) 1.4 PSIG
- c. -
Additional allowance to prevent spurious SI actuation due to instrtraent noise and potentially l
allowable Tech Spec limit. undetected pressure increases above the
_1.0 PSIG TOTAL 2.7 PSIG Technical Specification 3.3.1.We do not propose to reduce the Allowab psig as given in Safety Analysis.
This Allowable Value was determined in the Statistical Setpoint Study and is below the value of 6 8 used in the FSAR 3.
Subject:
Detector Plateau Curves Detector plateau curves are s7tained by the station t detector hi curve (i.e.gh voltage settings are in a plateau region of the response o verify that detector response is essentially independent of variations).
evaluating detector performance over many cycles as a means g
voltage potential detector degradation by comparison of current c on in of identifying curves to baseline cycle response curves ycle response alert the station to the need for a preve. This comparative review will failure appears likely.
ntative detector replacement if a SYSTEM INSTRUENTATION SURVEILLAtCE REQU
, REACTOR TRIP once per 18 months a channel calibration be performed on th u re that at least Intermediate Range and Power channels.
e Source Range, Table Notations (item 5) for each channel is:One of the items specified in the
" Detector plateau curves shall be obtained, evaluated a d manufacturer's data.
Neutron Flux channels the provisions of SpecificatioFor the Interme n compared to applicable for entry into MODE 2 or 1."
ns 4.0.4 are not
v
- H. R. Denton August 23, 1984 Manufacturer's data does not exist f Byron Station, therefore, Byron Stati or the specific detectors installed at 5 to read as follows
on proposes rewording Table Notation Subsequent plateau cu" Initial plateau curves shall be to the initial curves.rves shall be obtained, evaluated a dmeasu Neutron Flux channels the provisi For the Intermediate Range and P n
compared applicable for entry into MODE 2 or 1 "
ons of Specification 4.0.4 are not ower Range During initial startup, baseline Nuclear Instrumentation (Prior tSource Range channels A
o Core, Load) and again in test 2.52 3 Operational Alignment of Excore N e
Criticality).
Baseline plateau curves will be obt iuclear Instrumentation (P Alignment of Excore Nuclear InstrIntermediate Range a e channels in test 2.52.35Ea ned for the a
baseline data will be compared to umentation (At Full Power)., Thisplat channels as required by Table Notation 5 Operational this office.Should you have any questions reg e
arding this matter, please contact One si for NRC review gned original and fifteen copies of thi s letter are provided Very truly yours, T. R. Tramm MWW&
Nuclear Licensing Administrator 1m cc:
Byron Resident Inspector L. N. Olshan - NRR (Telecopy)
, 9116N
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